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by Copyright Arthur Bryan Crawford 2004 The Dissertation Committee for Arthur Bryan Crawford Certifies that this is the approved version of the following dissertation: Evaluation of the Impact of Non-Uniform Neutron Radiation Fields on the Dose Received by Glove Box Radiation Workers Committee: Steven Biegalski, Supervisor Sheldon Landsberger John Howell Ofodike Ezekoye Sukesh Aghara Evaluation of the Impact of Non-Uniform Neutron Radiation Fields on the Dose Received by Glove Box Radiation Workers by Arthur Bryan Crawford, B.S., M.S. Dissertation Presented to the Faculty of the Graduate School of The University of Texas at Austin in Partial Fulfillment of the Requirements for the Degree of Doctor of Philosophy The University of Texas at Austin December, 2004 Dedication I was born to goodly parents Harvey E. Crawford and Johnnie Lee Young Crawford Acknowledgements I would like to express my gratitude to Dr. Sheldon Landsberger for his vision in starting a distance learning program at the University of Texas at Austin and for his support and encouragement on this quest. I would like to thank my advisor, Dr. Steven Biegalski, for his support and encouragement even though the topic area was new to him. I would like to thank the members of my dissertation committee for finding the time to review this dissertation. To the staff of the Nuclear Engineering Teaching Laboratory I say thank you for your kindness and support during those brief times that I was on campus. A special thanks to my past and present group leaders, David Seidel, Eric McNamara, and Bill Eisele and my Division Leader, Lee McAtee, at Los Alamos National Laboratory, for their support in being allowed to use time and material resources at the Laboratory and for financial support in the form of tuition reimbursement and travel expenses. A special thanks to R.T. Perry for the discussions that we had at Los Alamos. To Jim Bland, a friend and mentor, for his insights and encouragement, a profound thanks of gratitude. And to my family for their moral support and prayers, may they be blessed in all of their endeavors. v Evaluation of the Impact of Non-Uniform Neutron Radiation Fields on the Dose Received by Glove Box Radiation Workers Publication No._____________ Arthur Bryan Crawford, PhD. The University of Texas at Austin, 2004 Supervisor: Steven Biegalski The effort to estimate the radiation dose received by an occupationally exposed worker is a complex task. Regulatory guidance assumes that the stochastic risks from uniform and non-uniform whole-body irradiations are equal. An ideal uniform irradiation of the whole body would require a broad parallel radiation field of relatively high-energy radiation, which many occupationally exposed workers do not experience. In reality, workers are exposed to a non-uniform irradiation of the whole body such as a radiation field with one or more types of radiation, each with varying energies and/or fluence rates, incident on the worker. Most occupational radiation exposure at LANL is due to neutron radiation. Many of these exposures originate from activities performed in glove boxes with nuclear materials. A standard Los Alamos 2x2x2 glove box is modeled with the source material being clean weapons grade plutonium. Dosimeter tally planes were modeled to stimulate the various positions that a dosimeter can be worn. An anthropomorphic phantom was used to determine whole body dose. Various geometries of source position and phantom vi location were used to determine the effects of streaming on the radiation dose a worker may receive. Based on computational and experimental results, the effects of a non-uniform radiation field have on radiation dose received by a worker in a glove box environment are: 1) Dosimeter worn at chest level can overestimate the whole body dose between a factor of two to six depending on location of the phantom with the source material close to the front of the glove box, 2) Dosimeter should be worn at waist level instead of chest level to more accurately reflect the whole body dose received, 3) Dose can be significantly higher for specific locations of the worker relative to the position of the source, 4) On the average the testes contribute almost 44% of the whole body dose for a male, and 5) Appropriate design considerations such as more shielding on the bottom of the glove box and controls such as the use of internal or external shielding can reduce the effects on dose from these non-uniform fields. vii Table of Contents List of Tables ........................................................................................................ xii List of Figures ........................................................................................................xv List of Figures ........................................................................................................xv Chapter 1: Introduction ...........................................................................................1 1.1 1.2 1.3 1.4 Estimation of Radiation Dose Received by a Glove Box Worker and its Associated Problems..............................................................................1 Current Problem Statement....................................................................4 Previous Studies Involving Estimation of Dose Received in Non-uniform Radiation Fields .....................................................................................9 Objectives ............................................................................................14 Chapter 2: Monte Carlo Calculations for Estimating Dose Received ..................16 2.1 2.2 2.3 2.4 Monte Carlo Method............................................................................16 Monte Carlo Sampling Techniques .....................................................20 Analog Monte Carlo Sampling ............................................................25 Modifications to Analog Monte Carlo Sampling.................................32 Chapter 3: Computational Experiment for Typical LANL Glove Box ................35 3.1 3.2 3.3 3.4 Objectives ............................................................................................35 Experimental Setup..............................................................................35 Computational Results .........................................................................53 Discussion of Results...........................................................................56 Chapter 4: Conclusions and Recommendations ...................................................85 4.1 4.2 General Discussion ..............................................................................85 Conclusions and recommendations......................................................85 Appendix A: Neutron Attenuation Provided By Several Different Materials.......89 Methodology for Determining the Attenuation of Different Neutron Shielding Materials ..............................................................................................90 viii Appendix B: Example Of Spreadsheet Format For Calculating Phantom Dose Estimates .......................................................................................................95 Appendix C: Neutron Radiation Field .................................................................102 Appendix C.1: .............................................................................................103 ANSI 1977 at 1 Foot with Source on Line S ..............................................103 Appendix C.2: .............................................................................................109 ANSI 1977 at 1 Foot with Source on Line V..............................................109 Appendix C.3: .............................................................................................115 ANSI 1977 at 1 Foot with Source on Line M.............................................115 Appendix C.4: .............................................................................................121 ANSI 1977 at 3 Foot with Source on Line S ..............................................121 Appendix C.5: .............................................................................................127 ANSI 1977 at 3 Foot with Source on Line V..............................................127 Appendix C.6: .............................................................................................133 ANSI 1977 at 3 Foot with Source on Line M.............................................133 Appendix C.7: .............................................................................................139 ANSI 1977 at 6 Foot with Source on Line S ..............................................139 Appendix C.8: .............................................................................................145 ANSI 1977 at 6 Foot with Source on Line V..............................................145 Appendix C.9: .............................................................................................151 ANSI 1977 at 6 Foot with Source on Line M.............................................151 Appendix D: Summary Of Estimated Doses Using Phantom's Dosimeter Lattice157 Appendix E: Estimated Dose Using Phantom's Dosimeter Lattice.....................176 Appendix F: Comparison Of Different Conversion Factors Using Dosimeter Reference Position ......................................................................................201 Appendix F.1: .............................................................................................202 Comparison at 1 Foot..................................................................................202 Appendix F.2: .............................................................................................207 Comparison at 3 Foot..................................................................................207 Appendix F.3: .............................................................................................212 ix Graphical Comparison at 1 Foot .................................................................212 Appendix F.4: .............................................................................................217 Graphical Comparison at 3 Foot .................................................................217 Appendix G: Comparison Of Whole Body Dose With Dosimeter With Various Tally Plane Doses.................................................................................................222 Appendix G.1:.............................................................................................223 ICRP 26 ANSI 1977 at 1 Foot .................................................................223 Appendix G.2:.............................................................................................228 ICRP 26 ANSI 1991 at 1 Foot .................................................................228 Appendix G.3:.............................................................................................233 ICRP 60 ANSI 1991 at 1 Foot .................................................................233 Appendix G.4:.............................................................................................238 ICRP 60 ICRP 74 at 1 Foot......................................................................238 Appendix G.5:.............................................................................................243 ICRP 26 ANSI 1977 at 3 Foot .................................................................243 Appendix G.6:.............................................................................................248 ICRP 26 ANSI 1991 at 3 Foot .................................................................248 Appendix G.7:.............................................................................................253 ICRP 60 ANSI 1991 at 3 Foot .................................................................253 Appendix G.8:.............................................................................................258 ICRP 60 ICRP 74 at 3 Foot......................................................................258 Appendix H: Distribution Of Average, Maximum, And Minimum Dosimeter Values .....................................................................................................................263 Appendix H.1: Detailed Tables for the Location of the Average, Maximum, and Minimum Dosimeter Values..............................................................264 Appendix H.2: Summary Tables for the Location of the Average Dosimeter Values ................................................................................................276 Appendix H.3: Summary Tables for the Location of the Maximum Dosimeter Values ................................................................................................278 Appendix H.4: Summary Tables for the Location of the Minimum Dosimeter Values ................................................................................................280 x Appendix I: Glove box Experiment at NETL.....................................................282 Glove box Experiment at NETL .................................................................283 Experimental Setup.....................................................................................283 Experimental Results ..................................................................................292 MCNP Model of NETL Experiment...........................................................296 Computational Results ................................................................................297 Comparison of Computational and Experimental Results..........................305 Appendix J: HSR-4 DOSIMETER DATA ..........................................................310 Appendix J.1 ...............................................................................................311 Appendix J.2 ...............................................................................................316 Appendix K: SOURCES 4C and MCNP Input Files...........................................318 Appendix K.1..............................................................................................319 Appendix K.2..............................................................................................321 Appendix K.3..............................................................................................327 Appendix L: Phantom Dose Estimates For NETL Glove Box Experiment ........372 References............................................................................................................377 Vita .....................................................................................................................383 xi List of Tables Table 1.1: Table 2.1: Table 3-1: Table 3-2: Table 3-3: Table 3-4: Table 3-5: Table 3-6: Table 3-7: Table 3-8: Table 3-9: Table A-1: Table A-2: Table B-1: Table B-2: Table B-3: Table B-4: Table B-5: Table B-6: Table D-1: Table D-2: Table D-3: Table D-4: Table H-5: Table H-6: Table E-1: Table E-2: Table E-3: Table E-4: Table E-5: Table E-6: Table F.1-1: Table F.1-2: Table F.1-3: Table F.1-4: Table F.1-5: Table F.1-6: Table F.1-7: Table F.1-8: Table F.1-9: Table F.2-1: Table F.2-2: Weighting Factor Determination Based on ICRP 26............................... 7 Tally Types. ........................................................................................... 28 Isotopic Content of Neutron Source. ..................................................... 42 Neutron Energy Spectrum...................................................................... 42 Neutron Quality Factors and Radiation Weighting Factors................... 47 Tissue Weighting Factors. ..................................................................... 48 ANSI-1977 Neutron Flux-to-Dose Conversion Factors. ....................... 49 ANSI 1991 Neutron Flux-to-Dose Conversion Factors......................... 50 ICRP 74 Neutron Flux-to-Dose Conversion Factors. ............................ 51 ANSI 1991 Neutron Flux-to-Dose Conversion Factors......................... 54 Contribution of Testes to Male Whole Body Dose................................ 78 Attenuation Coefficients for Various Materials Based on Dose............ 90 Attenuation Coefficients for Various Materials..................................... 93 Sheet 1: Input ......................................................................................... 96 Sheet 2 Phantom plus ICRP 26 Remainder ........................................ 97 Sheet 3: Colon-ULI................................................................................ 98 Sheet 4: Red Bone Marrow Near Bone Surface ................................. 99 Sheet 5: ICRP 60 Remainder ............................................................... 100 Sheet: EDE and ED.............................................................................. 101 Summary Phantom Dosimeter Tally Plane using ANSI 1977 at 1 Ft.. 158 Summary Phantom Dosimeter Tally Plane using ANSI 1991 at 1 Ft.. 161 Summary Phantom Dosimeter Tally Plane using ICRP-74 at 1 Ft...... 164 Summary Phantom Dosimeter Tally Plane using ANSI 1977 at 3 Ft.. 167 Summary Phantom Dosimeter Tally Plane using ANSI 1991 at 3 Ft.. 170 Summary Phantom Dosimeter Tally Plane using ICRP-74 at 3 Ft...... 173 Summary Whole Body Dose using ANSI 1977 at 1 Ft ....................... 177 Summary Whole Body Dose using ANSI 1991 at 1 Ft ....................... 181 Summary Whole Body Dose using ICRP-74 at 1 Ft ........................... 185 Summary Whole Body Dose using ANSI 1977 at 3 Ft ....................... 189 Summary Whole Body Dose using ANSI 1991 at 3 Ft ....................... 193 Summary Whole Body Dose using ICRP-74 at 3 Ft ........................... 197 MxxM1 ................................................................................................ 202 SxxM1.................................................................................................. 202 VxxM1 ................................................................................................. 203 MxxS1.................................................................................................. 203 SxxS1 ................................................................................................... 204 VxxS1 .................................................................................................. 204 MxxV1 ................................................................................................. 205 SxxV1 .................................................................................................. 205 VxxV1.................................................................................................. 206 MxxM3 ................................................................................................ 207 SxxM3.................................................................................................. 207 xii Table F.2-3: Table F.2-4: Table F.2-5: Table F.2-6: Table F.2-7: Table F.2-8: Table F.2-9: Table H.1-1: Table H.1-2: Table H.1-3: Table H.1-4: Table H.1-5: Table H.1-6: Table H.2-1: Table H.2-2: Table H.2-3: Table H.2-4: Table H.2-5: Table H.2-6: Table H.3-1: Table H.3-2: Table H.3-3: Table H.3-4: Table H.3-5: Table H.3-6: Table H.4-1: Table H.4-2: Table H.4-3: Table H.4-4: Table H.4-5: Table H.4-6: Table I-1: Table I-2: Table I-3: Table I-4: Table I-5: Table I-6: Table I-7: Table I-8: Table I-9: Table I-10: Table I-11: Table I-12: Table I-13: VxxM3 ................................................................................................. 208 MxxS3.................................................................................................. 208 SxxS3 ................................................................................................... 209 VxxS3 .................................................................................................. 209 MxxV3 ................................................................................................. 210 SxxV3 .................................................................................................. 210 VxxV3.................................................................................................. 211 ANSI 1977 at 1 ft - Location of Various Dosimeter Values................ 264 ANSI 1977 at 1 ft - Location of Various Dosimeter Values................ 266 ICRP 74 at 1 ft - Location of Various Dosimeter Values .................... 268 ANS1977 at 3 ft - Location of Various Dosimeter Values................ 270 I ANSI 1991 at 3 ft - Location of Various Dosimeter Values................ 272 ICRP 74 at 3 ft - Location of Various Dosimeter Values .................... 274 ANSI 1977 at 1 ft - Location of Average Dosimeter Values............... 276 ANSI 1991 at 1 ft - Location of Average Dosimeter Values............... 276 ICRP 74 at 1 ft - Location of Average Dosimeter Values ................... 276 ANSI 1977 at 3 ft - Location of Average Dosimeter Values............... 277 ANSI 1991 at 3 ft - Location of Average Dosimeter Values............... 277 ICRP 74 at 3 ft - Location of Average Dosimeter Values ................... 277 ANSI 1977 at 1 ft - Location of Maximum Dosimeter Values............ 278 ANSI 1991 at 1 ft - Location of Maximum Dosimeter Values............ 278 ICRP 74 at 1 ft - Location of Maximum Dosimeter Values ................ 278 ANSI 1977 at 3 ft - Location of Maximum Dosimeter Values............ 279 ANSI 1991 at 3 ft - Location of Maximum Dosimeter Values............ 279 ICRP 74 at 3 ft - Location of Maximum Dosimeter Values ................ 279 ANSI 1977 at 1 ft - Location of Minimum Dosimeter Values ............ 280 ANSI 1991 at 1 ft - Location of Minimum Dosimeter Values ............ 280 ICRP 74 at 1 ft - Location of Minimum Dosimeter Values................. 280 ANSI 1977 at 3 ft - Location of Minimum Dosimeter Values ............ 281 ANSI 1991 at 3 ft - Location of Minimum Dosimeter Values ............ 281 ICRP 74 at 3 ft - Location of Minimum Dosimeter Values................. 281 Setup of Dosimeters in Front of the Glove box. .................................. 288 TLD Readings in mrem by Badge Number. ........................................ 292 TLD Readings in mrem by location..................................................... 293 TED Readings in mrem by Dosimeter Number................................... 293 TED (Mean) Readings in mrem by Location. ..................................... 294 TED (Base) Readings in mrem by Location........................................ 294 Summary of Dosimeter Readings in mrem.......................................... 295 Neutron Radiation Field Measurements in ct/min by Location........... 296 Tally Number in Dosimeter Lattice by Location................................. 298 Calculated Dose by Location on Poly Slabs in mrem per 24 hr. ......... 298 Estimated Dose (mrem) with Dosimeter Lattice at 30.5 cm................ 303 Estimated Dose (mrem) using Dosimeter Lattice of Phantom at 91.5 303 Estimated Dose from Computational Phantom in mrem. .................... 305 xiii Table I-14: Table L-1: Table L-2: Table L-3: Table L-4: Comparison of Field Measurements with TLD and TED Readings.... 305 Phantom Dose Estimates at 1 ft using ICRP 26................................... 373 Phantom Dose Estimates at 1 ft using ICRP 60................................... 374 Phantom Dose Estimates at 3 ft using ICRP 26................................... 375 Phantom Dose Estimates at 3 ft using ICRP 60................................... 376 xiv List of Figures Figure 2.1: Figure 2.2: Figure 3-1: Figure 3-2: Figure 3-3: Figure 3-4: Figure 3-5: Figure 3-6: Figure 3-7: Figure 3-8: Figure 3-9: Figure 3-10: Figure 3-11: Figure 3-12: Figure 3-13: Figure 3-14: Figure 3-15: Figure 3-16: Figure 3-17: Figure 3-18: Figure 3-19: Figure 3-20: Figure 3-21: Figure 3-22: Figure 3-23: Figure 3-24: Figure 3-25: Figure 3-26: Figure 3-27: Figure 3-28: Figure 3-29: Figure 3-30: Figure 3-31: Figure 3-32: Figure 3-33: Figure 3-34: Figure 3-35: Figure 3-36: Figure 3-37: Figure 3-38: Figure 3-39: Figure 3-40: Discrete Probability Density Function................................................... 22 Discrete Cumulative Probability Density Function. .............................. 22 Shell Design A. ...................................................................................... 36 Shell Design B. ...................................................................................... 36 Typical 2x2x2 LANL Glove box Front View..................................... 38 Typical 2x2x2 LANL Glove box 3D View. ....................................... 39 Typical 2x2x2 LANL Glove box Side View. ..................................... 40 Longitudinal Medial View of Phantom and Dosimeter Tally Plane...... 41 Neutron Energy Spectrum for Clean WG Pu......................................... 43 Setup to Determine Neutron Radiation Field......................................... 44 Comparison of Neutron Flux-to-Dose Conversion Factors. .................. 52 Field at 30.5 cm with No Glove Box. .................................................... 57 Field at 30.5 cm with No Shielding Material in Glove Box. ................. 57 Field at 91.5 cm with No Glove Box. .................................................... 58 Field at 91.5 cm with No Shielding Material in Glove Box. ................. 58 Field at 183 cm with No Glove Box. ..................................................... 59 Field at 183 cm with No Shielding Material in Glove Box. .................. 59 Windows and Glove Ports Shielded with Source at 6 cm. .................... 62 Windows and Glove Ports Unshielded with Source at 6 cm. ................ 62 Windows and Glove Ports Shielded with Source at 15 cm. .................. 63 Windows and Glove Ports Unshielded with Source at 15 cm. .............. 63 Windows and Glove Ports Shielded with Source at 30 cm. .................. 64 Windows and Glove Ports Unshielded with Source at 30 cm. .............. 64 Windows and Glove Ports Shielded with Source at 45 cm. .................. 65 Windows and Glove Ports Unshielded with Source at 45 cm. .............. 65 Windows and Glove Ports Shielded with Source at 60 cm. .................. 66 Windows and Glove Ports Unshielded with Source at 60 cm. .............. 66 Windows and Glove Ports Shielded with Source at 75 cm. .................. 67 Windows and Glove Ports Unshielded with Source at 75 cm. .............. 67 Windows and Glove Ports Shielded with Source at 90 cm. .................. 68 Windows and Glove Ports Unshielded with Source at 90 cm. .............. 68 Windows and Glove Ports Shielded with Source at 105 cm. ................ 69 Windows and Glove Ports Unshielded with Source at 105 cm. ............ 69 Windows and Glove Ports Shielded with Source at 120 cm. ................ 70 Windows and Glove Ports Unshielded with Source at 120 cm. ............ 70 Shielded with Source at 135 cm............................................................. 71 Windows and Glove Ports Unshielded with Source at 135 cm. ............ 71 Windows and Glove Ports Shielded with Source at 150 cm. ................ 72 Windows and Glove Ports Unshielded with Source at 150 cm. ............ 72 MxxM1. ................................................................................................. 74 SxxM1.................................................................................................... 74 VxxM1. .................................................................................................. 74 xv Figure 3-41: Figure 3-42: Figure 3-43: Figure 3-44: Figure 3-45: Figure 3-46: Figure 3-47: Figure 3-48: Figure 3-49: Figure 3-50: Figure 3-51: Figure 3-52: Figure 3-53: Figure 3-54: Figure 3-55: Figure C.1-1: Figure C.1-2: Figure C.1-3: Figure C.1-4: Figure C.1-5: Figure C.1-6: Figure C.1-7: Figure C.1-8: Figure C.1-9: Figure C.1-10: Figure C.1-11: Figure C.2-1: Figure C.2-2: Figure C.2-3: Figure C.2-4: Figure C.2-5: Figure C.2-6: Figure C.2-7: Figure C.2-8: Figure C.2-9: Figure C.2-10: Figure C.2-11: Figure C.3-1: Figure C.3-2: Figure C.3-3: Figure C.3-4: Figure C.3-5: Figure C.3-6: Figure C.3-7: MxxS1.................................................................................................... 75 SxxS1. .................................................................................................... 75 VxxS1. ................................................................................................... 75 MxxV1. .................................................................................................. 76 SxxV1. ................................................................................................... 76 VxxV1.................................................................................................... 76 MxxM1- ICRP 26 ANSI 1977............................................................ 80 SxxM1- ICRP 26 ANSI 1977. ............................................................ 80 VxxM1- ICRP 26 ANSI 1977............................................................. 81 MxxS1- ICRP 26 ANSI 1977. ............................................................ 81 SxxS1- ICRP 26 ANSI 1977............................................................... 82 VxxS1- ICRP 26 ANSI 1977.............................................................. 82 MxxV1- ICRP 26 ANSI 1977............................................................. 83 SxxV1- ICRP 26 ANSI 1977.............................................................. 83 VxxV1- ICRP 26 ANSI 1977. ............................................................ 84 Source at 6 cm...................................................................................... 104 Source at 15 cm.................................................................................... 104 Source at 30 cm.................................................................................... 104 Source at 45 cm.................................................................................... 105 Source at 60 cm.................................................................................... 105 Source at 75 cm.................................................................................... 106 Source at 90 cm.................................................................................... 106 Source at 105 cm.................................................................................. 107 Source at 120 cm.................................................................................. 107 Source at 135 cm. ................................................................................. 108 Source at 150 cm. ................................................................................. 108 Source at 6 cm...................................................................................... 109 Source at 15 cm.................................................................................... 110 Source at 30 cm.................................................................................... 110 Source at 45 cm.................................................................................... 111 Source at 60 cm.................................................................................... 111 Source at 75 cm.................................................................................... 112 Source at 90 cm.................................................................................... 112 Source at 105 cm.................................................................................. 113 Source at 120 cm.................................................................................. 113 Source at 135 cm. ................................................................................. 114 Source at 150 cm. ................................................................................. 114 Source at 6 cm...................................................................................... 115 Source at 15 cm.................................................................................... 116 Source at 30 cm.................................................................................... 116 Source at 45 cm.................................................................................... 117 Source at 60 cm.................................................................................... 117 Source at 75 cm.................................................................................... 118 Source at 90 cm.................................................................................... 118 xvi Figure C.3-8: Figure C.3-9: Figure C.3-10: Figure C.3-11: Figure C.4-1: Figure C.4-2: Figure C.4-3: Figure C.4-4: Figure C.4-5: Figure C.4-6: Figure C.4-7: Figure C.4-8: Figure C.4-9: Figure C.4-10: Figure C.4-11: Figure C.5-1: Figure C.5-2: Figure C.5-3: Figure C.5-4: Figure C.5-5: Figure C.5-6: Figure C.5-7: Figure C.5-8: Figure C.5-9: Figure C.5-10: Figure C.5-11: Figure C.6-1: Figure C.6-2: Figure C.6-3: Figure C.6-4: Figure C.6-5: Figure C.6-6: Figure C.6-7: Figure C.6-8: Figure C.6-9: Figure C.6-10: Figure C.6-11: Figure C.7-1: Figure C.7-2: Figure C.7-3: Figure C.7-4: Figure C.7-5: Figure C.7-6: Figure C.7-7: Source at 105 cm.................................................................................. 119 Source at 120 cm.................................................................................. 119 Source at 135 cm. ................................................................................. 120 Source at 150 cm. ................................................................................. 120 Source at 6 cm...................................................................................... 121 Source at 15 cm.................................................................................... 122 Source at 30 cm.................................................................................... 122 Source at 45 cm.................................................................................... 123 Source at 60 cm.................................................................................... 123 Source at 75 cm.................................................................................... 124 Source at 90 cm.................................................................................... 124 Source at 105 cm.................................................................................. 125 Source at 120 cm.................................................................................. 125 Source at 135 cm. ................................................................................. 126 Source at 150 cm. ................................................................................. 126 Source at 6 cm...................................................................................... 127 Source at 15 cm.................................................................................... 128 Source at 30 cm.................................................................................... 128 Source at 45 cm.................................................................................... 129 Source at 60 cm.................................................................................... 129 Source at 75 cm.................................................................................... 130 Source at 90 cm.................................................................................... 130 Source at 105 cm.................................................................................. 131 Source at 120 cm.................................................................................. 131 Source at 135 cm. ................................................................................. 132 Source at 150 cm. ................................................................................. 132 Source at 6 cm...................................................................................... 133 Source at 15 cm.................................................................................... 134 Source at 30 cm.................................................................................... 134 Source at 45 cm.................................................................................... 135 Source at 60 cm.................................................................................... 135 Source at 75 cm.................................................................................... 136 Source at 90 cm.................................................................................... 136 Source at 105 cm.................................................................................. 137 Source at 120 cm.................................................................................. 137 Source at 135 cm. ................................................................................. 138 Source at 150 cm. ................................................................................. 138 Source at 6 cm...................................................................................... 140 Source at 15 cm.................................................................................... 140 Source at 30 cm.................................................................................... 140 Source at 45 cm.................................................................................... 141 Source at 60 cm.................................................................................... 141 Source at 75 cm.................................................................................... 142 Source at 90 cm.................................................................................... 142 xvii Figure C.7-8: Figure C.7-9: Figure C.7-10: Figure C.7-11: Figure C.8-1: Figure C.8-2: Figure C.8-3: Figure C.8-4: Figure C.8-5: Figure C.8-6: Figure C.8-7: Figure C.8-8: Figure C.8-9: Figure C.8-10: Figure C.8-11: Figure C.9-1: Figure C.9-2: Figure C.9-3: Figure C.9-4: Figure C.9-5: Figure C.9-6: Figure C.9-7: Figure C.9-8: Figure C.9-9: Figure C.9-10: Figure C.9-11: Figure F.3-1: Figure F.3-2: Figure F.3-3: Figure F.3-4: Figure F.3-5: Figure F.3-6: Figure F.3-7: Figure F.3-8: Figure F.3-9: Figure F.4-1: Figure F.4-2: Figure F.4-3: Figure F.4-4: Figure F.4-5: Figure F.4-6: Figure F.4-7: Figure F.4-8: Figure F.4-9: Source at 105 cm.................................................................................. 143 Source at 120 cm.................................................................................. 143 Source at 135 cm. ................................................................................. 144 Source at 150 cm. ................................................................................. 144 Source at 6 cm...................................................................................... 145 Source at 15 cm.................................................................................... 146 Source at 30 cm.................................................................................... 146 Source at 45 cm.................................................................................... 147 Source at 60 cm.................................................................................... 147 Source at 75 cm.................................................................................... 148 Source at 90 cm.................................................................................... 148 Source at 105 cm.................................................................................. 149 Source at 120 cm.................................................................................. 149 Source at 135 cm. ................................................................................. 150 Source at 150 cm. ................................................................................. 150 Source at 6 cm...................................................................................... 151 Source at 15 cm.................................................................................... 152 Source at 30 cm.................................................................................... 152 Source at 45 cm.................................................................................... 153 Source at 60 cm.................................................................................... 153 Source at 75 cm.................................................................................... 154 Source at 90 cm.................................................................................... 154 Source at 105 cm.................................................................................. 155 Source at 120 cm.................................................................................. 155 Source at 135 cm. ................................................................................. 156 Source at 150 cm. ................................................................................. 156 MxxM1. ............................................................................................... 212 SxxM1.................................................................................................. 213 VxxM1. ................................................................................................ 213 MxxS1.................................................................................................. 213 SxxS1. .................................................................................................. 214 VxxS1. ................................................................................................. 214 MxxV1. ................................................................................................ 215 SxxV1. ................................................................................................. 215 VxxV1.................................................................................................. 216 MxxM3. ............................................................................................... 217 SxxM3.................................................................................................. 218 VxxM3. ................................................................................................ 218 MxxS3.................................................................................................. 218 SxxS3. .................................................................................................. 219 VxxS3. ................................................................................................. 219 MxxV3. ................................................................................................ 220 SxxV3. ................................................................................................. 220 VxxV3.................................................................................................. 221 xviii Figure G.1-1: Figure G.1-2: Figure G.1-3: Figure G.1-4: Figure G.1-5: Figure G.1-6: Figure G.1-7: Figure G.1-8: Figure G.1-9: Figure G.2-1: Figure G.2-2: Figure G.2-3: Figure G.2-4: Figure G.2-5: Figure G.2-6: Figure G.2-7: Figure G.2-8: Figure G.2-9: Figure G.3-1: Figure G.3-2: Figure G.3-3: Figure G.3-4: Figure G.3-5: Figure G.3-6: Figure G.3-7: Figure G.3-8: Figure G.3-9: Figure G.4-1: Figure G.4-2: Figure G.4-3: Figure G.4-4: Figure G.4-5: Figure G.4-6: Figure G.4-7: Figure G.4-8: Figure G.4-9: Figure G.5-1: Figure G.5-2: Figure G.5-3: Figure G.5-4: Figure G.5-5: Figure G.5-6: Figure G.5-7: Figure G.5-8: MxxM1- ICRP 26 ANSI 1977.......................................................... 223 SxxM1- ICRP 26 ANSI 1977. .......................................................... 223 VxxM1- ICRP 26 ANSI 1977........................................................... 224 MxxS1- ICRP 26 ANSI 1977. .......................................................... 224 SxxS1- ICRP 26 ANSI 1977............................................................. 225 VxxS1- ICRP 26 ANSI 1977............................................................ 225 MxxV1- ICRP 26 ANSI 1977........................................................... 226 SxxV1- ICRP 26 ANSI 1977............................................................ 226 VxxV1- ICRP 26 ANSI 1977. .......................................................... 227 MxxM1- ICRP 26 ANSI 1991.......................................................... 228 SxxM1- ICRP 26 ANSI 1991. .......................................................... 228 VxxM1- ICRP 26 ANSI 1991........................................................... 229 MxxS1- ICRP 26 ANSI 1991. .......................................................... 230 SxxS1- ICRP 26 ANSI 1991............................................................. 230 VxxS1- ICRP 26 ANSI 1991............................................................ 231 MxxV1- ICRP 26 ANSI 1991........................................................... 231 SxxV1- ICRP 26 ANSI 1991............................................................ 232 VxxV1- ICRP 26 ANSI 1991. .......................................................... 232 MxxM1- ICRP 60 ANSI 1991.......................................................... 233 SxxM1- ICRP 60 ANSI 1991. .......................................................... 233 VxxM1- ICRP 60 ANSI 1991........................................................... 234 MxxS1- ICRP 60 ANSI 1991. .......................................................... 234 SxxS1- ICRP 60 ANSI 1991............................................................. 235 VxxS1- ICRP 60 ANSI 1991............................................................ 235 MxxV1- ICRP 60 ANSI 1991........................................................... 236 SxxV1- ICRP 60 ANSI 1991............................................................ 236 VxxV1- ICRP 60 ANSI 1991. .......................................................... 237 MxxM1- ICRP 60 ICRP 74. ............................................................. 238 SxxM1- ICRP 60 ICRP 74................................................................ 238 VxxM1- ICRP 60 ICRP 74. .............................................................. 239 MxxS1- ICRP 60 ICRP 74................................................................ 239 SxxS1- ICRP 60 ICRP 74. ................................................................ 240 VxxS1- ICRP 60 ICRP 74. ............................................................... 240 MxxV1- ICRP 60 ICRP 74. .............................................................. 241 SxxV1- ICRP 60 ICRP 74. ............................................................... 241 VxxV1 ICRP 60 ICRP 74. ................................................................ 242 MxxM3- ICRP 26 ANSI 1977.......................................................... 243 SxxM3- ICRP 26 ANSI 1977. .......................................................... 243 VxxM3- ICRP 26 ANSI 1977........................................................... 244 MxxS3- ICRP 26 ANSI 1977. .......................................................... 244 SxxS3- ICRP 26 ANSI 1977............................................................. 245 VxxS3- ICRP 26 ANSI 1977............................................................ 245 MxxV3- ICRP 26 ANSI 1977........................................................... 246 SxxV3- ICRP 26 ANSI 1977............................................................ 246 xix Figure G.5-9: Figure G.6-1: Figure G.6-2: Figure G.6-3: Figure G.6-4: Figure G.6-5: Figure G.6-6: Figure G.6-7: Figure G.6-8: Figure G.6-9: Figure G.7-1: Figure G.7-2: Figure G.7-3: Figure G.7-4: Figure G.7-5: Figure G.7-6: Figure G.7-7: Figure G.7-8: Figure G.7-9: Figure G.8-1: Figure G.8-2: Figure G.8-3: Figure G.8-4: Figure G.8-5: Figure G.8-6: Figure G.8-7: Figure G.8-8: Figure G.8-9: Figure I-1: Figure I-2: Figure I-3: Figure I-4: Figure I-5: Figure I-6: Figure I-7: Figure I-8: Figure I-9: Figure I-10: Figure I-11: Figure I-12: Figure I-13: Figure I-14: Figure I-15: Figure I-16: VxxV3- ICRP 26 ANSI 1977. .......................................................... 247 MxxM3- ICRP 26 ANSI 1991.......................................................... 248 SxxM3- ICRP 26 ANSI 1991. .......................................................... 248 VxxM3- ICRP 26 ANSI 1991........................................................... 249 MxxS3- ICRP 26 ANSI 1991. .......................................................... 249 SxxS3- ICRP 26 ANSI 1991............................................................. 250 VxxS3- ICRP 26 ANSI 1991............................................................ 250 MxxV3- ICRP 26 ANSI 1991........................................................... 251 SxxV3- ICRP 26 ANSI 1991............................................................ 251 VxxV3- ICRP 26 ANSI 1991. .......................................................... 252 MxxM3- ICRP 60 ANSI 1991.......................................................... 253 SxxM3- ICRP 60 ANSI 1991. .......................................................... 253 VxxM3- ICRP 60 ANSI 1991........................................................... 254 MxxS3- ICRP 60 ANSI 1991. .......................................................... 254 SxxS3- ICRP 60 ANSI 1991............................................................. 255 VxxS3- ICRP 60 ANSI 1991............................................................ 255 MxxV3- ICRP 60 ANSI 1991........................................................... 256 SxxV3- ICRP 60 ANSI 1991............................................................ 256 VxxV3- ICRP 60 ANSI 1991. .......................................................... 257 MxxM3- ICRP 60 ICRP 74. ............................................................. 258 SxxM3- ICRP 60 ICRP 74................................................................ 258 VxxM3- ICRP 60 ICRP 74. .............................................................. 259 MxxS3- ICRP 60 ICRP 74................................................................ 259 SxxS3- ICRP 60 ICRP 74. ................................................................ 260 VxxS31- ICRP 60 ICRP 74. ............................................................. 260 MxxV3- ICRP 60 ICRP 74. .............................................................. 261 SxxV3- ICRP 60 ICRP 74. ............................................................... 261 VxxV3 ICRP 60 ICRP 74. ................................................................ 262 Glove Box Used for Experiment.......................................................... 284 Plutonium-Beryllium Neutron Source ................................................. 285 Source Positioned Within Glove box................................................... 286 Setup of Dosimeters in Front of the Glove box ................................... 287 Setup of Dosimeters Around the Glove box ........................................ 289 Helium-3 Proportional Counter ........................................................... 290 Block Diagram of Counting System .................................................... 290 Setup of Counting System ................................................................... 291 Setup of Proportional Counter at a Given Dosimeter Position ............ 291 Computational Phantom with Dosimeter Lattice................................. 297 Grid View of Field on Poly Slab at 30.5 cm. in Front of Glove Box. . 299 Planar View of Field at 30.5 cm. in Front of Glove Box..................... 299 Grid View of Field on Poly Slab at 91.5 cm. in Front of Glove Box. . 300 Planar View of Field at 91.5 cm. in Front of Glove Box..................... 300 Grid View of Field on Poly Slab on Left Side of Glove Box. ............. 301 Planar View of Field on Poly Slab on Left Side of Glove Box. .......... 301 xx Figure I-17: Figure I-18: Figure I-19: Figure I-20: Grid View of Field on Poly Slab on Right Side of Glove Box............ 302 Planar View of Field on Poly Slab on Right Side of Glove Box......... 302 Estimated Dose Field with Phantom Dosimeter Lattice at 30.5 cm. ... 304 Estimated Dose Field with Phantom Dosimeter Lattice at 91.5 cm. ... 304 xxi Chapter 1: Introduction 1.1 ESTIMATION OF RADIATION DOSE RECEIVED BY A GLOVE BOX WORKER AND ITS ASSOCIATED PROBLEMS The effort to estimate the radiation dose received by an occupationally exposed worker is a complex task. The earliest efforts were directed towards medical radiologists and technicians operating x-ray machines and the system of protection developed was based on the "tolerance dose concept" (Taylor 1981; Poston 2000). The dose estimate was based on physical observations, e.g., reddening of the skin, and the unit of measurement, threshold erythema dose (TED), was the amount of radiation that would cause this reddening of the skin. The "tolerance dose", i.e., a dose that could be tolerated, was set at 0.01 TED/month. With the establishment of the Roentgen (R) as the unit of exposure in 1924, it was determined that TED was approximately 300 to 600 R and the tolerance dose was approximately 0.1 to 0.2 R/day of exposure. A tolerance dose of 0.1 R/day was adopted as the standard. The main assumption in the use of the tolerance dose concept was the existence of a threshold value below which no injury was expected to result. This concept was abandoned in 1948 upon recognition that there may be no threshold for gene mutation effects. The concept of "permissible dose - ...the dose of ionizing radiation that, in light of present knowledge, is not expected to cause appreciable body injury to a person at any time in his lifetime." became the basis of regulatory protection regulations from the late 1940's thru the 1970's into the early 1990's (Taylor 1979). A maximum permissible dose (MPD) of 0.3 R/week was established as the new dose limit. Since the Roentgen was originally defined as a measure of the amount of ionization produced in a given volume of air by x-ray or gamma-ray radiation, it is really a unit of measurement of exposure 1 because it does not express the direct interaction between the radiation and the material irradiated. The rad became the new unit for absorbed dose and was defined as the amount of radiation required to cause absorption of 100 ergs of energy per gram of material. As it was realized that different radiations had varying effects on the human body, another unit, the rem, was defined to permit comparison of radiation doses from different types of radiation that produce different amounts of damage. The concept of relative biological effectiveness (RBE), i.e., the ratio of the absorbed doses of different radiations required to produce the same damage, was developed. This lead to defining a quality factor (Q), for a given radiation, that would be a conservative upper limit of the RBE for the biological effect of greatest interest. Thus the product of absorbed dose (rads) and quality factor Q is known as the dose equivalent in units of rem (Healy 1970). In the early 1970's, the transition from radiation protection standards based on thresholds, safety factors, and permissible dose to standards based on quantitative risk assessment began. A linear, no threshold dose-response relationship was assumed for carcinogenic and genetic effects (1 x 10-04/rem whole body for malignant illnesses and 4 x 10-05/rem for hereditary effects) whereas absolute thresholds were assumed for all other radiation effects. Based on occupations with a high standard of safety, acceptable risk was taken as 50 deaths per million workers or a 40-year occupational lifetime risk of two fatalities per 1000 workers. Using an upper limit of 10 times this value for any individual worker, this resulted in an annual whole body dose limit of 5 rem/yr. Similarly, the effective dose equivalent HE is the weighted sum of the mean dose equivalents for all the relevant tissues and organs and thus takes into account the different mortality risks from cancer and the risk of hereditary effects associated with irradiations of different tissues and organs. This concept of risk-based dose limits provided the rationale for the 1977 ICRP recommendations (ICRP 1977). 2 In the early 1990s, the Nuclear Regulatory Commission (NRC) and Department of Energy (DOE) adopted the methodology of ICRP Publication 26 (1977) used in determining the dose of occupationally exposed workers. The intent of the ICRP Publication 26, NRC's regulation 10 CFR 20 and DOE's regulation 10 CFR 835 is to prevent non-stochastic effects and minimize the occurrence of stochastic effects to an acceptable level (ICRP 1977; NRC 1991; DOE 1999). The basis of these recommendations and regulations assume that the stochastic risk from uniform and nonuniform whole-body irradiations are equal. An ideal uniform irradiation of the whole body would require a broad parallel radiation field of relatively high-energy radiation, which many occupationally exposed workers do not experience. A non-uniform irradiation of the whole body could be created by a broad parallel beam of low energy radiation incident on one side of the worker, partial shielding of the body, or a radiation field with one or more types of radiation, each with varying energies or fluence rates, incident on the worker. There is no dosimetry device for the direct radiation dose measurement received by a worker's whole body or a specific tissue or organ. Instead, the dose from an external source of radiation can be estimated by one or more monitoring devices positioned somewhere on the surface of the worker's clothing or body. Commonly used monitoring devices, called dosimeters, can measure the type, fluence, and energy of the radiation incident on the worker's body. The Los Alamos National Laboratory (LANL) Model 8823 whole body dosimeter has been designed to perform accurate dose estimates for beta, photon, and neutron radiations that are encountered in typical field radiation conditions (Hoffman and Mallett 1999). For high-energy neutron radiation, the LANL track etch dosimeter (TED) provides better quality measurements than the Model 8823 (Hoffman 1998). The response of the dosimeter with associated dose algorithm, the 3 location of the dosimeter(s), and the number of dosimeters on the surface of the worker are the main components in estimating the radiation dose received by a worker. The primary task of computational dosimetry is to simulate or model radiation environments and find methods to enhance the accuracy of the determination of absorbed dose and dose equivalent (Siebert and Thomas 1997). Monte Carlo techniques are used extensively for these models and simulations in computational dosimetry. Appendix A provides an overview of Monte Carlo methods. It is important to remember that the models and simulations are an approximation to reality; the results are only as good as the assumptions, input data, and model for any given computational condition. These analyses can provide important insights into streaming problems, shielding options, dosimetry requirements, layout or work area, and potential radiological conditions not anticipated. In conjunction with the models or simulations of radiation environments, anthropomorphic computational phantoms are used to estimate the absorbed dose in specific organs or tissues of the body. BodyBuilder phantoms, developed from the mathematical phantom work at Oak Ridge National Laboratory (ORNL), allows the modeling of a human body with respect to the sex, selection of organs of interest, age, height, and weight including additional torso fat if desired (Van Riper 2002; Cristy and Eckerman 2003). 1.2 CURRENT PROBLEM STATEMENT Most occupational radiation exposure at LANL is due to neutron radiation (Hoffman and Mallett 1999). Almost always, the neutron radiation fields are part of a mixed radiation field. These exposures originate from isotropic sources, nuclear materials handling, sub-critical and critical assemblies, and accelerators. Many of the research and development activities connected with nuclear materials are performed in glove boxes. 4 The primary purpose of a glove box is to contain radioactive and other hazardous materials and prevent the inhalation or ingestion these materials by the workers (Dooley and Kornreich 1998). The glove box isolates the material and prevents direct contact with the worker as well as the spread of contamination in the workplace. Many different materials may be used in the construction of a glove box, depending on the radioactive and hazardous materials involved (AGS 1998). A standard glove box is constructed of stainless steel with transparent viewing windows and access ports with attached gloves. The glove box has airtight seals around penetrations or interfaces between the stainless steel and viewing windows, glove port gloves, and exhaust ventilation system which creating a negative pressure atmosphere of air or an inert gas. A properly sealed and ventilated glove box will contain the hazardous material, but in the case of radioactive material, the radiation (photons and neutrons) can penetrate the walls of the stainless steel glove box, viewing windows and glove ports. There are several methods used to reduce the radiation penetrating the stainless steel glove box walls, viewing windows, and glove ports, depending on the type and energy of radiation. Since the nominal -ray energy is low, the photons may be reduced with a relatively thin high Z material (i.e., a few millimeters to centimeters thickness of tungsten, lead or stainless steel). The high Z material may be placed around the source inside the glove box or incorporated into the structure of the glove box. Lead, when used, is usually sandwiched between plates of stainless steel that form the outer and inner surfaces of the glove box walls, excluding the glove ports and viewing windows. The viewing windows can be covered with leaded glass, but the glove ports do not normally have additional shielding for the photons, except when glove port gloves contain lead or other high Z materials. The unshielded or partially shielded glove port gloves or viewing 5 windows potentially create streaming paths for photons creating a non-uniform radiation field with varying fluence rates and energy distribution. The shielding for neutrons requires different types of material than used for photon shielding. Low Z materials, several inches thick, are used for neutron shields. It is common for the entire external surface of the glove box to be covered with four to sixinch thick transparent Lucite and Plexiglas , except the glove ports or other penetrations. This transparent shield permits glove box workers to look into the glove box to perform work or inspect the contents or process. The non-shielded or partially shielded portions of the glove box give rise to a neutron-streaming path and thus create a nonuniform radiation field external to the glove box. The estimation of radiation dose is performed in accordance with ICRP 26. The ICRP 26 risk-based dosimetry system deals with tissue risk coefficients and corresponding tissue weighting factors to assess tissue dose equivalent and to calculate effective dose equivalent. This system is based on the assumption that the stochastic risk is the same for a uniform whole body irradiation and the sum of individual weighted tissue irradiations (ICRP 1977). The risk factors for different tissues are based upon the estimated likelihood of inducing fatal malignant disease, non-stochastic changes, or substantial genetic defects in descendants. Table 1.1 provides the risk factors for each tissue or organ with their corresponding weighting factors that represent the proportion of the stochastic risk resulting from tissue T. Effective dose equivalent (HE) is calculated using H E = T wT H T where HT is the dose equivalent in tissue and wT is the weighting factor for each tissue. This is then compared to the whole body dose limit of 50 mSv (5 rem). This methodology is used because it forms the current basis of federal law (NRC 1991), which is the basis for DOE regulatory requirements. This risk-based dosimetry system was modified by the most 6 recent comprehensive recommendations of ICRP (Publication 60) (ICRP 1991). Although the use of this "new" system has been questioned at length (Dietze 1998; Thomas 1997; Thomas 1998), this methodology is being adopted by many countries (not including the United States) in their regulatory requirements. Since it has not been codified into federal law, calculations or estimates of radiation dose in accordance with these new recommendations will only be provided for comparison to ICRP 26 values. Table 1.1: Weighting Factor Determination Based on ICRP 26. Risk coefficient (Sv-1) wT 4 x 10-3 0.25 2.5 x 10-3 0.15 -3 2.0 x 10 0.12 2 x 10-3 0.12 -4 5 x 10 0.03 5 x 10-4 0.03 -3 5 x 10 0.3 * 1.65 x 10-2 (1.25 x 10-2 without gonads) * Limit for any single tissue in remainder category is 0.06. Rank order remainder organs/tissues and apply 0.06 to the first five organs/tissues. Note: Lens of eye, skin, hands and forearms, feet and ankles are not to be included in the "Remainder". Tissue Effect Gonads Hereditary (1st and 2nd) Breast Cancer Red Bone Marrow Leukemia Lung Cancer Thyroid Cancer Bone Surface Cancer Remainder Cancer ICRP acknowledges the use of dose equivalent as determined by dosimeters worn by the occupational worker as an acceptable means to determine the effective dose equivalent (HPS 1997). The current practice for most radiation fields is the use of a single dosimeter. Radiological glove box workers are trained to wear the whole-body dosimeter on the front of their body between their shoulders and their waist. The dosimeter may be worn on a lanyard or clipped to the worker's clothing. Wearing the dosimeter on a lanyard will usually locate the dosimeter mid-chest to upper abdomen; however, it also permits the dosimeter to rotate out of position even when the glove box worker is facing the radiation source. 7 The criteria for determining the type and number of dosimeters worn by occupational workers should be determined as a result of radiological surveys to assess the workplace radiation field variability (Brown 1997) coupled with computational modeling of the workplace conditions. The HPS N13.41-1997 standard lists several conditions that may indicate a need for multiple dosimetry. These can be summarized as two main conditions: 1) non-uniform radiation field due to partial shielding or streaming, and 2) variability in radiation field. Thus, a major concern is whether dose equivalent is correctly being estimated by the dosimeter(s) worn so that a viable estimate of effective dose equivalent can be determined, especially in a glove box environment where the radiation source will produce a non-uniform mixed radiation field. The radiation source term of interest is either weapons-grade plutonium (> 90% 239 Pu or heat source plutonium (238Pu). The age and purity of the plutonium will determine the composition of the radionuclides that make up the source, and in conjunction with the surrounding materials, will dictate the initial photon and neutron energy spectrums and the fluence rate for each radiation in the mixed field (Brown 1997). The neutron component of the source term is from the spontaneous fission of certain plutonium nuclides and 241 Am and ( ,n) reactions with low Z materials within the glove box. The photon component arises from radioactive decay, spontaneous fission, fission products, and (n, ) reactions. The radiation sources for this modeling are generated using ORIGEN-S (Gauld, Hermann, and Westfall 2002) to calculate nuclide decay and photon energy spectra and SOURCES (Wilson et al. 2002) to calculate the neutron energy spectra. The radiation fields are evaluated using Monte Carlo transport code MCNPXTM (Hendricks et al. 2003). MCNPX was created by combining the capabilities of LAHETTM (Prael and Lichtenstein 1989) and MCNPTM (Briesmeister 2000) into one code and was accomplished by extending the capabilities of MCNP (Monte Carlo Neutral Particle) to 8 all particles and energies and including physics models where table-based data was not available. Radiation dose is estimated using MCNPX (Monte Carlo Neutron Particle Extended) and anthropomorphic phantoms for various irradiation geometries. Additionally, a dosimeter tally plane can be modeled to simulate the various positions that a dosimeter can be worn. This will allow for the estimated dose at each location to be compared to the whole-body dose calculated using the phantom. Also, additional "dosimeters" could be modeled to simulate whether multiple dosimetry provides a better estimate of dose. 1.3 PREVIOUS STUDIES INVOLVING ESTIMATION OF DOSE RECEIVED IN NONUNIFORM RADIATION FIELDS Overview In the past, the major concern of dosimetry in radiation protection has been the external exposure of the workforce to gamma radiation while the realm of high LET radiations, particularly neutrons, has been considered to be in a state of disarray (Thomas 1998). This is evidenced in the literature by a preponderance of articles pertaining to photon dosimetry with few pertaining to neutron dosimetry. Thus, this review will include appropriate articles dealing with photon dosimetry. There are many factors influencing the assessment or estimation of tissue dose equivalent and effective dose equivalent for externally irradiated workers. The major factors are the methodology used to calculate tissue dose equivalent and effective dose equivalent, the radiation field geometry including the orientation of the worker to the radiation and the distance between the worker and the radiation source(s), the location of a single or multiple dosimeters worn by the worker, fluence to dose conversion coefficients, partial irradiation of the worker's body caused by streaming or created by 1.3.1 9 structures, equipment or shielding material, and the uniformity or lack thereof of the energy and fluence rate of the radiation field. 1.3.2 Photons Until 1991, the recommendations of ICRP 26 represent the methodology to calculate tissue dose equivalent and effective dose equivalent (Kramer and Drexler 1982; Drexler, Williams, and Zankl 1985). Since 1991, the recommendations of ICRP 60 have started to replace ICRP 26 as the methodology to calculate effective dose (Zankl, Petoussi, and Drexler 1992; Zankl and Drexler 1995). There have been several computational studies dealing with the relationship of the radiation field incident on a worker's body and the estimation of dose equivalent for various tissues and of wholebody effective dose equivalent (Reece, Poston, and Xu 1994; Kim, Reece, and Poston 1998; Kim, Reece, and Poston 1999). These studies dealt with the proposed methodology and conversion coefficients to estimate tissue dose equivalents and effective dose equivalent or effective dose the worker might receive for a given irradiation scenario. The radiation fields evaluated were from broad parallel beams or disk floor sources or point source geometries that would approximate a uniform field utilizing Monte Carlo transport codes and anthropomorphic computational phantoms to evaluate the radiation dose for the various geometries. The radiation dose quantities from external irradiation cannot be directly measured, so the measurement of the radiation dose is made at the surface of the body with the use of conversion coefficients and algorithms to estimate the tissue dose and whole body dose. (Kim, Reece, and Poston 1999). Fluence-to-dose conversion coefficients have been established by Monte Carlo transport codes calculations for various irradiation geometries. ANSI/ANS-6.1.1-1991 (ANS 1991) established and used ICRP 51 (ICRP 1987) fluence-to-dose factors for photons incident on an 10 anthropomorphic phantom for a range of photon energies and the following geometries: anterior-posterior, posterior-anterior, lateral, rotational and isotropic exposures. ICRP 74 (ICRP 1996) developed external radiation fluence-to-dose conversion coefficients that incorporated the concept of individual ICRP 60 tissues of highest risk for the following irradiation conditions: anterior-posterior, posterior-anterior, right lateral, left lateral rotational and isotropic exposure. Typically, the radiation field is assumed uniform for most work conditions or studies with respect to fluence rate, energy distribution, and conversion coefficients corresponding to the external irradiation scenario. The anterior-posterior irradiation condition of a parallel-broad photon beam creates the highest effective dose equivalent (effective dose) than the other irradiation projections (Reece, Poston, and Xu 1994; Kim, Reece, and Poston 1999). The studies performed on other types of uniform radiation fields, such as point or disk photon sources, demonstrate relationships of estimated effective dose equivalent (effective dose) dose for certain locations of the radiation source and orientation to a male or female. The irradiation orientation to phantoms suggest individuals, males and females, will receive a higher effective dose equivalent from a frontal irradiation than from the lateral or posterior-anterior, at least for photon energies with 1 MeV or less (Reece, Poston, and Xu 1994; Kim, Reece, and Poston 1998). When the body shields the dosimeter, the individual's effective dose equivalent could be underestimated by as much as 60% to 90% for photon energies ranging from 1 MeV to 0.08 MeV (Reece and Xu 1997). Fluence-to-dose conversion factors can vary significantly depending on the location and orientation of the dosimeter, and the direction of the irradiation incident on the body. The location of a dosimeter on the front torso and 11 a given incident photon geometry can impact the measured absorbed dose on the surface of the body (Zankl 1999). While a personal dosimeter on the chest can significantly underestimate worker dose, using an extra dosimeter on the back and taking a weighted average of these two dosimeter readings can fix the underestimation problem (Kim and Reece 2000). However, this approach can overestimate the effective dose for the lateral, over-head and underfoot beam directions. 1.3.3 Neutrons Until 1991, the recommendations of ICRP 26 represent the methodology to calculate tissue dose equivalent and effective dose equivalent (Endres et al. 1987; Tanner et al. 1992). Since 1991, the recommendations of ICRP 60 have started to replace ICRP 26 as the methodology to calculate effective dose (Hollnagel, Alberts and Dietze 1994; Meinhold 1992; Portal and Dietze 1992; Morstin, Kopec and Schmitz 1992). There have been several computational studies dealing with the relationship of the radiation field incident on a worker's body and the estimation of dose equivalent for various tissues and of whole-body effective dose equivalent (Hollnagel 1992; Drake and Bartlett 1997; Shores 1999; George and Shores 2000). These studies dealt with the proposed methodology and conversion coefficients to estimate tissue dose equivalents and effective dose equivalent or effective dose the worker might receive for a given irradiation scenario. The radiation fields evaluated were from broad parallel beams, PuBe neutron sources, and from typical working environments found at nuclear power reactors. One of these studies (George and Shores 2000) illustrates at least three different methods to calculate the effective dose equivalent (EDE or HE). The first method used to calculate HE was based on pre-calculated fluence-to-dose conversion factors. The fluence was determined at a plane having the same horizontal and vertical dimensions as the 12 computational phantom in method 3 in addition to a volume element having the same dimensions as the LANL TLD. The second method was based on calculating the energy deposition in a computational anthropomorphic phantom and folding in appropriate quality factors and tissue weighting factors. Method 3 employed pre-calculated fluenceto-dose conversion factors to calculate Deep Dose Equivalent (DDE) in mathematical shapes that simulate the human body. The DDE values were then weighted by compartment factors specified in ANSI N13.41 to calculate an HE. The calculated neutron EDE rates based on pre-calculated fluence-to-dose conversion factors yielded results similar to the energy deposition method. The neutron EDE rate based on the simulated human body compartment's DDE was significantly higher than the energy deposition model. As with photons, fluence-to-dose conversion coefficients have been established by Monte Carlo transport codes calculations for various irradiation geometries with ANSI/ANS-6.1.1-1991 (ANS 1991) and ICRP 74 (ICRP 1996) as the primary sources. Unlike photons, fluence-to-dose conversion factors are dependent upon the relative biological effectiveness (RBE) of neutrons and its variation with energy and how quality factors are determined (Cross and Ing 1985; Sinclair 1990; Van Dam et al. 1992; Hall and Brenner 1992). Although conversion coefficients relating neutron fluence to dose equivalent have been tabulated in many different formats and have been specified for many different phantoms and despite the significant changes in the definitions of the radiation protection quantities that have taken place, interestingly, the neutron conversion coefficients have remained nearly invariant for more than 40 years (McDonald, Schwartz, and Thomas 1998). Plutonium glove box workers usually wear a minimum of two dosimeters, a torso dosimeter and a wrist dosimeter (in lieu of a finger dosimeter). The torso dosimeter is a 13 custom designed Model 8823 whole-body TLD dosimeter that contains two Harshaw/Bicron-NE TLD cards and accurately measures dose equivalent estimates for beta, gamma and neutron radiations (Hoffman 1998, and Hoffman and Mallett 1999). The Model 8823 whole-body dosimeter's physical design and accompanying computational dose algorithm will determine the tissue dose equivalent at 7 mg/cm2 (shallow- dose equivalent), 300 mg/cm2 (lens-of-the-eye dose equivalent) and 1000 mg/cm2 (deep dose equivalent). This dosimeter meets the requirements in 10CFR835 Occupational Radiation Protection (DOE 1999) and is accredited for all performance testing categories in the Department of Energy Laboratory Accreditation Program (DOELAP) for external dosimetry. 1.4 OBJECTIVES Since most worker occupational exposure at LANL is due to neutron radiation, it is important to understand the differences in calculating dose using either ICRP 26 or ICRP 60 and which one is more conservative. If the dose calculated is too conservative, this has both a psychological impact as well as a productivity impact. If the dose calculated is not conservative, then a true safety concern exists. This research will evaluate the impact of non-uniform neutron radiation fields on assessing the tissue dose equivalents (equivalent dose) and effective dose equivalent (effective dose) of individuals working at a glove box workstation or in the vicinity of glove boxes. To accomplish this, a computational analysis for a typical LANL glove box will be performed with the following objectives: i. Evaluate the neutron radiation field distribution at various distances from a glove box for various radiation source locations inside the glove box. 14 ii. Evaluate the tissue dose equivalent and effective dose equivalent received by anthropomorphic computational phantoms at various distances and locations from a glove box containing neutron emitting radiation sources. iii. Evaluate the fluence rate and neutron energy field incident on pseudodosimeter tally cells positioned at various surface locations of the phantom. iv. Compare results of i - iii. 15 Chapter 2: Monte Carlo Calculations for Estimating Dose Received 2.1 2.1.1 MONTE CARLO METHOD Use of Random Sampling The Monte Carlo method is distinguished from other techniques in numerical analysis by the use of random sampling to construct the solution of a physical or mathematical problem (Carter and Cashwell 1975). In its simplest form, Monte Carlo consists of simulating a finite number of histories through the use of random numbers, or more appropriately a pseudorandom number generator. In each history, random numbers are generated and used to sample suitable probability distributions that describe the physical or mathematical problem at hand (Lewis and Miller 1993). Perhaps the earliest documented use of random sampling to find the solution to a mathematical problem was that of Comte de Buffon in 1777 (Kalos and Whitlock 1986). Although random sampling has been used to solve different mathematical problems since then, the Monte Carlo method is generally attributed to scientists working on the development of nuclear weapons at Los Alamos during the 1940's (Briesmeister 2000). For the neutron, photon, electron, or coupled neutron/photon/electron transport, this method has evolved with digital computers and at Los Alamos, it is known today as the Monte Carlo N-Particle (MCNP) method. There are two different versions available: the standard version, MCNP5 (X-5 Monte Carlo Team 2003) and an extended version MCNPX (Hendricks 2003) that allows for the transport of more energetic neutrons, photons, and electrons as well as other particles. Quite often, either version is often referred to as just MCNP. 16 2.1.2 Probability Density Function and the Cumulative Distribution Function "Life" of a neutron or photon, from its birth to its death, is governed by nature via many random processes (Lux and Koblinger 1991). Indeed, for an individual particle, neither the "birth" of the particle nor its location (if the source cannot be represented as a point source), nor its initial flight direction or energy or flight distance to its next interaction (collision) or the type of interaction and whether it is scattered or absorbed can be determined in advance. However, probability distributions can be determined for these random variables that describe the life of a particle. Typically, x represents some property of a particle history, such as flight distance, that may take on a range of values. If the probability that x will have a value between a and b is P ( a of f (x) x = P (x x' x + x) x b) , a probability density function (PDF) f(x) can be defined as the limit (2.1) as x 0 . Thus f (x) x represents the probability that x ' will take on a value between x and x + b x . Since probability is a number between 0 and 1, then f(x) 0, and f ( x )dx = P(a a x b) (2.2) with the requirement that f(x) be normalized; i.e. f ( x )dx = 1 (2.3) if x can take on any real value between - and . If the domain values are restricted between x- and x+, then x+ f ( x )dx = 1 . x (2.4) The probability that the random variable x ' is less than or equal to x is given by the cumulative probability distribution function (CDF) 17 x F ( x) = P( x ' x) = f ( x ')dx '. (2.5) From equation 2.5 it is clear that lim F ( x) = F ( ) = 1, x (2.6) (2.7) lim F ( x) = F (0) = 0. x 0 Using equations 2.2 and 2.5 P(a x ' b) = F (b) F (a ). (2.8) Often, it is more convenient to write equation 2.5 in differential form dF ( x ) = f ( x ). dx 2.1.3 Transformation of Random Variables (2.9) Often in Monte Carlo calculations, it is desirable to transform from one random variable to another, such as from speed to energy distribution for neutrons. Let f(x) be the PDF for the random variable x and let g(y) be the PDF for the random variable y, then f ( x )dx is the probability that x is between x and x + dx and g ( y )dy is the probability that y is between y and y+dy. Since it is desired that the probability not change because of the transformation, then the following condition must be satisfied f ( x )dx = g ( y )dy , or since f(x) > 0 and g(y) > 0, dx g ( y) = f ( x) . dy (2.10) (2.11) In particular, consider the case y=F(x), the CDF of the random variable x. Then equation 2.11 becomes dx . g ( F ) = f ( x) dF Using equation 2.9 to evaluate the derivative above g ( F ) = 1, 0 F 1. (2.12) (2.13) 18 Since g(F) is the PDF of the random variable F, equation 2.13 states that the probability of F taking on a value between F and F + dF is just dF . Thus, F is uniformly distributed between zero and one. Using a pseudorandom number generator that produces sequences of numbers that are uniformly distributed between zero and one, F(x) is then sampled in an unbiased manner by setting F ( x) = . (2.14) However, it is the distribution of x that needs to be sampled. Therefore the inversion x = F( ) 1 (2.15) must be performed. There are many techniques that can be used to perform this inversion. 2.1.4 Pseudorandom Number Generator The selection of the path length, angle of scattering, and many other parameters is made using a pseudorandom number generator. MCNP uses the linear congruential scheme of Lehmer (1951) though the mechanics of implementation have been modified for portability to different computer platforms (X-5 Monte Carlo Team 2003). The modified Lehmer's scheme generates a pseudorandom sequence of integers I n by I n +1 = (GI n + C ) mod 2 M , n = 0,1,... (2.16) where G is the random number multiplier, I0 is the initial random seed, C is an additive constant, and M-bit integers and M-bit floating point mantissas are assumed. The random number is then Rn = 2 MIn . (2.17) where MCNP implements the above algorithm using either 48-bit integers (the default) or 63-bit integers. The starting random number for history k is I 0k = [G kS I 0 + C (G kS 1) /(G 1)]mod 2 M (2.18) 19 where S is the random number stride, that is, the number of random numbers allocated to each single history. Successive random numbers for history k are then k I n +1 = (GI nk + C ) mod 2 M (2.19) where the default values of G, M, I0, S, and C, which can be changed with the RAND card, are G = 519= 19,073,486,328,125 M = 48 C=0 S = 152,917 I0 = 1 2.2 2.2.1 MONTE CARLO SAMPLING TECHNIQUES Sampling Techniques (2.20) There are many techniques to perform the inversion of equation 2.15. These include sampling distribution transformations (discrete or continuous), transformation of random variables, numerical transformations, rejection techniques, composition of random variable transformations, multivariate distributions, the Metropolis, Rosenbluth, 2 Rosenbluth, Teller and Teller M(RT) algorithm (Kalos and Whitlock 1986). The first four techniques are the most relevant to particle transport. 2.2.2 Sampling of Discrete Probability Distribution The way in which a random number between 0 and 1 is used to choose an event from a discrete probability distribution is as follows. Consider the selection of whether a neutron is supposed to interact by one of the following six types of reactions: 1. (n, n), elastic scattering with cross section s and probability p1 I 2. (n, n'), inelastic scattering with cross section 20 and probability p2 3. (n, ), radiative capture with cross section and probability p3 4 4. (n, ), (n, p), ..., charged particle with cross section probability p4 5. (n, 2n), (n, 3n), ..., n producing with cross section probability p5 6. (n, f), fission with cross section f = + p ... and 5 = 2n + 3n ... and and probability p6 where the total microscopic cross section is the sum of the possible reaction cross sections t =( s + I + + +...+ 2n + ...+ f ) (2.21) and the probabilities are defined by p1 = s / t, p2 = i/ t, p3 = p4 = p5 = p6 = / t, / t+ 2n p / t + ..., / t + ..., and (2.22) / t+ t 3n f / respectively with p1 + ... + p6 = 1. This case of discrete probabilities can be illustrated graphically by assigning a variable x on the interval 0 the agreement that j-1 x < n (n = 6 in this case) to the above events E1, ... , En with x < j represents the event EJ. A probability density function p(x) x < i for i = 1, 2, ... , n. Thus, can be constructed by the definition p(x) = pi where i-1 p(x) is a step function similar to that shown in Fig. 2.1. 21 p(x) p2 pn p1 E1 0 0 1 E2 2 n-1 En n X Figure 2.1: Discrete Probability Density Function. The CDF P(x) for the above PDF p(x) is shown in Fig. 2.2, a monotone increasing broken-line function. P(x) p1 + ...+pn =1 p1 +p2 p1 0 0 1 X 2 n-1 n Figure 2.2: Discrete Cumulative Probability Density Function. 22 Thus, P(x) can be interpreted as the probability of the inequality x ..., n. For a random number falls on the interval j-1 the event EJ. 2.2.3 i, for i = 1, 2, < 1, and if x distributed uniformly over the interval, 0 < P(j), then x < j, i.e., x such that P(j-1) = P(x) determines Sampling of an Invertible Continuous Probability Distribution Function Consider sampling the distance to collision of a particle. The probability of a first collision between s and s + ds along the flight path is given by p (l )dl = e tl t dl (2.23) Setting s = P( s ) = p (l )dl = 1 e 0 ts , (2.24) it follows that 1 s= ln(1 t ). (2.25) Since 1- is distributed as , then 1 s= ln( ) . t (2.26) That is, a random variable transformed as the natural logarithm of a uniform random variable is distributed exponentially. All cumulative probability distribution functions that arise from properly defined probability distribution functions are invertible, numerically if not analytically (Bielajew 2001). 2.2.4 Histogram or Tabulated Values Technique for a Continuous PDF Although = P( x ) = x a p (t )dt determines x uniquely, it is often difficult to find the inverse x = P 1 ( ) . Sometimes the CDF P(x) can be computed for specific values; other times the PDF p(t) is given as numerical data. In either of these cases, one can 23 subdivide the interval [a, b] such that x0 = a < x1 < ... < xn = b and then use tabulated values of Pi = P(xi) at the points of subdivision. Thus, for a random number , uniformly distributed over [0,1], the interval [xj-1, xj] that x falls into can be determined. By interpolation, if j is the first value of the index for which of the parameter x is determined to be Pj x = xj (xj xj 1) . Pj Pj 1 - Pj is negative, then the value (2.27) This is basically the same method used for the discrete PDF and is a common numerical transformation. 2.2.5 Rejection Techniques An alternate method of sampling makes use of the fact that the CDF (equation 2.5) represents the area under the curve of f(x) over the interval from - to x. The simplest rejection technique is illustrated by considering a PDF f(x) such that: 0 f(x) M for all x (a, b), and (2.28) (2.29) f(x) = 0 for f(x) outside of (a, b). Therefore the area under the curve of f(x) is enclosed within the rectangle defined by 0 y M and a < x < b . To find a point (x, y) distributed uniformly within the rectangle, two random numbers, 1 and 2 are chosen. The x value is selected uniformly within (a, b) by (2.30) x = a + (b a ) 1 , and the y value is selected uniformly within [0, M] by y=M 2 . (2.31) If y > f(x), the point is rejected and another point is selected. If y < f(x), the point is accepted and the random variable is set to x. 24 The efficiency of this technique is just the area below the graph to that of the rectangle. Since the area under the graph is one by definition of the PDF, then the efficiency is just 1 E= . M (b a ) (2.32) Although in principle this technique will work for any PDF, the efficiency may be too low in a given case for practical use. It should be note that one does not need to find the inverse of the CDF in this technique. More general rejection techniques involve finding a trial value of a random variable and then subjecting this value to one or more tests involving one or more random variables. It may then be accepted or rejected. If rejected, the cycle of choosing and testing another trial value is repeated until an acceptance takes place (Kalos and Whitlock 1986). 2.3 2.3.1 ANALOG MONTE CARLO SAMPLING Monte Carlo Modeling of Neutron Motion The movement of neutrons in a material is simulated by analog Monte Carlo by mimicking as precisely as possible the physical phenomena involved in such movement. First, the problem must be defined including such factors as the geometry and the neutron source. Once defined, the random walk of the neutrons through the geometry may be executed. The results of each random walk are used to calculate the detector response that is modeled by the calculation (Profio 1979; Dupree and Fraley 2002). 2.3.2 Problem Definition The physical description of the problem geometry and the material constituents is essential; all flight paths, particle interactions or escapes are based on this description. Describing a complex geometry accurately and ensuring that all regions are defined with 25 respect to the bounding surfaces is one of the most arduous tasks in preparing input for a Monte Carlo problem (Profio 1979). To help in this task, interactive geometry editors/viewers, such as MORITZ, have been developed for MCNP (Van Riper 2002). The physical description of the source may be a PDF that describes the source geometry and the distribution of neutrons within the source region or may be a specific set of start points with associated directions and energies. The initial starting neutron for each history arises from this definition and not from prior interactions. 2.3.3 Random Walk The random walk (Dupree and Fraley 2002) begins with a neutron being selected from the source distribution and assigned an initial position, energy, and direction of travel. Normally a weight of 1.0 is initially assigned to the neutron. The path length or distance to next collision, i.e. the collision site, is determined from the exponential distribution of collisions along the flight path. The probability of collision per unit path length is determined from the cross sections of the materials through which the neutron travels (Section 2.2.3). At the collision site, the specific nuclide involved in the collision is determined based on a proportionate division of the total cross section among the nuclides present. The specific interaction is determined based on the cross section of the nuclide chosen (Section 2.2.2). Alternative techniques include averaging or mixing the cross sections of the nuclides present to form one set of cross sections that contain all the features of all the nuclides present or doing a multi group formulation where a table of group averaged cross sections is used in connection with a set of discrete energy bins. Results of the interaction selected include one or more of the following alternatives: death of the neutron (reduction of the weight by the non-absorption probability); scattering of the neutron with scattering angle determined from the 26 scattering characteristics of the nuclide encountered; or production of secondary particles, including fission. The initial neutron and all secondary particles (or a statistically valid sample from them) are tracked similarly. This process continues until the initial neutron and all secondary particles produced die or escape from the geometry. The detector response that is modeled is usually calculated during the random walk. The number of histories, i.e. initial starting neutrons, is chosen so that the relative error is less than 0.1 and preferably less than 0.05 (Briesmeister 2000; X-5 Monte Carlo Team 2003). 2.3.4 Detector Response During the random walk the expected value or the mean of some random variable, most often related to scalar flux, current distribution, or another variable sought from the solution of the transport equation, is calculated. Results are obtained by assigning a score xi (xi = particle flux, particle track length, particle energy deposition or particle heating etc., associated with the ith random walk) to each random walk. Suppose f(x) is the PDF for selecting a random walk that scores x to the tally being estimated. The true mean is E ( x ) = xf ( x )dx and is estimated by the sample mean 1 N xN = x = xi N i =1 (2.33) (2.34) where xi is the value of x selected from f(x) for the ith history and N is the number of histories. The Monte Carlo mean x is the average value of the score xi for all the histories in the problem and is called a tally. Thus as the Monte Carlo calculation proceeds, we 27 tally the xi due to each history in order to calculate the sample mean at the end of the calculation. In MCNP, there are six tally types for neutrons: F1:n for surface current, F2:n for surface fluence, F4:n for cell fluence, F5:n for fluence at point or ring detector, F6:n for energy deposition, and F7:n for fission energy deposition. For these tally types, Table 2.1 gives the tally type, what estimator is used for calculating the tally, and the units that the tally is given in. Table 2.1: Tally Types. Tally Type F1:n F2:n F4:n Surface Current Surface Fluence Cell Fluence Estimator Units (per source particle) # #/cm2 W W /( * A) W* V #/cm2 #/cm2 Mev/gm Mev/gm F5:n F6:n F7:n where Detector Fluence Energy Deposition W*p( )*exp(-s)/2 R2 W* * T(E)*H(E)* a/m Fission Energy Deposition W* * f(E)*Q* a/m W = particle weight, E = energy of particle (MeV), p( ) = probability density function, = cosine of angle between surface normal and trajectory of particle, = track length (cm), S = total mean free path to detector (cm), R = distance to detector (cm), T (E) = microscopic total cross section (barns), 28 f (E) = microscopic fission cross section (barns), H(E) = heating number (MeV/collision), Q = fission heating Q-value (MeV), a = atom density (atoms/barn-cm), M = cell mass (gm), A = surface area (cm2), and V = cell volume (cm3). All MCNP tallies (except in criticality problems) are normalized to one starting source particle. Each tally must be scaled to the desired source strength. The fluence (particles/cm2) is of paramount importance because it can be converted into absorbed dose or dose equivalent if the differential energy distribution is known. 2.3.5 MCNP Precision The results from the Monte Carlo simulations represent averages of contributions from many histories sampled during the calculations; therefore MCNP (Briesmeister 2000) does ten statistical checks of the tallies to verify the stochastic behavior of the sampling and to provide assurance that the confidence interval for each tally is acceptable. The quantities involved in these checks are the estimated mean, relative error (R), variance of the variance (VOV), figure of merit (FOM), and the large history score behavior of f(x).These ten statistical checks are printed in the Tally Fluctuation Chart (TFC) at the end of the output file. MEAN xn or x 1. Random behavior should be exhibited; i.e., a non-monotonic behavior (no up or down trend) in the estimated mean as a function of the number histories n for the last half of the problem. 29 RELATIVE ERROR R The measure of how close the mean is to the true physical quantity being estimated (accuracy, systematic error, or bias) cannot directly be estimated by MCNP. Factors that affect the accuracy are: physics models used in the code, physical modeling of source and geometry, and user errors and abuse of the code. The uncertainty in the estimated mean x = xn caused by the statistical fluctuations in the sampled xi ' s is estimated by MCNP and reported as the relative error 1/ 2 R s 1 x2 xn = 2 n xn 1 ! . 1 n n i =1 (2.35) xi2 , the average of where 2 s is the standard deviation of the mean xn and x = the sum of the squares of the tally scores xi. Thus, the following checks are made on the estimated relative error R: 2. Acceptable magnitude of R < 0:05 for a point detector tally or < 0:10 for a non-point detector tally); 3. R should be monotonically decreasing as a function of the number histories n for the last half of the problem; and 4. Specifically, R should decrease as 1 VARIANCE OF VARIANCE (VOV) The VOV is n n n for the last half of the problem. (x i =1 x )4 / n( ( x " i =1 x)2 )2 # 1 n (2.36) and involves the first four history score moments. It should decrease as 1/n. The following checks are made on the VOV: 5. The magnitude of the estimated VOV should be less than 0.10 for all types of tallies; 30 6. VOV should be monotonically decreasing as a function of n for the last half of the problem; and 7. Specifically, VOV should decrease as 1/n for the last half of the problem. FIGURE OF MERIT (FOM) Since R 2 $ 1 n and the computational time T $ n , then the figure of merit FOM = 1 R 2T (2.37) should be constant with n. The measure of how quickly the desired precision is achieved is called the efficiency and increases with larger FOM values. The following checks are made on the FOM: 8. FOM should approach a statistically constant value as a function of n for the last half of the problem; and 9. FOM should exhibit non-monotonic behavior as a function of n for the last half of the problem. HISTORY SCORE PDF A history score PDF is generated using a logarithmic score grid for accumulating history scores. Six hundred bins are established (60 decades with 10 log bins per decade) and the probability for each bin j is calculated as follows: number of scores in bin j f (x j ) = ( N )( x ) (2.38) where N is the number of histories and x is the bin width. MCNP applies a curve fitting routine to the 201 largest history scores. If f(x) is unbounded, then it must decrease faster than 1/x3 for the second moment of f(x) to exist. Otherwise, the variance becomes infinite. The curve fitting routine assumes a Pareto shape for the PDF tail f ( x ) = a 1 (1 + kx a ) where the slope m (1/ k ) 1 (2.39) (1/ k ) + 1 . (2.40) 31 The following check in made on the history score PDF: 10. The SLOPE m of the history scores x should be greater than 3.0 so that the second moment will exist if the SLOPE is extrapolated to infinity. The seven N-dependent checks for the TFC bin are for the last half of the problem. The last half of the problem should be well behaved (in the sense of the Central Limit Theorem) to form the most valid confidence intervals. "Monotonically decreasing" in checks 3 and 5, allows for some increases in both R and the VOV. Such increases in adjacent TFC entries are acceptable and usually do not, by themselves, cause poor confidence intervals. A TFC bin R that does not pass check 3, by definition, does not pass check 4. Similarly, a TFC bin VOV that does not pass check 6, by definition, does not pass check 7. 2.4 2.4.1 MODIFICATIONS TO ANALOG MONTE CARLO SAMPLING Problems with Analog Monte Carlo Sampling Since analog Monte Carlo is based on mimicking as precisely as possible the physical processes of neutron transport (i.e. what nature does), it can suffer the same problems as an actual physical experiment. In an actual experiment, only a fraction of the emitted particles may reach the region of interest. This can result in low count rates in the detector necessitating longer count times or many repetitions of the experiment in order to obtain good statistics. In the equivalent numerical experiment one is forced to increase the number of particle histories or simulations in order to have good statistics (i.e. reducing the variance); however, the computational time may be prohibitive. Thus variance reduction techniques have been developed to modify the analog simulation process in such a way that more particle simulations have non-zero 32 contributions to the detector response or score while keeping the expected results of the analog and modified simulations identical (Lux and Koblinger 1990). 2.4.2 Variance Reduction Techniques Variance reduction techniques that have been developed (Booth 1985) include: Geometry Splitting/Russian Roulette; Energy splitting/Roulette Implicit Capture and Weight Cutoff Forced Collisions Angle Biasing Source Biasing Point vs. Ring Detector Weight Window Space-Energy Dependent Splitting/Roulette Exponential Transform For this dissertation, the variance reduction techniques used were Source Biasing and Implicit Capture. Source biasing maintains the physics of an isotropic distribution while aiming more particles in the preferred direction but with reduced weight. This is accomplished by sampling from an exponential function in the cosine of the angle with respect to a specified reference direction. Weights assigned to particles are adjusted so as to preserve the weight that would have been assigned without source biasing in place. Thus, more particles are sent toward the region of interest. Implicit capture is synonymous with absorption by weight reduction. Instead of allowing a particle to be absorbed, the particle always survives the collision but with a weight w modified by the survival probability shown in equation 2.41 33 w = w (1 ai ti ) (2.41) where ai and ti are the microscopic absorption cross section and total microscopic cross section for nuclide i respectively. This allows for more particles to reach the region of interest instead of being killed off before getting there. 34 Chapter 3: Computational Experiment for Typical LANL Glove Box 3.1 OBJECTIVES The computational experiment for a typical LANL glove box consisted of the following: i. ii. Construct a model of a typical LANL glove box. Evaluate the neutron radiation field distribution at various distances from a glove box for various radiation source locations inside the glove box. iii. Evaluate the tissue dose equivalent and effective dose equivalent received by anthropomorphic computational phantoms at various distances and locations from a glove box containing neutron emitting radiation sources. iv. Evaluate the fluence rate and neutron energy field incident on pseudodosimeter tally cells positioned at various surface locations of the phantom. v. 3.2 3.2.1 Compare results of ii - iv. EXPERIMENTAL SETUP Description of Glove Box A standard 2x2x2 LANL glove box is two workstations deep, two stations wide and two stations high where a typical workstation represents one pair of glove ports or about 71.12 to 81.28 cm (28 to 32 inches) in depth and width per workstation. The body of the glove box is approximately 152.4 cm x 162.6 cm x 114.3 cm (60 x 64" x 45") and the bottom of the glove box is approximately 106.7 cm (42 ) above the floor. The sides of the shell of the glove box is constructed of an inner layer of 0.47625 cm (3/16 ) type 304 stainless steel, a middle layer of 0.635 cm ( ") lead, an outer layer of 0.3175 cm (1/8") 35 stainless steel while the top and bottom of the shell were constructed of 0.47625 cm (3/16") stainless steel. The windows were constructed of 0.79 cm (5/16") boroscillate glass. This standard glove box needs to be modified if the source term has a significant neutron and/or photon components. If the glove box already exists, then it is easier to hang shielding materials on the outside of the glove box in the thickness required to reduce the dose to acceptable levels. This is usually done using low Z materials such as polyethylene for neutrons, lead blankets for photons, or using movable shields. If possible, it is better to design the required shielding into the glove box before it is built. Normally, the box is designed to attenuate the photons first and then designed to attenuate the neutrons. This is because in normal operations, the dose from photons can be orders of magnitude higher than that from neutrons. In designing the shell of a glove box, there are two approaches that are normally taken as depicted in Figs. 3-1 and 3-2. NSM SS Pb SS Figure 3-1: Shell Design A. NSM Inside SS SS Pb SS SS Inside Outside Outside Figure 3-2: Shell Design B. 36 Both of these designs add another layer of stainless steel and a layer of neutron shielding material (NSM). Historically, shell design A depicted above has been used with no documentation as to why. Shell design B with the lead (Pb) layer closest to the outside was chosen for this glove box. This provides for shielding of the photons created by neutrons interactions in the neutron shielding material. Layers of stainless steel 304 (SS) is used on both sides of the Pb and the NSM layers. The thickness of the NSM layer and the material used is dependent on many factors with the primary factor being the reduced reach inside the glove box by the worker for increasing shell thicknesses. Most glove box workers can tolerate a shell thickness between two and three inches and still perform work inside the box. For this glove box, a 5.08 cm (2 in.) thickness of the NSM was chosen with a resulting total shell thickness of 6.67 cm (210/16"). The choice of neutron shielding material was based on the attenuation of dose due to neutrons provided by the material. Appendix A provides the methodology used to determine the attenuation for several different neutron shielding materials. The material chosen was a mixture of NS-3, Pb, and B4C (34% NS-3, 65% Pb, and 1% B4C) (Dargis 2003) that has actually been used before and is not just a theoretical composition. The half-value thickness for this material is 2.4 cm (0.95 in). The upper and lower panels on each long side contain four glove ports, each with a radius of 10.16 cm (4"). Between each pair of glove ports is a small viewing window 16 cm x 26.67 cm (6.3" x 10.5"). In the slanted middle panel of the glove box are two large viewing windows between the upper and lower glove ports on the left and right side. For each pair of glove ports, the centers of the glove ports are 43.18 cm (17") apart. The base of the glove box was 2.54 cm (1 in.) stainless steel while the top was 0.47625 cm (3/16") stainless steel. The bottom of the glove box is 103.99 cm (40.94") off 37 the floor. The floor was taken to be 30.5 cm (1 ft) of concrete. The top of the glove box is 220.35 cm (86.75") above floor level. The glove box legs were not modeled. The vertical dimension 'z' was taken so that z = 0 was floor level. The 'x' dimension was taken such that positive 'x' pointed out from the glove box. The glove box has mirror symmetry about the vertical plane containing x=0 and y = 0. Figs. 3-3 to 3-5 depict the typical 2x2x2 LANL glove box as modified above to provide more neutron shielding. A computational phantom is shown at the middle of the glove box. Figure 3-3: Typical 2x2x2 LANL Glove box Front View. 38 Figure 3-4: Typical 2x2x2 LANL Glove box 3D View. 39 Figure 3-5: Typical 2x2x2 LANL Glove box Side View. 3.2.2 Description of Computational Phantom In conjunction with the glove box model developed above and the desire to simulate the radiation environment around the glove box, an anthropomorphic computational phantom is used to estimate the absorbed dose in specific organs or tissues of the body. BodyBuilder phantoms, developed from the mathematical phantom work at 40 ORNL, allows the modeling of a human body with respect to the sex, selection of organs of interest, age, height, and weight including additional torso fat if desired (Van Riper 2002; Cristy and Eckerman 2003). The phantom was 179 cm (70.5 ") tall and had a weight of 73.54 kg (161.8 pounds). In Figs. 3-3 to 3-5, the gray shield in front of the phantom is the dosimeter tally surface used to simulate the different positions a dosimeter can be worn on the body between neck and waist level. This surface is a cylindrical surface 16.8 cm from the centerline of the phantom. Fig.3-6 provides a longitudinal medial view of the phantom. Beside it is the dosimeter lattice that is placed over and around the torso of the phantom. The lattice consists of 8 cm x 8 cm squares, each represents a dosimeter location. The highlighted tally represents the middle of the torso where the dosimeter is most likely worn. Figure 3-6: Longitudinal Medial View of Phantom and Dosimeter Tally Plane. 41 3.2.3 Neutron Source The neutron energy spectrum for 1 kg of clean Weapons Grade (WG) Pu with isotopic content given in Table 3-1 was calculated using Sources 4C. The total neutron emission was 6.359 x 10+04 neutrons/s per kg of Pu and had a mean energy of 1.94 MeV. The neutron energy spectrum is given in Table 3-2 and Fig. 3-7. Table 3-1: Nuclide Wt% Table 3-2: Isotopic Content of Neutron Source. Pu-238 0.03 Pu-239 93.71 Pu-240 5.96 Pu-241 0.25 Pu-242 0.03 Am-241 0.02 Neutron Energy Spectrum. n/s/kg 0 2.649E+01 4.820E+01 2.180E+02 5.232E+02 1.424E+03 3.716E+03 4.309E+03 4.535E+03 4.545E+03 6.550E+03 7.862E+03 6.656E+03 4.189E+03 3.546E+03 Energy (MeV) 3.000E+00 3.300E+00 3.600E+00 4.000E+00 4.400E+00 5.000E+00 6.000E+00 7.000E+00 8.000E+00 9.000E+00 1.000E+01 1.200E+01 1.500E+01 2.000E+01 Total n/s/kg 2.965E+03 2.454E+03 2.013E+03 2.113E+03 1.588E+03 1.650E+03 1.501E+03 6.667E+02 2.864E+02 1.198E+02 4.898E+01 2.743E+01 4.633E+00 2.651E-01 6.359E+04 Energy (MeV) 1.000E-08 1.000E-02 2.000E-02 5.000E-02 1.000E-01 2.000E-01 4.000E-01 6.000E-01 8.000E-01 1.000E+00 1.300E+00 1.700E+00 2.100E+00 2.400E+00 2.700E+00 42 Neutron Energy Spectrum for Clean WG Pu 1.4e-1 1.2e-1 1.0e-1 Probability 8.0e-2 6.0e-2 4.0e-2 2.0e-2 1e-9 1e-8 1e-7 1e-6 1e-5 1e-4 1e-3 1e-2 1e-1 1e+0 1e+1 1e+2 Energy, MeV Figure 3-7: Neutron Energy Spectrum for Clean WG Pu. 3.2.4 Setup to Determine Neutron Radiation Field and Associated Dose at Selected Locations Mesh tallies at 30.5 cm and 91.5 cm (1 ft and 3 ft) from the front of the glove box were used to determine the neutron radiation field for different source locations. The source locations were determined by a grid within the glove box. The grid was formed three lines parallel to the x-axis and 11 lines parallel to the y-axis. The line S is 6 cm from the left side of the glove box while the lines V and M went through the gloveport 43 viewing window (V) and the middle (M) of the glove box. The numbers labeling the lines parallel to the y-axis represent the distance in cm from the inside surface of the front of the glove box. The 33 source locations were the intersections of these lines. A computational phantom representing a worker was located at one of six places determined by the intersection of the lines S, V, and M with the mesh tally lines at 30.5 cm and 91.5 cm (1 ft and 3 ft). Besides calculating the whole body dose using the computational phantom, each phantom had a dosimeter tally lattice associated with it as described above that allowed the calculation of the dose a dosimeter would measure at various locations on the torso of a worker. Fig. 3-8 shows a phantom located at the intersection of M and 30.5 cm (1 ft) lines and the source (marked by 'x') at the intersection of the lines labeled V and 15. Figure 3-8: Setup to Determine Neutron Radiation Field. 44 3.2.5 Estimating Whole Body Dose Using Computational Phantom and F6 Tally By the nature of the simulation, MCNP builds up a picture of the radiation field and determines the fluence (particles/cm2) at a desired tally location. All MCNP tallies (except in criticality problems) are normalized to one starting source particle. Each tally must be scaled to the desired source strength. Fluence is of paramount importance since it can be converted into absorbed dose or dose equivalent if the differential energy distribution is known. For calculating the whole body dose, an F6 Energy Deposition tally type was used for each organ/tissue of interest. MCNP returns for each F6 tally some number X with units of Mev/g per source particle. To convert to absorbed dose D, D = X Mev/g/src-part * 1 rad/6.242E+7 Mev/g =X * 1.6E-08 rad/src-part. (3.1) To convert to dose equivalent, HT = Q (rem/rad) * DT (rad/src-part) = Q*DT rem/src-part (3.2) where Q is the mean quality factor. Since Q depends on the energy of the particle, a differential distribution of Q can be input by using the de and df cards. Thus, in addition to X, MCNP returns some number Y representing the value of Q. Thus, the dose equivalent per source particle for a given organ/tissue is HT = X Mev/g/src-part * Y (rem/rad) * [1 rad/6.242E+7 Mev/g] * [1000 mrem/rem] = 1.602E-5 * XY mrem/src part. Then the effective dose equivalent for the whole body is H E = wT H T T (3.3) (3.4) where wT is a weighting factor representing the proportion of stochastic risk resulting from organ/tissue T to the total risk. The above methodology for calculating effective dose equivalent is based on ICRP 26 (1977) and can be used with either the ANSI-1977 set of quality factors or the 45 ICRP 51 (1987) set of quality factors. ICRP 60 (1991) changed the methodology to calculate whole body dose. This defined three principal protection quantities: DT, mean absorbed dose in an organ or tissue, HT, equivalent dose in an organ or tissue, and E, effective dose. These protection quantities are related by the following: DT = HT = T / mT, where T and mT are the energy deposited in a tissue of mass m, wR DT,R, where DT,R is the averaged absorbed dose from radiation R and tissue T, and wR is the radiation weighting factor for radiation R, and E = wTHT, where wT is the weighting factor for tissue T. (3.5) In calculating the effective dose with MCNP, the radiation weighting factor depends on energy and can be input as a differential distribution by using the de and df cards. For calculational purposes, wR = 5 + 17e (ln(2 E )) 2 6 (3.4) where E is the neutron energy in MeV (ICRP 1991). Likewise, MCNP will output XY and HT = 1.602E-5 * XY mrem/src part. (3.5) Since MCNP returns only the value XY, a tally multiplier card was used to input the value 1.602E-5. Table 3-3 provides the quality factors or radiation weighting factors that were used. A spreadsheet format (see Appendix B for an example) was created to take the dose equivalent data for each organ/tissue and apply the appropriate tissue weighting factors to come up with effective dose equivalent (Equation 3-4) or the effective dose (Equation 3-5). 46 Table 3-3: Neutron Quality Factors and Radiation Weighting Factors. Energy ANSI 1977 ANSI 1991 ICRP 26 ICRP 51 ICRP 60 E (MeV) Q Q WR 2.00E-01 24.8 19.8 3.00E-01 21.3 5.00E-01 11 25.4 22.0 7.00E-01 21.7 9.00E-01 21.0 1.00E+00 11 23.6 20.7 1.20E+00 20.0 1.50E+00 21.2 2.00E+00 19.78 17.3 2.50E+00 9 3.00E+00 18 15.0 4.00E+00 17.1 13.3 5.00E+00 8 15.7 12.0 6.00E+00 14.86 11.1 7.00E+00 7 14.6 10.3 8.00E+00 14.6 9.7 9.00E+00 9.2 1.00E+01 6.5 14.82 8.8 1.20E+01 8.2 1.40E+01 7.5 15.08 7.7 1.50E+01 7.5 1.60E+01 7.3 1.70E+01 14.88 1.80E+01 7.0 2.00E+01 8 15.48 6.8 Energy ANSI 1977 ANSI 1991 ICRP 26 ICRP 51 ICRP 60 E (MeV) Q Q WR 1.00E-09 5.0 1.00E-08 5.0 2.50E-08 2 6.56 5.0 1.00E-07 2 6.32 5.0 2.00E-07 5.0 5.00E-07 5.0 1.00E-06 2 6.02 5.0 2.00E-06 5.0 5.00E-06 5.0 1.00E-05 2 5.82 5.0 2.00E-05 5.0 5.00E-05 5.0 1.00E-04 2 5.7 5.0 2.00E-04 5.0 5.00E-04 5.0 1.00E-03 2 5.48 5.0 2.00E-03 5.1 5.00E-03 5.5 1.00E-02 2.5 5.54 6.3 2.00E-02 8.0 3.00E-02 9.5 5.00E-02 14.46 12.0 7.00E-02 13.9 1.00E-01 7.5 20.2 16.0 1.50E-01 18.4 For determining effective dose equivalent (ICRP 26 1977), the remainder is distributed as a tissue weighting factor wT = 0.05 to each of the five organs or tissues of the remainder receiving the highest dose equivalents. For determining effective dose 47 (ICRP 60 1991), the weighting factor of 0.05 is applied to the sum of the dose equivalents for all of the remainder tissues (adrenals, brain, upper large intestine, small intestine, kidney, muscle, pancreas, spleen, thymus, and uterus). Table 3-4 provides the tissue weighting factors that were used. Table 3-4: Tissue Weighting Factors. ICRP 26 wT 0.25 0.12 0.12 ICRP 60 wT 0.20 0.12 0.12 0.12 0.12 0.05 0.05 0.05 0.05 0.05 0.01 0.01 0.05 Tissue Gonads Red bone marrow Colon Lung Stomach Bladder Breast Liver Esophagus Thyroid Skin Bone surfaces Remainder 3.2.6 0.15 0.03 0.03 0.30 Estimating Dose that a Dosimeter Would Measure h4 For estimating the dose that a dosimeter would measure, an F2 Surface Fluence type tally was used for each dosimeter location in the dosimeter lattice. This tally return a number X tally particles/(source neutron cm2). To convert this to dose, neutron flux-to dose conversion factors were input as a differential distribution by using the de and df cards. With this addition, a number X Y tally neutrons/(source_neutrons-cm^2) * E-12 Sv-cm2/tally neutron is returned. To convert this number to dose (mrem/h-kg), the following conversion is made (6.359E+04 src_neuts/s) / (kg Pu) x (100 rem/Sv) x (3600 s/h) x (1000 mrem/rem) * X Y tally neutrons/ (source_neutrons-cm^2) * E-12 Sv-cm2/tally neutron 48 = 2.28924E+1*XY mrem/h-kg. Thus, a tally multiplier card with the value 2.28924E+1 is used so that MCNP outputs the dose in the units desired (mrem/h-kg). Tables 3-5, 3-6, and 3-7 provide the flux-to-dose conversion factors that were used. Fig. 3-9 provides a graphical comparison of the dose conversion factors used. Table 3-5: ANSI-1977 Neutron Flux-to-Dose Conversion Factors. Neutron Flux-to-Dose-Rate Conversion Factors ANSI/ANS-6.1.1-1977 (Basis: NCRP) E MeV 2.50E-08 1.00E-07 1.00E-06 1.00E-05 1.00E-04 1.00E-03 1.00E-02 1.00E-01 5.00E-01 1.00E+00 2.50E+00 5.00E+00 7.00E+00 1.00E+01 1.40E+01 2.00E+01 DFn(E) (rem/hr) / (n/cm -s) 3.67E-06 3.67E-06 4.46E-06 4.54E-06 4.18E-06 3.76E-06 3.56E-06 2.17E-05 9.26E-05 1.32E-04 1.25E-04 1.56E-04 1.47E-04 1.47E-04 2.08E-04 2.27E-04 2 rem-cm / n 1.019E-09 1.019E-09 1.239E-09 1.261E-09 1.161E-09 1.044E-09 9.889E-10 6.028E-09 2.572E-08 3.667E-08 3.472E-08 4.333E-08 4.083E-08 4.083E-08 5.778E-08 6.306E-08 2 Sv-cm / n 1.019E-11 1.019E-11 1.239E-11 1.261E-11 1.161E-11 1.044E-11 9.889E-12 6.028E-11 2.572E-10 3.667E-10 3.472E-10 4.333E-10 4.083E-10 4.083E-10 5.778E-10 6.306E-10 2 pSv-cm / n 1.02E+01 1.02E+01 1.24E+01 1.26E+01 1.16E+01 1.04E+01 9.89E+00 6.03E+01 2.57E+02 3.67E+02 3.47E+02 4.33E+02 4.08E+02 4.08E+02 5.78E+02 6.31E+02 2 49 Table 3-6: ANSI 1991 Neutron Flux-to-Dose Conversion Factors. Neutron Flux-to-Dose-Rate Conversion Factors ANSI/ANS-6.1.1-1991 (Basis: ICRP 51) E MeV 2.50E-08 1.00E-07 1.00E-06 1.00E-05 1.00E-04 1.00E-03 1.00E-02 2.00E-02 5.00E-02 1.00E-01 2.00E-01 5.00E-01 1.00E+00 1.50E+00 2.00E+00 3.00E+00 4.00E+00 5.00E+00 6.00E+00 7.00E+00 8.00E+00 1.00E+01 1.40E+01 DFn(E) (rem/hr) / (n/cm -s) 1.44E-06 1.58E-06 1.74E-06 1.61E-06 1.59E-06 1.38E-06 1.63E-06 2.11E-06 3.92E-06 7.13E-06 1.39E-05 3.13E-05 5.15E-05 6.59E-05 7.70E-05 9.50E-05 1.08E-04 1.18E-04 1.25E-04 1.31E-04 1.37E-04 1.48E-04 1.73E-04 2 Sv-cm / n 4.00E-12 4.40E-12 4.82E-12 4.46E-12 4.41E-12 3.83E-12 4.53E-12 5.87E-12 1.09E-11 1.98E-11 3.86E-11 8.70E-11 1.43E-10 1.83E-10 2.14E-10 2.64E-10 3.00E-10 3.27E-10 3.47E-10 3.65E-10 3.80E-10 4.10E-10 4.80E-10 2 pSv-cm / n 4.00 4.40 4.82 4.46 4.41 3.83 4.53 5.87 10.90 19.80 38.60 87.00 143.00 183.00 214.00 264.00 300.00 327.00 347.00 365.00 380.00 410.00 480.00 2 50 Table 3-7: ICRP 74 Neutron Flux-to-Dose Conversion Factors. Neutron Flux-to-Dose-Rate Conversion Factors ICRP 74 ICRP 74 E 2 2 2 E MeV 1.00E-09 1.00E-08 2.50E-08 1.00E-07 2.00E-07 5.00E-07 1.00E-06 2.00E-06 5.00E-06 1.00E-05 2.00E-05 5.00E-05 1.00E-04 2.00E-04 5.00E-04 1.00E-03 2.00E-03 5.00E-03 1.00E-02 2.00E-02 3.00E-02 5.00E-02 7.00E-02 1.00E-01 1.50E-01 2.00E-01 3.00E-01 DFn(E) (rem/hr) / (n/cm -s) Sv-cm / n pSv-cm / n 1.89E-06 2.25E-06 2.74E-06 3.58E-06 4.03E-06 4.61E-06 4.97E-06 5.22E-06 5.40E-06 5.44E-06 5.44E-06 5.33E-06 5.26E-06 5.18E-06 5.11E-06 5.11E-06 5.18E-06 5.65E-06 6.59E-06 8.57E-06 1.04E-05 1.39E-05 1.70E-05 2.15E-05 2.89E-05 3.56E-05 4.79E-05 DFn(E) (rem/hr) / (n/cm -s) Sv-cm / n pSv-cm / n 6.77E-05 8.32E-05 9.61E-05 1.02E-04 1.12E-04 1.38E-04 1.56E-04 1.65E-04 1.71E-04 1.74E-04 1.76E-04 1.78E-04 1.79E-04 1.80E-04 1.80E-04 1.79E-04 1.78E-04 1.77E-04 1.75E-04 1.73E-04 1.65E-04 1.57E-04 1.54E-04 1.54E-04 1.56E-04 1.58E-04 1.60E-04 1.88E-10 1.88E+02 2.31E-10 2.31E+02 2.67E-10 2.67E+02 2.82E-10 2.82E+02 3.10E-10 3.10E+02 3.83E-10 3.83E+02 4.32E-10 4.32E+02 4.58E-10 4.58E+02 4.74E-10 4.74E+02 4.83E-10 4.83E+02 4.90E-10 4.90E+02 4.94E-10 4.94E+02 4.97E-10 4.97E+02 4.99E-10 4.99E+02 4.99E-10 4.99E+02 4.96E-10 4.96E+02 4.94E-10 4.94E+02 4.91E-10 4.91E+02 4.86E-10 4.86E+02 4.80E-10 4.80E+02 4.58E-10 4.58E+02 4.37E-10 4.37E+02 4.29E-10 4.29E+02 4.29E-10 4.29E+02 4.32E-10 4.32E+02 4.38E-10 4.38E+02 4.45E-10 4.45E+02 2 2 2 MeV 5.24E-12 5.24E+00 5.00E-01 6.25E-12 6.25E+00 7.00E-01 7.60E-12 7.60E+00 9.00E-01 9.95E-12 9.95E+00 1.00E+00 1.12E-11 1.12E+01 1.20E+00 1.28E-11 1.28E+01 2.00E+00 1.38E-11 1.38E+01 3.00E+00 1.45E-11 1.45E+01 4.00E+00 1.50E-11 1.50E+01 5.00E+00 1.51E-11 1.51E+01 6.00E+00 1.51E-11 1.51E+01 7.00E+00 1.48E-11 1.48E+01 8.00E+00 1.46E-11 1.46E+01 9.00E+00 1.44E-11 1.44E+01 1.00E+01 1.42E-11 1.42E+01 1.20E+01 1.42E-11 1.42E+01 1.40E+01 1.44E-11 1.44E+01 1.50E+01 1.57E-11 1.57E+01 1.60E+01 1.83E-11 1.83E+01 1.80E+01 2.38E-11 2.38E+01 2.00E+01 2.90E-11 2.90E+01 3.00E+01 3.85E-11 3.85E+01 5.00E+01 4.72E-11 4.72E+01 7.50E+01 5.98E-11 5.98E+01 1.00E+02 8.02E-11 8.02E+01 1.30E+02 9.90E-11 9.90E+01 1.50E+02 1.33E-10 1.33E+02 1.80E+02 51 Figure 3-9: Comparison of Neutron Flux-to-Dose Conversion Factors. 3.2.7 Determining the Neutron Radiation Field For determining the neutron radiation field, a mesh tally (Type 1) that allows for the setup of a large Cartesian, cylindrical, or spherical mesh in which to score track averaged data such as flux. The average fluence is particle weight times track length divided by volume in units of number/cm2. If the source is considered to be steady state in particles per second, then the value becomes flux in number/cm2/second. This may be converted to dose by the same methodology as above. 52 The mesh was setup to provide the neutron dose field in a 400 cm by 440 cm YZ plane at distances 30.5 cm, 91.5 cm and 183 cm (1 ft, 91.5 cm and 6 ft) in front of the glove box. It was 1 cm deep in the X direction. The grid points in the YZ plane were 8 cm apart. This mesh then simulated the placing of 2750 dosimeters in a plane parallel to the front of the glove box. 3.3 3.3.1 COMPUTATIONAL RESULTS Neutron Radiation Field Appendix C provides the plots of the neutron radiation field at distances 30.5 cm, 91.5 cm, and 183 cm (1 ft, 3 ft, and 6 ft) in front of the glove box for 33 different source locations (11 on the side, 11 in front of the viewing window, and 11 in the middle). ANSI 1977 fluence-to-dose conversion factors were used. The outline of the front of the glove box is shown on each plot for reference. 3.3.2 Estimated Dose using Phantom's Dosimeter Lattice Appendix D provides a summary of the calculations of the estimated dose using the phantom's dosimeter lattice at 30.5 cm (1 ft) and 91.5 cm (3 ft) for each of the different conversion factor sets. For each phantom position, it provides the maximum, minimum, average, and reference position values in the dosimeter tally plane along with the respective dosimeter positions. For ANSI 1977 conversion factors, the dosimeter positions were labeled between 402 and 722 while they were labeled between 2 and 322 for ANSI 1991 conversion factors and between 802 and 1122 for ICRP-74 conversion factors (refer to Table 3-8). 53 Table 3-8: Relative Z (cm) ANSI 1991 Neutron Flux-to-Dose Conversion Factors. Y (cm) for Phantom Tally Plane -16 -8 2 402 802 42 442 842 92 492 892 142 542 942 192 592 992 242 642 1042 292 692 1092 0 12 412 812 52 452 852 102 502 902 152 552 952 202 602 1002 252 652 1052 302 702 1102 8 22 422 822 62 462 862 112 512 912 162 562 962 212 612 1012 262 662 1062 312 712 1112 16 74 66 58 50 42 34 26 3.3.3 32 432 832 82 482 882 132 532 932 182 582 982 232 632 1032 282 682 1082 72 472 872 122 522 922 172 572 972 222 622 1022 272 672 1072 322 722 1122 Estimated Whole Body Dose Using the Computational Phantom Appendix E provides a summary of the whole body dose for each combination of 6 phantom positions and 33 source positions in mrem/hr/kg for a male with breasts, male without breasts, and a female for each methodology ICRP-26 and ICRP-60. Estimates for the phantom at the 30.5 cm (1 ft) positions using quality factors from ANSI 1977, ANSI 1991, and ICRP-74 are provided in Tables E-1 through E-3 respectively while Tables E-4 through E-6 provide estimates with the phantom at the 91.5 cm (3 ft) positions. 54 3.3.4 Comparison of Different Conversion Factors using Dosimeter Reference Position 4 Appendix F provides a comparison the using ANSI 1977, ANSI 1991, and ICRP74 conversion factors at the reference dosimeter position. Appendices F.1 and F.2 provide tabular comparisons at 30.5 cm and 91.5 cm (1 ft and 3 ft) respectively while Appendices F.3 and F.4 provide a graphical comparison. Nine comparisons were made in each. Each consisted of considering the phantom at one of the given three locations (side, viewing window, or middle) and letting the source position vary from the front of the glove box to the back of the glove box (source distance within glove box from 6 cm to 150 cm measured from the inside front of the glove box). 3.3.5 Comparison of Whole Body Dose with Dosimeter Tally Plane Dose Appendix G provides a graphical comparison of the whole body dose estimates to the reference dosimeter dose for a male with breasts, for a male without breasts, and for a female. This comparison is given for the phantom at 30.5 cm and at 91.5 cm (1 ft and 3 ft) for the following cases: ICRP 26 methodology with ANSI 1977 dose conversion factors, ICRP 26 methodology with ANSI 1991 dose conversion factors, ICRP 60 methodology with ANSI 1991 dose conversion factors, and ICRP 60 methodology with ICRP 74 dose conversion factors. In addition, Appendix G provides comparisons of the whole body doses with the average dose of all the dosimeters located on the phantom dosimeter plan and the maximum and minimum doses from any of the dosimeters. Appendix H provides tables that give the distribution of the average, maximum, and minimum of the dosimeter readings on the dosimeter tally plane for all source locations and phantom locations (side, viewing window, and middle) for both 30.5 cm and at 91.5 cm (1 ft and 3 ft) phantom distances from the glove box.. These tables are given for each of the dosimetry 55 methodologies. Appendix H.1 provides detailed tables that provide the dosimeter location of the average, maximum, and minimum values for each configuration. Appendices H.2 through H.4 provide summary tables for each dosimetry methodology. 3.4 3.4.1 DISCUSSION OF RESULTS Neutron Radiation Field To get a feel for what the neutron radiation field is like without a glove box present or with an unshielded glove box (i.e., no specific neutron shielding material in the shell), Figures 3-10 through 3-15 compare the neutron radiation field at 30.5 cm, 91.5 cm, and 183cm (1 ft, 3ft, and 6 ft) for these two cases with the source at 60 cm inside on line V that goes from the front to the back of the glove box on a line centered on the left viewing window. With no glove box present, the calculation shows the typical circular patterns that would be expected with a more uniform field the farther the dosimeter plane is away from the source. For the unshielded glove box, the circular pattern is changed to reflect the neutron scattering that occurs within the shell of the glove box. The pattern changes are due to streaming. This shows that there is little attenuation of the field by a glove box with no neutron shielding material. In fact, since there is little attenuation, the dose in the streaming areas actually increases due to the contribution of the secondary (scattered) neutrons to those areas which the primary (streaming) neutrons affect. The farther the dose plane from the glove box the more distinct the streaming pattern becomes. For the unshielded cases, just below Z=100 cm, one sees the dose pattern change dramatically. These patterns are due to the neutrons coming from the source and traversing the bottom stainless steel plate of the glove box. The sharp line is for those 56 Figure 3-10: Field at 30.5 cm with No Glove Box. Figure 3-11: Field at 30.5 cm with No Shielding Material in Glove Box. 57 Figure 3-12: Field at 91.5 cm with No Glove Box. Figure 3-13: Field at 91.5 cm with No Shielding Material in Glove Box. 58 Figure 3-14: Field at 183 cm with No Glove Box. Figure 3-15: Field at 183 cm with No Shielding Material in Glove Box. 59 neutrons that leave the source at a small angle of incidence to the bottom plate and thus have to traverse through more of the bottom plate. The round ball shape drops lower the farther the dose plane is from the glove box. These neutrons have to travel through less of the bottom plate. The pattern in front of the left workstation at 30.5 cm (1 ft) is smeared together due to the streaming paths intersecting one another. As one moves to 91.5 cm (3 ft), the pattern takes on a "Mickey Mouse" shape while at 183 cm (6 ft) it shows distinctly the glove ports and viewing windows. The jagged patterns on the outside of the previous circular shapes are due to streaming from the other ports or windows of the glove box. Since the predominant position of a worker will be at the 1 foot position in front of the glove box, the discussion of results for the neutron radiation field will concentrate on this position for the worker with the source on line V. The source positions considered are 6, 15 30, 45, 60, 75, 90, 105, 120, 135, and 150 cm as measured from the front of the inside of the glove box going toward the back of the glove box. To better understand the effects of streaming, two figures are presented. The first is with the glove box completely shielded; i.e., the ports and windows are filled in with the same shielding materials as the shell. This will provide the field with no streaming paths. The second is with the regular glove box with glove ports open and windows in place as if a worker or workers were present. The normal glove box cases show the effects of streaming due to no viable shielding in the glove ports and with windows in place that do not offer the same degree of shielding as the shell. Each set of figures will be presented in the left column with a discussion of each in the right column. Since there are many commonalities, those will be discussed here. The change going from the shielded case to the regular case is described. For the examples discussed here, the source 60 location is six cm off the bottom of the glove box and goes back on a line through the middle of the viewing window of the left workstation. The magnitude of the dose field is throughout the plane relative to the same location in the shielded case. Depending on location, the magnitude of the change can be a factor of four or more. This is in keeping with the attenuation properties of the two inches of neutron shielding material in the shell (34% NS-3 + 1% B4C + 65% Pb whose half value thickness is 2.4 cm). Consider the region in the dose plane from the floor level to the level of the bottom of the glove box. This region does not have any streaming paths. However, the pattern of the dose field is determined by where the source is located. At the same height above the floor, the magnitude of the dose field decreases the farther the source is inside the glove box. This is due to two factors: first, the neutrons have to traverse more material to reach the same external point and are attenuated more as a result, and secondly, the distance from the source as increased. With the source close in to the front of the glove box, the streaming patterns are smeared together in many cases. As the source is moved farther back into the box, the streaming patterns become more distinct and knowing the source location, the windows or ports through which the streaming occurred are more easily identified. These streaming paths are important considerations for co-located workers since they may easily be in a higher dose field than they thought they were in. 61 With the source just 6 cm inside the glove box, the primary streaming paths are directed up to chest level through the window and to the sides of and at head level of the worker through the glove ports. Some streaming through the middle window is identified at the region above Z=400. Figure 3-16: Windows and Glove Ports Shielded with Source at 6 cm. Figure 3-17: Windows and Glove Ports Unshielded with Source at 6 cm. 62 As the source has moved back to 15 cm, the smeared shape in the middle of the glove box starts looking like "Mickey Mouse". Streaming through the middle window is plainly evident above Z=200. This could be a concern to any maintenance personnel that need to be above the glove box. Figure 3-18: Windows and Glove Ports Shielded with Source at 15 cm. To the right of the glove box, streaming from the right lower workstation and from the right middle window can be seen. "Mickey Mouse" shape Figure 3-19: Windows and Glove Ports Unshielded with Source at 15 cm. 63 As the source is moved back to 30 cm, the "Mickey Mouse" shape gets narrower. The streaming above the glove box is more easily identified with the middle window At about Z=150 on the right hand side of the glove box, the streaming from the left glove port and associated viewing Figure 3-20: Windows and Glove Ports Shielded with window of the lower right Source at 30 cm. workstation are identified. Above that is the streaming pattern from the middle right window. Figure 3-21: Windows and Glove Ports Unshielded with Source at 30 cm. 64 As the source is moved back to 45 cm, the dose field of the neutrons going through the top of the glove box becomes visible in the dose plane. Streaming through the upper left workstation ports and window, lower right workstation ports and window, and the middle window Figure 3-22: Windows and Glove Ports Shielded with are easily identified. Source at 45 cm. At about Z=300 and Y=100, streaming through the left glove port of the upper right workstation identified. can now be Figure 3-23: Windows and Glove Ports Unshielded with Source at 45 cm. 65 Above Z=300, the dose field is that coming from neutrons going through the top of the glove box. Below that level, streaming from all of the glove ports and windows is clearly identified. The "Mickey Mouse" shape is getting smaller and now appears to be detached from its Figure 3-24: Windows and Glove Ports Shielded with body below. Source at 60 cm. Figure 3-25: Windows and Glove Ports Unshielded with Source at 60 cm. 66 Above Z=300, the dose field is that coming from neutrons going through the top of the glove box. Below that level, streaming from all of the glove ports and windows is clearly identified. The "Mickey Mouse" shape is getting smaller and now is more detached from its body below. Figure 3-26: Windows and Glove Ports Shielded with Source at 75 cm. Figure 3-27: Windows and Glove Ports Unshielded with Source at 75 cm. 67 Above Z=300, the dose field is that coming from neutrons going through the top of the glove box. Below that level, streaming from all of the glove ports and windows is clearly identified. The "Mickey Mouse" shape is getting smaller and now is more detached from its body below. Figure 3-28: Windows and Glove Ports Shielded with Source at 90 cm. The dose field in the middle of the glove box due to streaming is not as smeared and is getting more localized. Figure 3-29: Windows and Glove Ports Unshielded with Source at 90 cm. 68 Above Z=300, the dose field is that coming from neutrons going through the top of the glove box. Below that level, streaming from all of the glove ports and windows is clearly identified. The "Mickey Mouse" shape is getting smaller and now is more detached from its body below. Figure 3-30: Windows and Glove Ports Shielded with Source at 105 cm. The dose field in the middle of the glove box due to streaming is less smeared and is almost localized into portions from the left and right workstations. Figure 3-31: Windows and Glove Ports Unshielded with Source at 105 cm. 69 Above Z=300, the dose field is that coming from neutrons going through the top of the glove box. Below that level, streaming from all of the glove ports and windows is clearly identified. The "Mickey Mouse" shape is getting smaller and now is more detached from its body below. Figure 3-32: Windows and Glove Ports Shielded with Source at 120 cm. The dose field in the middle of the glove box due to streaming is not smeared and is localized into portions from the right and left workstations. Figure 3-33: Windows and Glove Ports Unshielded with Source at 120 cm. 70 Above Z=300, the dose field is that coming from neutrons going through the top of the glove box. Below that level, streaming from all of the glove ports and windows is clearly identified. The "Mickey Mouse" shape is getting smaller and now is more detached from its body below. Figure 3-34: Shielded with Source at 135 cm. The dose field in the middle of the glove box due to streaming is not smeared and is localized into portions from the right and left workstations. Overall, with the source is farther away, the dose field due to streaming is getting smaller in size while the remaining field is starting to become more uniform. Figure 3-35: Windows and Glove Ports Unshielded with Source at 135 cm. 71 Above Z=300, the dose field is that coming from neutrons going through the top of the glove box. Below that level, streaming from all of the glove ports and windows is clearly identified. The "Mickey Mouse" shape is getting smaller and now is more detached from its body below. Figure 3-36: Windows and Glove Ports Shielded with Source at 150 cm. The dose field in the middle of the glove box due to streaming is not smeared and is localized into portions from the right and left workstations. Overall, with the source is farther away, the dose field due to streaming is more localized while the remaining field is becoming more uniform. Figure 3-37: Windows and Glove Ports Unshielded with Source at 150 cm. 72 Appendix C provides the comparison between the shielded and normal cases at 30.5 cm, 91.5 cm, and 183 cm (1 ft, 3 ft, and 6 ft) distances from the front of the glove box for each of the 33 different source positions. The discussion provided above for the cases where the source in on the line V and the dose plane at 30.5 cm (1 ft) applies to all of the other case. For the dose plane moves farther from the glove box, the more quickly the dose field tends to a more uniform field; especially as the source is moved farther back into the glove box. 3.4.2 Comparison of Whole Body Dose with Dosimeter Tally Plane Reference Position Dose First, before performing a comparison of the whole body dose as determined from the computational phantom, it is desirable to compare the reference position doses using the different conversion factors from ANSI 1977, ANSI 1991, and ICRP 74. For a worker working in the glove box, the discussion will center on the phantom at the 30.5 cm (1 ft) location. There are three possible phantom positions and 33 possible source positions. With M, S, and V representing the middle of the glove box, S the line 6 cm to the right of the left side, and V in front of the viewing window of the lower left workstation and 1 representing the phantom distance from the glove box, the data is presented in curves for a given phantom position and the source moving back along one of the lines M, S, or V. Thus, MxxM1 represents the source position xx on the line M with the phantom at M1. In Figures 3-38 to 3-46 it is shown that ANSI 1977 conversion factors provide a more conservative estimate of the dose with ICRP 74 dose values just slightly lower than those obtained using ANSI 1977. This same conclusion is reached for the phantom at 91.5 cm (3 ft) (see Appendix F). 73 MxxM1 Dosimeter Reference Values 0.180 0.160 The shape of the curve is to be expected since the streaming ANSI 1977 ANSI 1991 ICRP 74 mrem/hr/kg 0.140 0.120 0.100 0.080 0.060 0.040 0.020 0.000 paths either go to the side of the worker since the worker is not in front of a workstation. 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox Figure 3-38: MxxM1. SxxM1 Dosimeter Reference Values As distance along S increases, streaming through the left workstation glove ports and 0.090 0.080 mrem/hr/kg 0.070 0.060 0.050 0.040 0.030 0.020 0.010 0.000 viewing window causes the dose ANSI 1977 ANSI 1991 ICRP 74 to increase while moving the source farther back in the glove 0 15 30 45 60 75 90 105 120 135 150 box results in the dose decreasing. Source Distance Inside Glovebox Figure 3-39: SxxM1. VxxM1 Dosimeter Reference Values 7.000E-02 6.000E-02 Streaming effects through the right glove port of the left workstation only affect the dose for distances close to the front of ANSI 1977 ANSI 1991 ICRP 74 mrem/hr/kg 5.000E-02 4.000E-02 3.000E-02 2.000E-02 1.000E-02 0.000E+00 0 15 30 45 60 75 90 105 120 135 150 the glove box. Source Distance Inside Glovebox Figure 3-40: VxxM1. 74 MxxS1 Dosimeter Reference Values 0.070 0.060 The first hump shows the streaming through the left glove ANSI 1977 ANSI 1991 ICRP 74 mrem/hr/kg 0.050 0.040 0.030 0.020 0.010 0.000 port of the left workstation while the larger bump reflects the streaming through the viewing window. 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox Figure 3-41: MxxS1. SxxS1 Dosimeter Reference Values The shape of the curve is 0.140 0.120 to be expected since the streaming ANSI 1977 ANSI 1991 ICRP 74 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 paths either go to the side of the worker since the worker is not in 0 15 30 45 60 75 90 105 120 135 150 front of a workstation. Source Distance Inside Glovebox Figure 3-42: SxxS1. VxxS1 Dosimeter Reference Values 6.000E-02 5.000E-02 Streaming effects through the left glove port of the left ANSI 1977 ANSI 1991 ICRP 74 mrem/hr/kg 4.000E-02 3.000E-02 2.000E-02 1.000E-02 0.000E+00 0 15 30 45 60 75 90 105 120 135 150 workstation only affect the dose for distances close to the front of the glove box. Source Distance Inside Glovebox Figure 3-43: VxxS1. 75 MxxV1 Dosimeter Reference Values 0.080 0.070 Streaming effects through the right glove port of the left ANSI 1977 ANSI 1991 ICRP 74 mrem/hr/kg 0.060 0.050 0.040 0.030 0.020 0.010 0.000 workstation only affect the dose for distances close to the front of the glove box. The smaller 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox broader hump is due to the viewing window. Figure 3-44: MxxV1. SxxV1 Dosimeter Reference Values There 0.100 0.090 0.080 0.070 0.060 0.050 0.040 0.030 0.020 0.010 0.000 is relatively constant streaming through either ANSI 1977 ANSI 1991 ICRP 74 mrem/hr/kg the left glove port or the viewing window with the phantom in this 0 15 30 45 60 75 90 105 120 135 150 position and the source on the side. Source Distance Inside Glovebox Figure 3-45: SxxV1. VxxV1 Dosimeter Reference Values 8.000E-01 7.000E-01 Since ANSI 1977 ANSI 1991 ICRP 74 the phantom is mrem/hr/kg 6.000E-01 5.000E-01 4.000E-01 3.000E-01 2.000E-01 1.000E-01 0.000E+00 0 15 30 45 60 75 90 105 120 135 150 within the streaming pattern for all distances, the curve reflects the change in distance as the source moves toward the back of the glove box. Source Distance Inside Glovebox Figure 3-46: VxxV1. 76 For each of the cases described above, the whole body dose was compared to the reference position dosimeter. The whole body dose in this case was calculated according to ICRP 26 methodology with neutron quality factors determined from ANSI 1977. This case was chosen since it is the regulatory position taken at Los Alamos. Other cases were looked at and are reported in Appendix G. The whole body dose was calculated for a "male with breasts", a normal male (without breasts), and for a female. The calculations for a "male with breasts" account for the breast tissue that a male has. Although the breast tissue volume for a male is small compared to a female, computational models show that that there is an increase in effective dose equivalent for low energy photons for smaller breast tissue volumes (Kramer and Drexler 1982). The whole body dose for a male with breasts was greater than that of a male without breasts. In most cases the dose to a male without breasts was larger than the dose for a female. This is predominantly due to the dose that the testes receive. Table 3-9 provides the percentage of the whole body dose that comes from the dose received by the testes. Figures 3-47 to 3-55 provide the comparisons of the reference dosimeter with the different whole body doses calculated. In general, the whole body dose curves do not follow the reference position dosimeter. From a streaming point of view, the streaming paths will hit different parts of the body and the reference dosimeter may not be in all the paths. 77 Table 3-9: Contribution of Testes to Male Whole Body Dose. ANSI 1977 Testes % Contribution MwB 47.2 39.3 45.9 52.5 36.0 44.0 51.1 26.2 30.2 46.9 27.4 25.8 40.0 24.2 26.1 36.0 21.2 23.6 33.4 20.3 22.0 30.0 21.5 19.9 28.6 20.1 18.7 28.6 22.1 18.3 MwoB 58.3 48.4 55.8 62.2 51.7 51.0 60.5 38.4 41.5 58.0 39.4 40.0 54.6 32.2 45.3 53.0 30.7 42.1 51.0 30.8 39.4 47.9 32.9 35.2 46.4 32.0 32.3 46.8 37.1 30.9 Run 1S75V1A 1S90M1A 1S90S1A 1S90V1A 1S05M1A 1S05S1A 1S05V1A 1S20M1A 1S20S1A 1S20V1A 1S35M1A 1S35S1A 1S35V1A 1S50M1A 1S50S1A 1S50V1A 1V06M1A 1V06S1A 1V06V1A 1V15M1A 1V15S1A 1V15V1A 1V30M1A 1V30S1A 1V30V1A 1V45M1A 1V45S1A 1V45V1A 1V60M1A 1V60S1A ANSI 1977 ICRP 26 4.27E-03 2.21E-03 2.79E-03 3.14E-03 2.11E-03 2.06E-03 2.40E-03 1.56E-03 1.78E-03 1.97E-03 1.28E-03 1.36E-03 1.62E-03 1.09E-03 1.14E-03 1.41E-03 8.89E-03 8.82E-03 2.32E-02 1.25E-02 1.24E-02 2.68E-02 1.03E-02 9.71E-03 1.73E-02 7.25E-03 6.97E-03 1.11E-02 5.54E-03 5.05E-03 Testes % Contribution MwB 21.9 21.5 46.9 19.8 23.8 44.5 18.3 22.7 45.7 18.0 22.6 42.9 17.5 21.8 40.3 16.3 37.8 37.8 18.6 44.6 45.8 26.0 31.8 31.5 26.5 28.6 29.1 26.6 31.4 31.9 MwoB 39.4 33.1 56.2 34.3 36.6 54.2 30.9 37.2 55.9 29.8 39.2 53.6 28.8 38.9 50.8 27.1 47.3 46.6 30.3 51.8 52.5 39.4 43.0 42.5 39.1 41.8 42.3 37.7 49.2 50.1 Run 1M06M1A 1M06S1A 1M06V1A 1M15M1A 1M15S1A 1M15V1A 1M30M1A 1M30S1A 1M30V1A 1M45M1A 1M45S1A 1M45V1A 1M60M1A 1M60S1A 1M60V1A 1M75M1A 1M75S1A 1M75V1A 1M90M1A 1M90S1A 1M90V1A 1M05M1A 1M05S1A 1M05V1A 1M20M1A 1M20S1A 1M20V1A 1M35M1A 1M35S1A 1M35V1A ICRP 26 2.43E-02 2.50E-03 1.01E-02 2.68E-02 3.80E-03 1.37E-02 1.73E-02 3.59E-03 1.04E-02 1.11E-02 3.28E-03 7.64E-03 7.13E-03 2.76E-03 5.92E-03 5.12E-03 2.15E-03 4.09E-03 3.78E-03 1.67E-03 3.05E-03 2.74E-03 1.55E-03 2.32E-03 2.20E-03 1.18E-03 1.90E-03 1.91E-03 1.09E-03 1.66E-03 78 ANSI 1977 Run 1M50M1A 1M50S1A 1M50V1A 1S06M1A 1S06S1A 1S06V1A 1S15M1A 1S15S1A 1S15V1A 1S30M1A 1S30S1A 1S30V1A 1S45M1A 1S45S1A 1S45V1A 1S60M1A 1S60S1A 1S60V1A 1S75M1A 1S75S1A ICRP 26 1.43E-03 9.18E-04 1.43E-03 3.21E-03 2.06E-02 1.29E-02 4.93E-03 2.42E-02 1.71E-02 4.85E-03 1.49E-02 1.25E-02 4.26E-03 9.24E-03 9.29E-03 3.36E-03 6.21E-03 6.08E-03 2.89E-03 4.29E-03 Testes % Contribution MwB 24.5 20.7 17.0 38.8 46.4 43.9 30.3 55.5 42.0 29.9 55.5 29.7 26.9 53.8 28.1 22.9 52.7 24.5 22.5 51.0 MwoB 42.2 36.6 28.8 48.7 57.1 54.5 43.3 63.6 49.8 42.9 62.9 43.0 36.4 61.5 48.0 31.7 60.9 44.0 33.5 59.8 Run 1V60V1A 1V75M1A 1V75S1A 1V75V1A 1V90M1A 1V90S1A 1V90V1A 1V05M1A 1V05S1A 1V05V1A 1V20M1A 1V20S1A 1V20V1A 1V35M1A 1V35S1A 1V35V1A 1V50M1A 1V50S1A 1V50V1A Average ANSI 1977 ICRP 26 7.47E-03 3.97E-03 3.87E-03 4.99E-03 3.39E-03 2.51E-03 3.69E-03 2.53E-03 2.04E-03 2.69E-03 1.99E-03 1.59E-03 2.13E-03 1.65E-03 1.39E-03 1.78E-03 1.31E-03 1.27E-03 1.47E-03 Testes % Contribution MwB 26.7 30.0 32.8 24.8 31.7 29.7 24.8 29.8 29.9 22.6 28.7 29.5 21.9 28.3 30.7 21.5 25.6 30.6 19.7 30.9 MwoB 37.4 48.8 52.6 34.6 49.9 49.3 34.2 47.7 49.1 31.4 46.4 48.0 30.2 45.3 48.7 29.8 42.6 48.6 27.6 43.8 79 MxxM1 - ICRP 26 / ANSI 1977 0.350 0.300 0.250 0.200 0.150 0.100 0.050 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum Dosimeter Reference Male w/ Breasts Male without Breasts Female mrem/hr/kg Source Distance inside Glovebox Figure 3-47: MxxM1- ICRP 26 ANSI 1977. SxxM1- ICRP 26 / ANSI 1977 0.180 0.160 0.140 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.120 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure 3-48: SxxM1- ICRP 26 ANSI 1977. 80 VxxM1- ICRP 26 / ANSI 1977 0.300 0.250 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure 3-49: VxxM1- ICRP 26 ANSI 1977. MxxS1- ICRP 26 / ANSI 1977 0.160 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure 3-50: MxxS1- ICRP 26 ANSI 1977. 81 SxxS1- ICRP 26 / ANSI 1977 0.300 0.250 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure 3-51: SxxS1- ICRP 26 ANSI 1977. VxxS1- ICRP 26 / ANSI 1977 0.300 0.250 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure 3-52: VxxS1- ICRP 26 ANSI 1977. 82 MxxV1- ICRP 26 / ANSI 1977 0.350 0.300 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.250 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure 3-53: MxxV1- ICRP 26 ANSI 1977. SxxV1- ICRP 26 / ANSI 1977 0.400 0.350 0.300 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.250 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure 3-54: SxxV1- ICRP 26 ANSI 1977. 83 VxxV1- ICRP 26 / ANSI 1977 1.000 0.800 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female mrem/hr/kg 0.600 0.400 0.200 0.000 0 15 30 45 60 75 90 105 120 135 150 Source Distance inside Glovebox Figure 3-55: VxxV1- ICRP 26 ANSI 1977. 3.4.3 Comparison of Whole Body Dose with Various Dosimeter Tally Plane Doses For each configuration, the average, maximum, and minimum values that occurred on the dosimeter tally plane were determined. These were compared with the whole body doses that were calculated using the phantom. For the case of ICRP 26 methodology using ANSI 1977 data, Figures 3-47 to 3-55 above show the comparison. Appendix G provides the comparison for other cases. For this case it is seen that the minimum value tracks very well with the whole body doses that were calculated. From Table H.3-1, it is seen that 77% of the time, the dosimeter with the minimum value is one that is worn at waist level. When the phantom is at one of the 91.5 cm (3 ft) locations, the dosimeter with the minimum value is worn at the waist level 74% of the time. 84 Chapter 4: Conclusions and Recommendations 4.1 GENERAL DISCUSSION Shielding problems can be among the most difficult to solve. Coupled with the task of estimating the dose that a worker receives makes it even more difficult. Because of the traditional way shielding is taught, most people do not understand that there are realistic issues dealing with non-uniform radiation fields resulting from streaming of radiation from an experiment, process, or operation through areas that are less shielded than others; especially when the work involves "shielded" glove boxes. This study with the following conclusions and recommendations is the author's attempt to clarify some of these issues. 4.2 4.2.1 CONCLUSIONS AND RECOMMENDATIONS Conclusions The followings conclusions are made: 1) The neutron radiation field and associated dose field are very dependent on the streaming paths available. In the case considered here, the magnitude of the change of the dose field relative to the same location in the shielded case can be a factor or 4 or more. This is in keeping with the attenuation properties of the two inches of neutron shielding material in the shell (34% NS-3 + 1% B4C + 65% Pb whose half value thickness is 2.4 cm). Thus, in streaming areas, the radiation field is as if there were no shielding present. 2) With the source close in to the front of the glove box, the streaming patterns are smeared together in many cases. As the source is moved 85 farther back into the box, the streaming patterns are more collimated. Thus, depending on the location of the worker and where the source material is, the dose received can be significantly higher. 3) ANSI 1977 conversion factors provide a more conservative estimate of the dose with ICRP 74 dose values just slightly lower than those obtained using ANSI 1977. 4) The whole body dose for a male with breasts was greater than that of a male without breasts or a female. In most cases the dose to a male without breasts was larger than the dose for a female. This is predominantly due to the dose that the testes receive. The testes contribute almost 44% to the total whole body dose on the average for a male without breasts with a range of 27% to 64%. 5) Consider the region in the dose plane from the floor level to the level of the bottom of the glove box. Although this region does not have any streaming paths due to glove ports or windows, the non-uniform field in this region is due to the varying thicknesses of the bottom shell that the radiation has to traverse. Thus, the pattern of the dose field is determined by where the source is located. At the same height above the floor, the magnitude of the dose field decreases the farther the source is inside the glove box. Thus, for normal working conditions where the source is close to the front of the glove box, the dose to the testes is higher. 6) In the dosimeter tally plane, the dosimeter with the minimum value tracks the whole body dose very well. The dosimeter with the minimum value is one that is worn at waist level 77% of the time. When the phantom is at 86 one of the 3 ft locations, the dosimeter with the minimum value is worn at the waist level 74% of the time. 7) The reference dosimeter position can overestimate the whole body dose between a factor of two to six depending on location of the phantom and with the source material close to the front of the glove box. 4.2.2 Recommendations 1) Experimental validation and benchmarking of MCNP models of glove boxes is needed. 2) Since the LANL TLD can be in a significantly varying radiation field (i.e., each element is not seeing the same uniform field), a reevaluation of the dose algorithms should be performed. In addition, further studies of the angular dependence of the dosimeter should be made with the dosimeter in a highly varying radiation field. 3) Collaboration with experimenters conducting similar photon studies is needed. Most radiation sources of interest are photon sources in addition to neutron sources. 4) Streaming paths are important considerations for co-located workers since they may easily be in a higher dose field than they thought they were in. These paths should be determined for all glove boxes so that a proper ALARA (As Low As Reasonably Achievable) evaluation can be made. These evaluations focus on the different methods that reduce dose: increase shielding (type of shielding, internal or external, thickness required, and cost), minimize time (as relates to productivity and operational concerns relative to potential dose received), and maximize 87 distance between source material and worker. These methods are not independent of each other. 5) Currently, dosimeters are required to be worn between waist and neck level. The reference position in the middle of the chest provides an overly conservative estimate of the whole body dose by a factor of two to six depending on location of material and where the worker stands. Consideration should be given to requiring dosimeters to be worn at waist level. This should provide a better estimate of the whole body dose 75% of the time. Experimental validation of this recommendation is needed. 6) Internal shielding around source material that is not being handled or processed in some fashion should be considered. This would reduce the dose from this material for all streaming paths of interest. 7) Glove ports and windows in workstations that are not being used should be provided with external shielding to reduce the dose from these streaming paths. 8) Additional shielding from waist level down and under the glove box should be provided either in the design and construction of new glove boxes or externally if they are already built. This is needed in order to reduce the dose to the testes for male workers. 9) Estimates of whole body dose should include males with breasts. Males have about 8% of all breast cancers. Since males have a smaller breast tissue volume, a higher dose is received by the male compared to the female who has a larger breast tissue volume. 88 Appendix A: Neutron Attenuation Provided By Several Different Materials 89 METHODOLOGY FOR DETERMINING THE ATTENUATION OF DIFFERENT NEUTRON SHIELDING MATERIALS A point source of clean weapons grade (WG) Pu was placed at the origin. At a distance of 45 cm from the source, a spherical shell ranging between 2 and 20 cm was placed that contained the material of interest. At a distance of 100 cm, the dose (mrem/hr/kg of WG Pu) and spectra (n/s/kg of WG Pu)) were determined. For each material, runs were made for shell thicknesses of 0, 2, 4, 6, 8, 10, 12, 14, 16, 18, and 20 cm. The dose at thickness t, Dt, was divided by the dose at 0 cm, D0. A plot of ln (Dt/ D0) vs thickness was made for each material. The attenuation coefficient is the negative of the value of the slope. The half value layer and tenth value layer were then determined from the attenuation coefficient. Table D-1 provides the attenuation coefficient based on dose and the corresponding half-and tenth-value layers for many shielding materials of interest. Table D-2 provides the same except that it was based on the spectra. Table A-1: Attenuation Coefficients for Various Materials Based on Dose Material Nylon NS-3 + 1% B4C + 65% Pb NS-4 + 56% B4c + 32% Pb NS-4-FR + 15% Pb NS-4 + 88% Pb NS-1 + 50% B4C + 34% Pb NS-3 + 11.25% B4C + 70.75% Pb NS-4-FR + 6.5% B4C + 8.5% Pb NS-3 + 82% Pb NS-1 + 84% Pb PVC Material m702 m516 m521 m524 m520 m511 m517 m525 m515 m510 m703 90 Att. Coef. 0.3028 0.2874 0.2850 0.2698 0.2563 0.2514 0.2493 0.2321 0.2120 0.1893 0.1885 X1/2 (cm) 2.289 2.412 2.432 2.569 2.704 2.757 2.780 2.986 3.270 3.662 3.677 X1/10 (cm) 7.604 8.012 8.079 8.534 8.984 9.159 9.236 9.921 10.861 12.164 12.215 Material NS-4 + 56% B4C Paraffin Lithium Hydride Polyethylene Rx #213 Krafton-XP3 NS-4-FR + 6.5% B4C Krafton-N5 WEP Rx #207 Rx #259 Rx #210 NS-4-FR Krafton-C1 Premadex Rx #201 NS-3 + 11.25% B4C NS-4 NS-3 + 4% B4C Plexiglas (Lucite) Borated Water Heavy Water NS-3 Water Rx #215 Bisco Rx #244 NS-1 + 50% B4C Kynar Rx #237 Boron Carbide Rx #217 Lexan Borobond 4.1 Rx #277 Material m519 m526 m543 m528 m534 m506 m523 m505 m541 m532 m539 m533 m522 m504 m530 m531 m514 m518 m513 m527 m003 m004 m512 m002 m535 m500 m538 m509 m701 m537 m503 m536 m507 m501 m540 91 Att. Coef. 0.1848 0.1824 0.1784 0.1762 0.1761 0.1713 0.1698 0.1697 0.1693 0.1679 0.1678 0.1676 0.1664 0.1660 0.1578 0.1558 0.1520 0.1503 0.1498 0.1478 0.1469 0.1469 0.1461 0.1452 0.1451 0.1395 0.1365 0.1345 0.1343 0.1304 0.1296 0.1293 0.1209 0.1117 0.1084 X1/2 (cm) 3.751 3.800 3.885 3.934 3.936 4.046 4.082 4.085 4.094 4.128 4.131 4.136 4.166 4.176 4.393 4.449 4.560 4.612 4.627 4.690 4.718 4.718 4.744 4.774 4.777 4.969 5.078 5.154 5.161 5.316 5.348 5.361 5.733 6.205 6.394 X1/10 (cm) 12.460 12.624 12.907 13.068 13.075 13.442 13.561 13.569 13.601 13.714 13.722 13.739 13.838 13.871 14.592 14.779 15.149 15.320 15.371 15.579 15.675 15.675 15.760 15.858 15.869 16.506 16.869 17.120 17.145 17.658 17.767 17.808 19.045 20.614 21.242 Material NS-1 Cadmium Glass Liquid Hydrogen Silicon Rubber Teflon Leaded Glass 6.0 Boral Graphite Leaded Glass 3.8 Compacted Tuff Fiberglass Borosilicate Glass Ordinary Concrete Iconel 316SS 304SS Pyrex Carbon Steel Polyurethane Air Material m508 m401 m542 m704 m705 m403 m502 m005 m402 m800 m700 m400 m200 m303 m301 m300 m404 m302 m529 m001 Att. Coef. X1/2 (cm) 0.1055 6.570 0.0993 6.980 0.0860 8.060 0.0757 9.157 0.0733 9.456 0.0732 9.469 0.0657 10.550 0.0549 12.626 0.0548 12.649 0.0548 12.649 0.0513 13.512 0.0470 14.748 0.0457 15.167 0.0433 16.008 0.0382 18.145 0.0366 18.938 0.0364 19.043 0.0266 26.058 0.0004 1732.868 0.0000 346573.590 X1/10 (cm) 21.825 23.188 26.774 30.417 31.413 31.456 35.047 41.941 42.018 42.018 44.885 48.991 50.385 53.177 60.277 62.912 63.258 86.563 5756.463 1151292.546 92 Table A-2: Attenuation Coefficients for Various Materials Material NS-4 + 56% B4c + 32% Pb NS-3 + 1% B4C + 65% Pb NS-1 + 50% B4C + 34% Pb NS-3 + 11.25% B4C + 70.75% Pb NS-4-FR + 15% Pb NS-4-FR + 6.5% B4C + 8.5% Pb Nylon NS-4 + 88% Pb NS-4 + 56% B4C PVC NS-4-FR + 6.5% B4C Rx #210 Lithium Hydride WEP Rx #259 Rx #207 Rx #201 Premadex NS-3 + 82% Pb NS-3 + 11.25% B4C Paraffin NS-3 + 4% B4C Polyethylene Rx #213 Borated Water Rx #215 Bisco NS-1 + 50% B4C Rx #244 Krafton-C1 Krafton-N5 NS-4-FR Number Att. Coef. m521 0.2847 m516 0.2841 m511 0.2485 m517 0.2456 m524 0.2375 m525 0.2318 m702 0.2197 m520 0.2027 m519 0.1840 m703 0.1800 m523 0.1661 m533 0.1661 m543 0.1654 m541 0.1629 m539 0.1622 m532 0.1608 m531 0.1514 m530 0.1504 m515 0.1499 m514 0.1481 m526 0.1481 m513 0.1440 m528 0.1408 m534 0.1407 m003 0.1388 m535 0.1355 m500 0.1338 m509 0.1305 m538 0.1293 m504 0.1290 m505 0.1275 m522 0.1257 93 X1/2 (cm) 2.435 2.440 2.789 2.822 2.919 2.990 3.155 3.420 3.767 3.851 4.173 4.173 4.191 4.255 4.273 4.311 4.578 4.609 4.624 4.680 4.680 4.814 4.923 4.926 4.994 5.115 5.180 5.311 5.361 5.373 5.436 5.514 X1/10 (cm) 8.088 8.105 9.266 9.375 9.695 9.933 10.481 11.360 12.514 12.792 13.863 13.863 13.921 14.135 14.196 14.320 15.209 15.310 15.361 15.548 15.548 15.990 16.354 16.365 16.589 16.993 17.209 17.644 17.808 17.849 18.059 18.318 Material Krafton-XP3 NS-1 + 84% Pb Boron Carbide Rx #237 NS-4 Water Plexiglas (Lucite) Borobond 4.1 NS-3 Rx #277 Rx #217 Lexan Kynar Silicon Rubber NS-1 Liquid Hydrogen Boral Cadmium Glass Borosilicate Glass Fiberglass Iconel Pyrex 316SS 304SS Ordinary Concrete Leaded Glass 6.0 Leaded Glass 3.8 Carbon Steel Teflon Compacted Tuff Heavy Water Graphite Polyurethane Air Number Att. Coef. X1/2 (cm) X1/10 (cm) m506 0.1234 5.617 18.660 m510 0.1232 5.626 18.690 m503 0.1231 5.631 18.705 m537 0.1202 5.767 19.156 m518 0.1137 6.096 20.251 m002 0.1090 6.359 21.125 m527 0.1036 6.691 22.226 m501 0.1019 6.802 22.597 m512 0.1009 6.870 22.820 m540 0.0968 7.161 23.787 m536 0.0827 8.381 27.843 m507 0.0700 9.902 32.894 m701 0.0676 10.254 34.062 m704 0.0616 11.252 37.380 m508 0.0588 11.788 39.160 m542 0.0537 12.908 42.879 m502 0.0519 13.355 44.366 m401 0.0374 18.533 61.566 m400 0.0226 30.670 101.884 m700 0.0211 32.851 109.127 m303 0.0174 39.836 132.332 m404 0.0122 56.815 188.736 m301 0.0092 75.342 250.281 m300 0.0075 92.420 307.011 m200 0.0064 108.304 359.779 m403 0.0055 126.027 418.652 m402 0.0032 216.608 719.558 m302 0.0027 256.721 852.809 m705 0.0009 770.164 2558.428 m800 0.0007 990.210 3289.407 m004 0.0004 1732.868 5756.463 m005 0.0004 1732.868 5756.463 m529 0.0000 34657.359 115129.255 m001 0.0000 173286.795 575646.273 94 Appendix B: Example Of Spreadsheet Format For Calculating Phantom Dose Estimates 95 Table B-1: Sheet 1: Input Phantom ANSI 1977 Neutron Tally Date: 23 Dec 2003 Preparer: Neutron ABC src particle / hr-basis fm: 2.29E+08 1 kg Pu (clean) Phantom 1 ft from GB 6.359E+04 sp/s-kg * 3600 s/hr 1940 keV Average of neutron energy spectrum Tally Cell 306 316 326 336 346 356 366 376 386 396 406 416 426 436 446 456 466 476 486 496 506 516 526 536 546 556 mrem/sp 8.29808E-11 5.86938E-10 8.23482E-10 3.88792E-12 8.39152E-14 1.07729E-10 6.26512E-11 4.11304E-10 8.39152E-14 2.66822E-10 1.52873E-10 2.92987E-10 5.12470E-10 7.42672E-11 9.23479E-11 9.62839E-11 7.87520E-11 9.37811E-15 2.07578E-10 4.68944E-10 3.74382E-10 2.63250E-10 1.14310E-10 1.02074E-09 5.54599E-11 7.95029E-11 sp/hr-basis mrem/hr-basis 2.29E+08 1.90E-02 2.29E+08 1.34E-01 2.29E+08 1.89E-01 2.29E+08 8.90E-04 2.29E+08 1.92E-05 2.29E+08 2.47E-02 2.29E+08 1.43E-02 2.29E+08 9.42E-02 2.29E+08 1.92E-05 2.29E+08 6.11E-02 2.29E+08 3.50E-02 2.29E+08 6.71E-02 2.29E+08 1.17E-01 2.29E+08 1.70E-02 2.29E+08 2.11E-02 2.29E+08 2.20E-02 2.29E+08 1.80E-02 2.29E+08 2.15E-06 2.29E+08 4.75E-02 2.29E+08 1.07E-01 2.29E+08 8.57E-02 2.29E+08 6.03E-02 2.29E+08 2.62E-02 2.29E+08 2.34E-01 2.29E+08 1.27E-02 2.29E+08 1.82E-02 96 Table B-2: Sheet 2 Phantom plus ICRP 26 Remainder Androgynous Phantom: ICRP 26 Cell 6 16 26 36 46 56 66 76 86 96 106 116 126 136 146 156 166 176 186 196 206 216 226 236 246 256 Sheet 4 Sheet 4 Sheet 3 Sheet 3 Tissue mrem /hr-basis Brain 1.90E-02 Thyroid 1.34E-01 Thymus 1.89E-01 Lungs 8.90E-04 Heart 1.92E-05 Adrenals 2.47E-02 Kidneys 1.43E-02 Liver 9.42E-02 Gall Bladder 1.92E-05 Pancreas 6.11E-02 Spleen 3.50E-02 Esophagus 6.71E-02 Stomach 1.17E-01 Small Intestine 1.70E-02 Ascending Colon 2.11E-02 Transverse Colon 2.20E-02 Descending Colon 1.80E-02 Sigmoid 2.15E-06 Bladder 4.75E-02 Testes 1.07E-01 Gentalia 8.57E-02 Skin 6.03E-02 Bone 2.62E-02 Breast 2.34E-01 Ovaries 1.27E-02 Uterus 1.82E-02 Red Bone Marrow 2.73E-02 NBS 2.60E-02 Colon 1.76E-02 ULI 1.76E-02 Cell 6 16 26 36 46 56 66 76 86 96 106 116 126 136 146 156 166 176 186 196 206 216 226 236 246 256 ICRP 60 Tissue mrem /hr-basis Brain 1.90E-02 Thyroid 1.34E-01 Thymus 1.89E-01 Lungs 8.90E-04 Heart 1.92E-05 Adrenals 2.47E-02 Kidneys 1.43E-02 Liver 9.42E-02 Gall Bladder 1.92E-05 Pancreas 6.11E-02 Spleen 3.50E-02 Esophagus 6.71E-02 Stomach 1.17E-01 Small 1.70E-02 Ascending 2.11E-02 Transverse 2.20E-02 Descending 1.80E-02 Sigmoid 2.15E-06 Bladder 4.75E-02 Testes 1.07E-01 Gentalia 8.57E-02 Skin 6.03E-02 Bone 2.62E-02 Breast 2.34E-01 Ovaries 1.27E-02 Uterus 1.82E-02 Red Bone 2.73E-02 NBS 2.60E-02 Colon 1.76E-02 ULI 1.76E-02 Remainder 2.02E-02 Remainder 2.05E-02 Determination of Reminder Tissues Rank Tissue 16 Brain 1 Thymus 20 Heart 13 Adrenals 19 Kidneys 3 Liver 20 Gall Bladder 6 Pancreas 9 Spleen 5 Esophagus 2 Stomach 18 Small 15 Ascending 14 Transverse 17 Descending 22 Sigmoid 8 Bladder 4 Gentalia 7 Skin 11 Bone 10 Colon 12 ULI mrem/hr-basis Top 5 Remainder Tissues 1 Thymus 1.89E-01 Stomach 2 Liver 3 Gentalia 4 5 Esophagus 1.90E-02 1.89E-01 1.92E-05 2.47E-02 1.43E-02 9.42E-02 1.92E-05 6.11E-02 3.50E-02 6.71E-02 1.17E-01 1.70E-02 2.11E-02 2.20E-02 1.80E-02 2.15E-06 4.75E-02 8.57E-02 6.03E-02 2.62E-02 2.73E-02 2.60E-02 1.17E-01 9.42E-02 8.57E-02 6.71E-02 Male Female 97 Table B-3: Sheet 3: Colon-ULI Ascending Transverse Descending Sigmoid 1 Sum Colon dose rate mrem/hr-basis 2.11E-02 2.20E-02 1.80E-02 2.15E-06 Tissue Sum of Fractions ULI weighted dose rate weighted fraction mrem/hr-basis mrem/hr-basis fraction mrem/hr-basis 0.253 5.35E-03 2.11E-02 0.253 5.35E-03 0.340 7.49E-03 2.20E-02 0.340 7.49E-03 0.263 4.74E-03 1.80E-02 0.263 4.74E-03 0.144 3.09E-07 1.76E-02 1.76E-02 98 Table B-4: Sheet 4: Red Bone Marrow Near Bone Surface Red Bone Marrow E (keV) 60 100 300 500 1000 1940 Bone mrem/hr-basis RBM 2.62E-02 Equations Red Bone Marrow Near Bone Surface RBM Ratio BM to Bone NBS 0.2794 1.0197 0.519 1.0088 0.9481 1.0052 1.0004 1.0049 1.0192 1.0051 1.04E+00 9.93E-01 Ratio BM to Bone mrem/hr-basis NBS RBM NBS 1.04E+00 9.93E-01 2.73E-02 2.60E-02 1.2 1.0 Ratio BM to Bone 0.8 0.6 y = 1.043 1 e ( 0.006629 x ) 0.4 y = 1.0127 0.0000102 x 0.2 0 200 400 600 800 1000 1200 where x = E (keV) and y = Ratio BM to Bone E (keV) Ratio BM to Bone ve Energy y = 1.043 1 e ( 0.006629 x ) Near Bone Surface 1.2 1.0 Ratio NBS to Bone 0.8 0.6 0.4 0.2 0.0 0 200 400 600 800 1000 1200 E (keV) Ratio NBS to Bone vs energy x column vs y column y = 1.0127 0.0000102 x 99 Table B-5: Sheet 5: ICRP 60 Remainder ICRP 60: Male and Female Remainder Determination Male Female Tissue Fraction mrem/hr-basismrem/hr-basis mrem/hr-basis Adrenal 0.00422 2.47E-02 1.04E-04 1.04E-04 Brain 0.36803 1.90E-02 6.99E-03 6.99E-03 ULI 0.16817 1.76E-02 2.96E-03 2.96E-03 SI 0.28476 1.70E-02 4.84E-03 4.84E-03 Kidney 0.07737 1.43E-02 1.11E-03 1.11E-03 Pancreas 0.02437 6.11E-02 1.49E-03 1.49E-03 Spleen 0.04728 3.50E-02 1.65E-03 1.65E-03 Thymus 0.0054 1.89E-01 1.02E-03 1.02E-03 Uterus 0.02042 1.82E-02 3.72E-04 Remainder 2.0164E-02 2.0536E-02 100 Table B-6: Sheet: EDE and ED ICRP 26 Male with breasts Tissue E Testes Breast RBM Lungs Thyroid NBS Thymus Stomach Liver Gentalia Esophagus DE mrem/hr-b 1.07E-01 2.34E-01 2.73E-02 8.90E-04 1.34E-01 2.60E-02 1.89E-01 1.17E-01 9.42E-02 8.57E-02 6.71E-02 fraction 0.25 0.15 0.12 0.12 0.03 0.03 0.06 0.06 0.06 0.06 0.06 mrem/hr-b 2.68E-02 3.51E-02 3.28E-03 1.07E-04 4.03E-03 7.79E-04 1.13E-02 7.04E-03 5.65E-03 5.14E-03 4.02E-03 1.03E-01 Male without breasts Tissue E Testes Breast RBM Lungs Thyroid NBS Thymus Stomach Liver Gentalia Esophagus DE mrem/hr-b 1.07E-01 2.34E-01 2.73E-02 8.90E-04 1.34E-01 2.60E-02 1.89E-01 1.17E-01 9.42E-02 8.57E-02 6.71E-02 fraction 0.25 0 0.12 0.12 0.03 0.03 0.06 0.06 0.06 0.06 0.06 mrem/hr-b 2.68E-02 0.00E+00 3.28E-03 1.07E-04 4.03E-03 7.79E-04 1.13E-02 7.04E-03 5.65E-03 5.14E-03 4.02E-03 6.82E-02 Female Tissue E Ovaries Breast RBM Lungs Thyroid NBS Thymus Stomach Liver Gentalia Esophagus DE mrem/hr-b 1.27E-02 2.34E-01 2.73E-02 8.90E-04 1.34E-01 2.60E-02 1.89E-01 1.17E-01 9.42E-02 8.57E-02 6.71E-02 fraction 0.25 0.15 0.12 0.12 0.03 0.03 0.06 0.06 0.06 0.06 0.06 mrem/hr-b 3.17E-03 3.51E-02 3.28E-03 1.07E-04 4.03E-03 7.79E-04 1.13E-02 7.04E-03 5.65E-03 5.14E-03 4.02E-03 7.96E-02 ICRP 60 Male with breasts Tissue Esophagus hyroid Skin T NBS Remainder ED Testes RBM Colon Lungs Stomach Bladder Breast Liver mrem/hr-b 1.07E-01 2.73E-02 1.76E-02 8.90E-04 1.17E-01 4.75E-02 2.34E-01 9.42E-02 6.71E-02 1.34E-01 6.03E-02 2.60E-02 2.02E-02 fraction 0.2 0.12 0.12 0.12 0.12 0.05 0.05 0.05 0.05 0.05 0.01 0.01 0.05 mrem/hr-b 2.15E-02 3.28E-03 2.11E-03 1.07E-04 1.41E-02 2.38E-03 1.17E-02 4.71E-03 3.35E-03 6.72E-03 6.03E-04 2.60E-04 1.01E-03 7.18E-02 Male without breasts Tissue Esophagus hyroid Skin T NBS Remainder ED Testes RBM Colon Lungs Stomach Bladder Breast Liver mrem/hr-b 1.07E-01 2.73E-02 1.76E-02 8.90E-04 1.17E-01 4.75E-02 2.34E-01 9.42E-02 6.71E-02 1.34E-01 6.03E-02 2.60E-02 2.02E-02 fraction 0.2 0.12 0.12 0.12 0.12 0.05 0 0.05 0.05 0.05 0.01 0.01 0.05 mrem/hr-b 2.15E-02 3.28E-03 2.11E-03 1.07E-04 1.41E-02 2.38E-03 0.00E+00 4.71E-03 3.35E-03 6.72E-03 6.03E-04 2.60E-04 1.01E-03 6.01E-02 Female Tissue Esophagus hyroid Skin T NBS Remainder ED Ovaries RBM Colon Lungs Stomach Bladder Breast Liver mrem/hr-b 1.27E-02 2.73E-02 1.76E-02 8.90E-04 1.17E-01 4.75E-02 2.34E-01 9.42E-02 6.71E-02 1.34E-01 6.03E-02 2.60E-02 2.05E-02 fraction 0.2 0.12 0.12 0.12 0.12 0.05 0.05 0.05 0.05 0.05 0.01 0.01 0.05 mrem/hr-b 2.54E-03 3.28E-03 2.11E-03 1.07E-04 1.41E-02 2.38E-03 1.17E-02 4.71E-03 3.35E-03 6.72E-03 6.03E-04 2.60E-04 1.03E-03 5.28E-02 101 Appendix C: Neutron Radiation Field 102 APPENDIX C.1: ANSI 1977 AT 1 FOOT WITH SOURCE ON LINE S The neutron dose field is determined using ANSI 1977 flux-to-dose conversion factors and a mesh tally that is 1 ft in front of the glove box. Figures C.1-1 thru C.1-11 show the changes in the field as the source is moved from 6 cm from the front inside surface of the box to 150 cm from the inside surface on a line that is 6 cm from the left edge of the box (S). The source is 6 cm above the glove box floor. The outline of the front of glove box is shown in each Figure. 103 Figure C.1-1: Source at 6 cm. Figure C.1-2: Source at 15 cm. Figure C.1-3: Source at 30 cm. 104 Figure C.1-4: Source at 45 cm. Figure C.1-5: Source at 60 cm. 105 Figure C.1-6: Source at 75 cm. Figure C.1-7: Source at 90 cm. 106 Figure C.1-8: Source at 105 cm. Figure C.1-9: Source at 120 cm. 107 Figure C.1-10: Source at 135 cm. Figure C.1-11: Source at 150 cm. 108 APPENDIX C.2: ANSI 1977 AT 1 FOOT WITH SOURCE ON LINE V The neutron dose field is determined using ANSI 1977 flux-to-dose conversion factors and a mesh tally that is 1 ft in front of the glove box. Figures C.2-1 thru C.2-11 show the changes in the field as the source is moved from 6 cm from the front inside surface of the box to 150 cm from the inside surface on a line that corresponds to the middle of the left pair of gloveports (V). The source is 6 cm above the glove box floor. The outline of the front of glove box is shown in each Figure. Figure C.2-1: Source at 6 cm. 109 Figure C.2-2: Source at 15 cm. Figure C.2-3: Source at 30 cm. 110 Figure C.2-4: Source at 45 cm. Figure C.2-5: Source at 60 cm. 111 Figure C.2-6: Source at 75 cm. Figure C.2-7: Source at 90 cm. 112 Figure C.2-8: Source at 105 cm. Figure C.2-9: Source at 120 cm. 113 Figure C.2-10: Source at 135 cm. Figure C.2-11: Source at 150 cm. 114 APPENDIX C.3: ANSI 1977 AT 1 FOOT WITH SOURCE ON LINE M The neutron dose field is determined using ANSI 1977 flux-to-dose conversion factors and a mesh tally that is 1 ft in front of the glove box. Figures C.3-1 thru C.3-11 show the changes in the field as the source is moved from 6 cm from the front inside surface of the box to 150 cm from the inside surface on a line that corresponds to the middle of the glove box (M). The source is 6 cm above the glove box floor. The outline of the front of glove box is shown in each Figure. Figure C.3-1: Source at 6 cm. 115 Figure C.3-2: Source at 15 cm. Figure C.3-3: Source at 30 cm. 116 Figure C.3-4: Source at 45 cm. Figure C.3-5: Source at 60 cm. 117 Figure C.3-6: Source at 75 cm. Figure C.3-7: Source at 90 cm. 118 Figure C.3-8: Source at 105 cm. Figure C.3-9: Source at 120 cm. 119 Figure C.3-10: Source at 135 cm. Figure C.3-11: Source at 150 cm. 120 APPENDIX C.4: ANSI 1977 AT 3 FOOT WITH SOURCE ON LINE S The neutron dose field is determined using ANSI 1977 flux-to-dose conversion factors and a mesh tally that is 3 ft in front of the glove box. Figures C.4-1 thru C.4-11 show the changes in the field as the source is moved from 6 cm from the front inside surface of the box to 150 cm from the inside surface on a line that is 6 cm from the left edge of the box (S). The source is 6 cm above the glove box floor. The outline of the front of glove box is shown in each Figure. Figure C.4-1: Source at 6 cm. 121 Figure C.4-2: Source at 15 cm. Figure C.4-3: Source at 30 cm. 122 Figure C.4-4: Source at 45 cm. Figure C.4-5: Source at 60 cm. 123 Figure C.4-6: Source at 75 cm. Figure C.4-7: Source at 90 cm. 124 Figure C.4-8: Source at 105 cm. Figure C.4-9: Source at 120 cm. 125 Figure C.4-10: Source at 135 cm. Figure C.4-11: Source at 150 cm. 126 APPENDIX C.5: ANSI 1977 AT 3 FOOT WITH SOURCE ON LINE V The neutron dose field is determined using ANSI 1977 flux-to-dose conversion factors and a mesh tally that is 3 ft in front of the glove box. Figures C.2-1 thru C.2-11 show the changes in the field as the source is moved from 6 cm from the front inside surface of the box to 150 cm from the inside surface on a line that corresponds to the middle of the left pair of gloveports (V). The source is 6 cm above the glove box floor. The outline of the front of glove box is shown in each Figure. Figure C.5-1: Source at 6 cm. 127 Figure C.5-2: Source at 15 cm. Figure C.5-3: Source at 30 cm. 128 Figure C.5-4: Source at 45 cm. Figure C.5-5: Source at 60 cm. 129 Figure C.5-6: Source at 75 cm. Figure C.5-7: Source at 90 cm. 130 Figure C.5-8: Source at 105 cm. Figure C.5-9: Source at 120 cm. 131 Figure C.5-10: Source at 135 cm. Figure C.5-11: Source at 150 cm. 132 APPENDIX C.6: ANSI 1977 AT 3 FOOT WITH SOURCE ON LINE M The neutron dose field is determined using ANSI 1977 flux-to-dose conversion factors and a mesh tally that is 3 ft in front of the glove box. Figures C.3-1 thru C.3-11 show the changes in the field as the source is moved from 6 cm from the front inside surface of the box to 150 cm from the inside surface on a line that corresponds to the middle of the glove box (M). The source is 6 cm above the glove box floor. The outline of the front of glove box is shown in each Figure. Figure C.6-1: Source at 6 cm. 133 Figure C.6-2: Source at 15 cm. Figure C.6-3: Source at 30 cm. 134 Figure C.6-4: Source at 45 cm. Figure C.6-5: Source at 60 cm. 135 Figure C.6-6: Source at 75 cm. Figure C.6-7: Source at 90 cm. 136 Figure C.6-8: Source at 105 cm. Figure C.6-9: Source at 120 cm. 137 Figure C.6-10: Source at 135 cm. Figure C.6-11: Source at 150 cm. 138 APPENDIX C.7: ANSI 1977 AT 6 FOOT WITH SOURCE ON LINE S The neutron dose field is determined using ANSI 1977 flux-to-dose conversion factors and a mesh tally that is 6 ft in front of the glove box. Figures C.1-1 thru C.1-11 show the changes in the field as the source is moved from 6 cm from the front inside surface of the box to 150 cm from the inside surface on a line that is 6 cm from the left edge of the box (S). The source is 6 cm above the glove box floor. The outline of the front of glove box is shown in each Figure. 139 Figure C.7-1: Source at 6 cm. Figure C.7-2: Source at 15 cm. Figure C.7-3: Source at 30 cm. 140 Figure C.7-4: Source at 45 cm. Figure C.7-5: Source at 60 cm. 141 Figure C.7-6: Source at 75 cm. Figure C.7-7: Source at 90 cm. 142 Figure C.7-8: Source at 105 cm. Figure C.7-9: Source at 120 cm. 143 Figure C.7-10: Source at 135 cm. Figure C.7-11: Source at 150 cm. 144 APPENDIX C.8: ANSI 1977 AT 6 FOOT WITH SOURCE ON LINE V The neutron dose field is determined using ANSI 1977 flux-to-dose conversion factors and a mesh tally that is 6 ft in front of the glove box. Figures C.2-1 thru C.2-11 show the changes in the field as the source is moved from 6 cm from the front inside surface of the box to 150 cm from the inside surface on a line that corresponds to the middle of the left pair of gloveports (V). The source is 6 cm above the glove box floor. The outline of the front of glove box is shown in each Figure. Figure C.8-1: Source at 6 cm. 145 Figure C.8-2: Source at 15 cm. Figure C.8-3: Source at 30 cm. 146 Figure C.8-4: Source at 45 cm. Figure C.8-5: Source at 60 cm. 147 Figure C.8-6: Source at 75 cm. Figure C.8-7: Source at 90 cm. 148 Figure C.8-8: Source at 105 cm. Figure C.8-9: Source at 120 cm. 149 Figure C.8-10: Source at 135 cm. Figure C.8-11: Source at 150 cm. 150 APPENDIX C.9: ANSI 1977 AT 6 FOOT WITH SOURCE ON LINE M The neutron dose field is determined using ANSI 1977 flux-to-dose conversion factors and a mesh tally that is 6 ft in front of the glove box. Figures C.9-1 thru C.9-11 show the changes in the field as the source is moved from 6 cm from the front inside surface of the box to 150 cm from the inside surface on a line that corresponds to the middle of the glove box (M). The source is 6 cm above the glove box floor. The outline of the front of glove box is shown in each Figure. Figure C.9-1: Source at 6 cm. 151 Figure C.9-2: Source at 15 cm. Figure C.9-3: Source at 30 cm. 152 Figure C.9-4: Source at 45 cm. Figure C.9-5: Source at 60 cm. 153 Figure C.9-6: Source at 75 cm. Figure C.9-7: Source at 90 cm. 154 Figure C.9-8: Source at 105 cm. Figure C.9-9: Source at 120 cm. 155 Figure C.9-10: Source at 135 cm. Figure C.9-11: Source at 150 cm. 156 Appendix D: Summary Of Estimated Doses Using Phantom's Dosimeter Lattice 157 Table D-1: Summary Phantom Dosimeter Tally Plane using ANSI 1977 at 1 Ft Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1M06M1Z 1.51E-01 2.72E-01 4.60E-02 1.55E-01 552 652 412 1M06S1Z 1.61E-02 3.51E-02 8.66E-03 1.15E-02 612 522 692 1M06V1Z 5.94E-02 1.32E-01 2.61E-02 4.74E-02 412 672 692 1M15M1Z 1.11E-01 1.58E-01 4.98E-02 1.17E-01 572 652 412 1M15S1Z 3.60E-02 6.10E-02 1.16E-02 3.89E-02 412 562 692 1M15V1Z 1.08E-01 2.54E-01 3.09E-02 7.29E-02 622 462 692 1M30M1Z 8.53E-02 2.87E-01 4.65E-02 7.54E-02 482 472 412 1M30S1Z 4.66E-02 1.37E-01 1.00E-02 2.28E-02 502 572 692 1M30V1Z 9.10E-02 2.88E-01 3.14E-02 7.57E-02 622 472 692 1M45M1Z 6.86E-02 2.34E-01 3.87E-02 5.03E-02 482 522 412 1M45S1Z 4.24E-02 9.43E-02 1.00E-02 6.54E-02 562 572 692 1M45V1Z 9.08E-02 2.35E-01 2.67E-02 5.15E-02 442 522 692 1M60M1Z 5.57E-02 1.79E-01 2.88E-02 3.87E-02 562 522 712 1M60S1Z 3.00E-02 7.93E-02 9.71E-03 4.86E-02 722 512 692 1M60V1Z 7.53E-02 1.83E-01 2.20E-02 5.40E-02 642 522 702 1M75M1Z 4.56E-02 1.44E-01 2.08E-02 3.06E-02 532 522 702 1M75S1Z 2.38E-02 6.77E-02 9.65E-03 2.85E-02 672 512 642 1M75V1Z 6.13E-02 1.42E-01 1.94E-02 5.72E-02 642 522 702 1M90M1Z 3.68E-02 1.12E-01 1.66E-02 2.40E-02 622 522 702 1M90S1Z 2.00E-02 6.40E-02 8.08E-03 1.80E-02 612 522 692 1M90V1Z 4.95E-02 1.11E-01 1.55E-02 5.27E-02 642 522 702 1M05M1Z 3.08E-02 9.33E-02 1.40E-02 1.99E-02 462 522 702 1M05S1Z 1.77E-02 6.39E-02 7.22E-03 1.28E-02 672 522 692 1M05V1Z 4.20E-02 9.42E-02 1.36E-02 4.82E-02 642 522 702 1M20M1Z 2.63E-02 7.77E-02 1.22E-02 1.64E-02 462 522 702 1M20S1Z 1.56E-02 6.04E-02 6.62E-03 1.02E-02 422 522 692 1M20V1Z 3.46E-02 7.76E-02 1.23E-02 4.30E-02 622 522 712 1M35M1Z 2.34E-02 6.97E-02 1.11E-02 1.44E-02 582 522 692 1M35S1Z 1.40E-02 5.66E-02 5.80E-03 8.29E-03 672 522 592 1M35V1Z 2.97E-02 6.64E-02 1.09E-02 3.92E-02 562 572 702 1M50M1Z 2.21E-02 6.40E-02 9.98E-03 1.33E-02 432 522 702 1M50S1Z 1.36E-02 5.49E-02 5.45E-03 7.37E-03 462 522 492 158 Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1M50V1Z 2.83E-02 6.47E-02 1.03E-02 3.81E-02 402 572 702 1S06M1Z 2.33E-02 4.90E-02 1.24E-02 1.92E-02 592 482 702 1S06S1Z 1.27E-01 2.70E-01 3.11E-02 1.16E-01 642 672 402 1S06V1Z 9.48E-02 1.82E-01 3.94E-02 7.30E-02 542 632 712 1S15M1Z 4.84E-02 1.02E-01 1.51E-02 3.33E-02 472 542 712 1S15S1Z 8.04E-02 1.63E-01 2.57E-02 7.77E-02 512 672 402 1S15V1Z 1.30E-01 3.39E-01 4.15E-02 9.24E-02 632 432 712 1S30M1Z 6.30E-02 1.66E-01 1.59E-02 4.62E-02 562 532 712 1S30S1Z 5.10E-02 2.16E-01 1.90E-02 4.01E-02 512 472 402 1S30V1Z 1.29E-01 3.46E-01 3.54E-02 7.80E-02 502 482 712 1S45M1Z 5.01E-02 1.03E-01 1.21E-02 8.23E-02 462 492 712 1S45S1Z 3.72E-02 1.65E-01 1.39E-02 2.52E-02 462 472 402 1S45V1Z 1.11E-01 2.70E-01 3.13E-02 7.44E-02 462 482 712 1S60M1Z 3.72E-02 1.01E-01 1.29E-02 5.42E-02 452 492 712 1S60S1Z 2.83E-02 1.43E-01 1.14E-02 1.70E-02 462 522 402 1S60V1Z 8.74E-02 2.01E-01 2.50E-02 8.25E-02 442 482 702 1S75M1Z 3.05E-02 8.48E-02 1.27E-02 3.33E-02 632 492 702 1S75S1Z 2.26E-02 1.15E-01 9.26E-03 1.30E-02 662 522 402 1S75V1Z 6.92E-02 1.57E-01 2.06E-02 7.61E-02 532 472 702 1S90M1Z 2.63E-02 8.67E-02 1.09E-02 2.12E-02 502 482 712 1S90S1Z 1.78E-02 9.11E-02 7.42E-03 1.07E-02 612 522 442 1S90V1Z 5.49E-02 1.21E-01 1.71E-02 6.63E-02 472 482 692 1S05M1Z 2.30E-02 8.28E-02 9.88E-03 1.51E-02 632 482 702 1S05S1Z 1.50E-02 7.38E-02 6.77E-03 8.40E-03 612 522 492 1S05V1Z 4.34E-02 9.74E-02 1.44E-02 5.78E-02 652 482 692 1S20M1Z 2.02E-02 7.31E-02 8.47E-03 1.25E-02 632 482 712 1S20S1Z 1.26E-02 6.20E-02 5.07E-03 6.74E-03 662 522 402 1S20V1Z 3.54E-02 8.10E-02 1.20E-02 4.97E-02 672 482 702 1S35M1Z 1.76E-02 6.51E-02 8.46E-03 1.15E-02 442 482 712 1S35S1Z 1.10E-02 5.17E-02 4.51E-03 5.76E-03 512 522 442 1S35V1Z 3.00E-02 6.93E-02 1.06E-02 4.23E-02 582 482 702 1S50M1Z 1.67E-02 6.28E-02 8.18E-03 1.03E-02 632 482 702 1S50S1Z 1.02E-02 4.85E-02 4.61E-03 5.73E-03 662 522 492 1S50V1Z 2.81E-02 6.64E-02 1.03E-02 3.95E-02 422 482 702 159 Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1V06M1Z 7.60E-02 2.70E-01 2.75E-02 4.52E-02 542 582 712 1V06S1Z 7.39E-02 2.65E-01 2.44E-02 4.20E-02 562 622 692 1V06V1Z 5.63E-01 9.30E-01 1.96E-01 7.56E-01 492 602 722 1V15M1Z 9.61E-02 2.29E-01 2.88E-02 5.72E-02 632 442 712 1V15S1Z 9.15E-02 2.25E-01 2.43E-02 5.39E-02 672 462 692 1V15V1Z 3.76E-01 5.76E-01 1.32E-01 5.15E-01 522 602 722 1V30M1Z 7.80E-02 2.74E-01 2.66E-02 5.81E-02 582 432 712 1V30S1Z 7.20E-02 2.72E-01 2.24E-02 5.00E-02 622 472 692 1V30V1Z 1.81E-01 3.18E-01 6.99E-02 3.05E-01 462 602 712 1V45M1Z 6.09E-02 2.27E-01 2.26E-02 3.70E-02 582 482 712 1V45S1Z 5.38E-02 2.23E-01 1.83E-02 2.83E-02 622 522 692 1V45V1Z 1.13E-01 2.00E-01 4.42E-02 1.97E-01 432 602 692 1V60M1Z 4.77E-02 1.77E-01 2.05E-02 3.03E-02 582 482 712 1V60S1Z 4.01E-02 1.74E-01 1.40E-02 2.16E-02 672 522 692 1V60V1Z 8.20E-02 1.39E-01 3.10E-02 1.39E-01 452 552 702 1V75M1Z 3.83E-02 1.40E-01 1.69E-02 2.51E-02 632 482 702 1V75S1Z 3.08E-02 1.34E-01 1.15E-02 1.68E-02 672 522 692 1V75V1Z 6.30E-02 1.07E-01 2.37E-02 1.02E-01 642 522 702 1V90M1Z 3.10E-02 1.12E-01 1.47E-02 2.05E-02 632 482 712 1V90S1Z 2.39E-02 1.06E-01 8.48E-03 1.32E-02 462 522 402 1V90V1Z 4.97E-02 9.27E-02 1.82E-02 7.72E-02 662 522 702 1V05M1Z 2.64E-02 9.20E-02 1.27E-02 1.71E-02 572 482 702 1V05S1Z 1.96E-02 8.92E-02 7.31E-03 1.15E-02 722 522 492 1V05V1Z 4.10E-02 7.71E-02 1.51E-02 6.15E-02 662 482 702 1V20M1Z 2.33E-02 7.73E-02 1.16E-02 1.44E-02 632 482 692 1V20S1Z 1.61E-02 7.29E-02 6.24E-03 9.03E-03 722 522 402 1V20V1Z 3.48E-02 6.60E-02 1.29E-02 5.11E-02 662 522 692 1V35M1Z 2.07E-02 6.73E-02 9.85E-03 1.24E-02 632 482 712 1V35S1Z 1.38E-02 6.40E-02 5.13E-03 8.01E-03 722 522 402 1V35V1Z 3.01E-02 5.71E-02 1.13E-02 4.37E-02 412 522 702 1V50M1Z 1.93E-02 6.21E-02 8.64E-03 1.15E-02 542 482 702 1V50S1Z 1.27E-02 5.91E-02 5.02E-03 7.28E-03 722 522 402 1V50V1Z 2.78E-02 5.35E-02 1.03E-02 4.07E-02 432 482 702 160 Table D-2: Summary Phantom Dosimeter Tally Plane using ANSI 1991 at 1 Ft Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1M06M1A 7.93E-02 1.44E-01 2.27E-02 8.16E-02 152 252 12 1M06S1A 7.70E-03 1.69E-02 4.01E-03 5.50E-03 212 122 192 1M06V1A 2.97E-02 6.97E-02 1.24E-02 2.24E-02 112 272 292 1M15M1A 5.79E-02 8.35E-02 2.48E-02 6.13E-02 322 252 12 1M15S1A 1.85E-02 3.28E-02 4.80E-03 2.01E-02 222 162 292 1M15V1A 5.67E-02 1.37E-01 1.45E-02 3.75E-02 272 62 292 1M30M1A 4.43E-02 1.55E-01 2.34E-02 3.91E-02 192 72 12 1M30S1A 2.42E-02 7.37E-02 4.71E-03 1.18E-02 102 172 292 1M30V1A 4.70E-02 1.53E-01 1.39E-02 3.86E-02 222 72 292 1M45M1A 3.55E-02 1.25E-01 1.97E-02 2.59E-02 82 122 12 1M45S1A 2.19E-02 4.98E-02 4.33E-03 3.55E-02 162 122 292 1M45V1A 4.73E-02 1.24E-01 1.19E-02 2.55E-02 42 122 292 1M60M1A 2.87E-02 9.48E-02 1.45E-02 1.97E-02 162 122 312 1M60S1A 1.51E-02 4.21E-02 4.32E-03 2.53E-02 82 112 302 1M60V1A 3.90E-02 9.61E-02 1.04E-02 2.78E-02 242 122 292 1M75M1A 2.34E-02 7.60E-02 1.05E-02 1.54E-02 132 122 302 1M75S1A 1.16E-02 3.58E-02 3.80E-03 1.49E-02 272 112 292 1M75V1A 3.14E-02 7.48E-02 8.46E-03 2.89E-02 242 122 292 1M90M1A 1.88E-02 5.88E-02 8.16E-03 1.19E-02 222 122 302 1M90S1A 9.77E-03 3.30E-02 3.41E-03 9.24E-03 212 122 292 1M90V1A 2.53E-02 5.77E-02 7.05E-03 2.73E-02 32 122 292 1M05M1A 1.57E-02 4.88E-02 6.85E-03 9.78E-03 222 122 302 1M05S1A 8.62E-03 3.32E-02 2.87E-03 5.88E-03 22 122 292 1M05V1A 2.12E-02 4.85E-02 5.97E-03 2.48E-02 242 122 302 1M20M1A 1.33E-02 4.07E-02 5.85E-03 8.16E-03 62 122 302 1M20S1A 7.57E-03 3.14E-02 2.87E-03 4.45E-03 22 122 292 1M20V1A 1.75E-02 4.05E-02 5.36E-03 2.23E-02 162 122 292 1M35M1A 1.18E-02 3.60E-02 5.36E-03 7.06E-03 182 122 292 1M35S1A 6.72E-03 2.95E-02 2.45E-03 4.07E-03 22 122 292 1M35V1A 1.48E-02 3.43E-02 4.82E-03 2.04E-02 22 122 302 1M50M1A 1.07E-02 3.25E-02 4.49E-03 6.74E-03 32 122 292 1M50S1A 6.36E-03 2.80E-02 2.29E-03 3.36E-03 22 122 292 161 Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1M50V1A 1.40E-02 3.32E-02 4.20E-03 1.96E-02 2 122 302 1S06M1A 1.12E-02 2.36E-02 5.66E-03 9.48E-03 192 82 302 1S06S1A 6.68E-02 1.42E-01 1.57E-02 6.16E-02 242 272 2 1S06V1A 4.83E-02 9.70E-02 1.82E-02 3.56E-02 142 12 312 1S15M1A 2.51E-02 5.56E-02 7.15E-03 1.66E-02 72 142 312 1S15S1A 4.17E-02 8.53E-02 1.22E-02 4.07E-02 112 272 2 1S15V1A 6.75E-02 1.83E-01 2.00E-02 4.50E-02 182 32 312 1S30M1A 3.28E-02 8.84E-02 7.26E-03 2.41E-02 162 132 312 1S30S1A 2.59E-02 1.16E-01 8.95E-03 2.02E-02 62 72 2 1S30V1A 6.71E-02 1.84E-01 1.90E-02 3.76E-02 102 82 312 1S45M1A 2.56E-02 5.41E-02 5.56E-03 4.35E-02 62 92 312 1S45S1A 1.85E-02 8.76E-02 6.33E-03 1.21E-02 62 72 2 1S45V1A 5.70E-02 1.41E-01 1.49E-02 3.78E-02 62 82 312 1S60M1A 1.87E-02 5.25E-02 5.95E-03 2.81E-02 52 92 312 1S60S1A 1.38E-02 7.57E-02 4.76E-03 8.26E-03 62 122 2 1S60V1A 4.50E-02 1.05E-01 1.15E-02 4.27E-02 42 82 312 1S75M1A 1.53E-02 4.41E-02 6.12E-03 1.68E-02 182 92 302 1S75S1A 1.09E-02 6.13E-02 3.99E-03 6.09E-03 212 122 292 1S75V1A 3.53E-02 8.15E-02 9.34E-03 3.97E-02 142 82 302 1S90M1A 1.31E-02 4.49E-02 5.10E-03 1.04E-02 102 82 312 1S90S1A 8.43E-03 4.80E-02 3.16E-03 4.68E-03 112 122 292 1S90V1A 2.80E-02 6.27E-02 7.47E-03 3.45E-02 72 82 302 1S05M1A 1.15E-02 4.29E-02 4.53E-03 7.33E-03 232 82 302 1S05S1A 6.92E-03 3.83E-02 2.69E-03 3.67E-03 112 122 42 1S05V1A 2.19E-02 5.03E-02 6.13E-03 3.01E-02 252 82 302 1S20M1A 1.01E-02 3.80E-02 3.92E-03 6.13E-03 232 82 312 1S20S1A 5.85E-03 3.22E-02 2.25E-03 3.12E-03 112 122 92 1S20V1A 1.78E-02 4.22E-02 5.48E-03 2.56E-02 272 82 292 1S35M1A 8.79E-03 3.35E-02 4.05E-03 5.57E-03 42 82 302 1S35S1A 5.03E-03 2.70E-02 2.03E-03 2.64E-03 162 122 192 1S35V1A 1.50E-02 3.60E-02 4.67E-03 2.19E-02 92 82 302 1S50M1A 8.00E-03 3.17E-02 3.54E-03 4.80E-03 232 82 312 1S50S1A 4.72E-03 2.51E-02 1.79E-03 2.27E-03 62 122 42 1S50V1A 1.39E-02 3.44E-02 4.15E-03 2.03E-02 122 132 302 162 Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1V06M1A 3.92E-02 1.46E-01 1.32E-02 2.25E-02 192 182 312 1V06S1A 3.83E-02 1.43E-01 1.18E-02 2.05E-02 212 222 292 1V06V1A 3.05E-01 5.05E-01 9.89E-02 4.08E-01 102 202 322 1V15M1A 5.05E-02 1.24E-01 1.40E-02 2.98E-02 232 42 312 1V15S1A 4.81E-02 1.22E-01 1.21E-02 2.76E-02 272 62 292 1V15V1A 2.02E-01 3.11E-01 6.79E-02 2.76E-01 122 202 282 1V30M1A 4.05E-02 1.46E-01 1.31E-02 2.98E-02 182 32 312 1V30S1A 3.71E-02 1.44E-01 1.03E-02 2.61E-02 222 72 292 1V30V1A 9.51E-02 1.71E-01 3.61E-02 1.62E-01 182 202 292 1V45M1A 3.13E-02 1.20E-01 1.12E-02 1.84E-02 182 82 312 1V45S1A 2.76E-02 1.18E-01 8.72E-03 1.46E-02 222 122 292 1V45V1A 5.86E-02 1.06E-01 2.21E-02 1.05E-01 72 202 312 1V60M1A 2.44E-02 9.33E-02 9.83E-03 1.50E-02 182 82 312 1V60S1A 2.03E-02 9.13E-02 6.43E-03 1.05E-02 222 122 292 1V60V1A 4.21E-02 7.35E-02 1.51E-02 7.31E-02 52 202 302 1V75M1A 1.94E-02 7.34E-02 8.20E-03 1.24E-02 232 82 302 1V75S1A 1.54E-02 7.09E-02 4.89E-03 8.29E-03 272 122 292 1V75V1A 3.22E-02 5.53E-02 1.09E-02 5.36E-02 172 122 302 1V90M1A 1.57E-02 5.86E-02 7.07E-03 1.03E-02 42 82 312 1V90S1A 1.18E-02 5.56E-02 3.70E-03 6.50E-03 272 122 292 1V90V1A 2.51E-02 4.79E-02 8.20E-03 4.03E-02 242 122 302 1V05M1A 1.33E-02 4.80E-02 6.05E-03 8.41E-03 172 82 302 1V05S1A 9.48E-03 4.64E-02 3.23E-03 5.28E-03 272 122 292 1V05V1A 2.07E-02 3.96E-02 7.02E-03 3.24E-02 262 82 292 1V20M1A 1.18E-02 4.02E-02 5.52E-03 7.13E-03 72 82 312 1V20S1A 7.78E-03 3.77E-02 2.40E-03 4.27E-03 322 122 242 1V20V1A 1.74E-02 3.43E-02 5.73E-03 2.66E-02 12 122 302 1V35M1A 1.04E-02 3.49E-02 4.64E-03 6.11E-03 232 82 312 1V35S1A 6.53E-03 3.33E-02 2.27E-03 3.64E-03 322 122 2 1V35V1A 1.50E-02 2.93E-02 5.13E-03 2.25E-02 2 122 302 1V50M1A 9.45E-03 3.18E-02 3.70E-03 5.47E-03 142 82 302 1V50S1A 5.94E-03 3.03E-02 2.13E-03 3.35E-03 322 122 292 1V50V1A 1.38E-02 2.73E-02 4.66E-03 2.09E-02 32 82 302 163 Table D-3: Summary Phantom Dosimeter Tally Plane using ICRP-74 at 1 Ft Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1M06M1Z 1.47E-01 2.65E-01 4.33E-02 1.50E-01 952 1052 812 1M06S1Z 1.49E-02 3.26E-02 8.03E-03 1.07E-02 1012 922 1092 1M06V1Z 5.66E-02 1.29E-01 2.45E-02 4.43E-02 862 1072 1092 1M15M1Z 1.08E-01 1.54E-01 4.70E-02 1.13E-01 1122 1052 812 1M15S1Z 3.47E-02 5.98E-02 1.07E-02 3.79E-02 812 962 1092 1M15V1Z 1.05E-01 2.47E-01 2.89E-02 7.00E-02 1072 862 1092 1M30M1Z 8.21E-02 2.79E-01 4.41E-02 7.28E-02 992 872 812 1M30S1Z 4.51E-02 1.34E-01 9.23E-03 2.20E-02 902 972 1092 1M30V1Z 8.74E-02 2.78E-01 2.96E-02 7.23E-02 1022 872 1092 1M45M1Z 6.58E-02 2.26E-01 3.69E-02 4.84E-02 882 922 812 1M45S1Z 4.09E-02 9.13E-02 9.12E-03 6.39E-02 962 972 1092 1M45V1Z 8.75E-02 2.26E-01 2.51E-02 4.85E-02 842 922 1092 1M60M1Z 5.33E-02 1.73E-01 2.75E-02 3.70E-02 962 922 1112 1M60S1Z 2.87E-02 7.66E-02 9.01E-03 4.70E-02 1122 912 1092 1M60V1Z 7.24E-02 1.76E-01 2.04E-02 5.18E-02 1042 922 1092 1M75M1Z 4.36E-02 1.39E-01 1.99E-02 2.91E-02 932 922 1102 1M75S1Z 2.26E-02 6.54E-02 9.11E-03 2.75E-02 1072 912 1102 1M75V1Z 5.87E-02 1.36E-01 1.81E-02 5.48E-02 1042 922 1102 1M90M1Z 3.51E-02 1.08E-01 1.56E-02 2.27E-02 1022 922 1102 1M90S1Z 1.90E-02 6.14E-02 7.54E-03 1.72E-02 1012 922 1092 1M90V1Z 4.74E-02 1.07E-01 1.44E-02 5.07E-02 832 922 1102 1M05M1Z 2.93E-02 8.94E-02 1.32E-02 1.87E-02 862 922 1102 1M05S1Z 1.68E-02 6.12E-02 6.60E-03 1.21E-02 1072 922 1092 1M05V1Z 4.02E-02 9.05E-02 1.27E-02 4.63E-02 1042 922 1102 1M20M1Z 2.50E-02 7.46E-02 1.14E-02 1.56E-02 862 922 1102 1M20S1Z 1.48E-02 5.78E-02 6.06E-03 9.57E-03 822 922 1092 1M20V1Z 3.30E-02 7.46E-02 1.13E-02 4.14E-02 962 922 1102 1M35M1Z 2.22E-02 6.65E-02 1.04E-02 1.36E-02 982 922 1092 1M35S1Z 1.32E-02 5.43E-02 5.41E-03 7.83E-03 1072 922 992 1M35V1Z 2.83E-02 6.36E-02 1.00E-02 3.77E-02 962 972 1102 1M50M1Z 2.09E-02 6.10E-02 9.27E-03 1.25E-02 832 922 1102 1M50S1Z 1.28E-02 5.24E-02 5.06E-03 6.96E-03 862 922 892 164 1M50V1Z 1S06M1Z 1S06S1Z 1S06V1Z 1S15M1Z 1S15S1Z 1S15V1Z 1S30M1Z 1S30S1Z 1S30V1Z 1S45M1Z 1S45S1Z 1S45V1Z 1S60M1Z 1S60S1Z 1S60V1Z 1S75M1Z 1S75S1Z 1S75V1Z 1S90M1Z 1S90S1Z 1S90V1Z 1S05M1Z 1S05S1Z 1S05V1Z 1S20M1Z 1S20S1Z 1S20V1Z 1S35M1Z 1S35S1Z 1S35V1Z 1S50M1Z 1S50S1Z 1S50V1Z 1V06M1Z 1V06S1Z 1V06V1Z 2.68E-02 2.17E-02 1.23E-01 9.08E-02 4.64E-02 7.78E-02 1.25E-01 6.04E-02 4.90E-02 1.24E-01 4.78E-02 3.56E-02 1.06E-01 3.53E-02 2.69E-02 8.37E-02 2.89E-02 2.14E-02 6.62E-02 2.48E-02 1.68E-02 5.26E-02 2.17E-02 1.41E-02 4.14E-02 1.91E-02 1.19E-02 3.38E-02 1.67E-02 1.03E-02 2.85E-02 1.57E-02 9.60E-03 2.67E-02 7.28E-02 7.08E-02 5.50E-01 6.16E-02 4.57E-02 2.62E-01 1.77E-01 1.00E-01 1.58E-01 3.29E-01 1.61E-01 2.09E-01 3.34E-01 9.88E-02 1.60E-01 2.59E-01 9.63E-02 1.37E-01 1.93E-01 8.11E-02 1.11E-01 1.50E-01 8.28E-02 8.78E-02 1.16E-01 7.91E-02 7.10E-02 9.33E-02 7.01E-02 5.96E-02 7.77E-02 6.20E-02 4.98E-02 6.62E-02 5.96E-02 4.65E-02 6.39E-02 2.63E-01 2.59E-01 9.09E-01 9.52E-03 1.13E-02 2.96E-02 3.72E-02 1.41E-02 2.42E-02 3.93E-02 1.44E-02 1.75E-02 3.38E-02 1.12E-02 1.28E-02 2.96E-02 1.18E-02 1.05E-02 2.35E-02 1.19E-02 8.42E-03 1.93E-02 1.01E-02 6.81E-03 1.61E-02 9.06E-03 6.04E-03 1.36E-02 7.84E-03 4.66E-03 1.11E-02 7.92E-03 4.11E-03 9.75E-03 7.58E-03 4.20E-03 9.50E-03 2.55E-02 2.27E-02 1.87E-01 165 3.64E-02 1.81E-02 1.13E-01 6.84E-02 3.15E-02 7.58E-02 8.66E-02 4.44E-02 3.86E-02 7.27E-02 7.94E-02 2.39E-02 7.07E-02 5.20E-02 1.60E-02 7.93E-02 3.17E-02 1.22E-02 7.31E-02 1.99E-02 9.92E-03 6.38E-02 1.41E-02 7.86E-03 5.58E-02 1.18E-02 6.31E-03 4.78E-02 1.08E-02 5.27E-03 4.06E-02 9.71E-03 5.32E-03 3.79E-02 4.27E-02 3.93E-02 7.36E-01 802 992 1042 942 872 952 932 962 912 902 862 862 862 852 862 842 1032 1012 932 902 1012 872 1032 1012 1052 1032 1062 1072 842 912 982 1032 1062 822 992 1012 902 922 882 1072 1032 942 1072 832 932 872 882 892 872 882 892 922 882 892 922 872 882 922 882 882 922 882 882 922 882 882 922 882 882 922 932 982 1022 1002 1102 1102 802 1112 1112 802 1112 1112 802 1112 1112 802 1112 1112 802 1102 1102 802 1102 1112 842 1092 1102 892 1102 1112 802 1102 1112 842 1102 1102 892 1102 1112 1092 1122 1V15M1Z 1V15S1Z 1V15V1Z 1V30M1Z 1V30S1Z 1V30V1Z 1V45M1Z 1V45S1Z 1V45V1Z 1V60M1Z 1V60S1Z 1V60V1Z 1V75M1Z 1V75S1Z 1V75V1Z 1V90M1Z 1V90S1Z 1V90V1Z 1V05M1Z 1V05S1Z 1V05V1Z 1V20M1Z 1V20S1Z 1V20V1Z 1V35M1Z 1V35S1Z 1V35V1Z 1V50M1Z 1V50S1Z 1V50V1Z 9.25E-02 8.84E-02 3.66E-01 7.48E-02 6.92E-02 1.75E-01 5.81E-02 5.16E-02 1.08E-01 4.55E-02 3.84E-02 7.86E-02 3.64E-02 2.94E-02 6.03E-02 2.94E-02 2.27E-02 4.75E-02 2.50E-02 1.86E-02 3.91E-02 2.21E-02 1.52E-02 3.31E-02 1.96E-02 1.30E-02 2.86E-02 1.83E-02 1.19E-02 2.64E-02 2.22E-01 2.19E-01 5.61E-01 2.65E-01 2.63E-01 3.08E-01 2.19E-01 2.15E-01 1.94E-01 1.70E-01 1.67E-01 1.35E-01 1.34E-01 1.30E-01 1.03E-01 1.07E-01 1.02E-01 8.87E-02 8.81E-02 8.60E-02 7.38E-02 7.39E-02 7.00E-02 6.32E-02 6.44E-02 6.15E-02 5.46E-02 5.93E-02 5.65E-02 5.11E-02 2.69E-02 2.29E-02 1.27E-01 2.51E-02 2.11E-02 6.72E-02 2.14E-02 1.75E-02 4.21E-02 1.90E-02 1.32E-02 2.93E-02 1.58E-02 1.08E-02 2.22E-02 1.38E-02 7.95E-03 1.70E-02 1.18E-02 6.80E-03 1.41E-02 1.08E-02 5.84E-03 1.20E-02 9.11E-03 4.73E-03 1.06E-02 8.06E-03 4.61E-03 9.62E-03 5.51E-02 5.23E-02 5.00E-01 5.56E-02 4.81E-02 2.95E-01 3.51E-02 2.71E-02 1.91E-01 2.87E-02 2.06E-02 1.34E-01 2.37E-02 1.60E-02 9.87E-02 1.96E-02 1.26E-02 7.45E-02 1.61E-02 1.09E-02 5.94E-02 1.37E-02 8.56E-03 4.93E-02 1.17E-02 7.59E-03 4.19E-02 1.09E-02 6.89E-03 3.91E-02 1032 1072 922 982 1022 862 982 1022 872 982 1072 852 1032 1072 972 1032 862 1042 972 1122 1062 872 1122 1062 1032 1122 812 942 1122 832 842 862 1002 832 872 1002 882 922 1002 882 922 1002 882 922 922 882 922 922 882 922 882 882 922 922 882 922 922 882 922 882 1112 1092 1122 1112 1092 1112 1112 1092 1092 1112 1092 1102 1102 1092 1102 1112 802 1102 1102 892 1102 1092 802 1092 1112 802 1102 1102 802 1102 166 Table D-4: Summary Phantom Dosimeter Tally Plane using ANSI 1977 at 3 Ft Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1M06M3Z 3.40E-02 4.41E-02 2.53E-02 3.06E-02 662 582 412 1M06S3Z 1.51E-02 2.42E-02 1.05E-02 1.27E-02 662 622 402 1M06V3Z 2.71E-02 3.98E-02 1.85E-02 2.30E-02 662 672 402 1M15M3Z 2.84E-02 3.69E-02 2.15E-02 2.65E-02 642 572 412 1M15S3Z 1.49E-02 2.32E-02 1.12E-02 1.26E-02 532 572 402 1M15V3Z 2.36E-02 3.47E-02 1.73E-02 2.00E-02 612 722 402 1M30M3Z 2.22E-02 2.81E-02 1.86E-02 1.95E-02 562 522 402 1M30S3Z 1.58E-02 4.45E-02 9.47E-03 1.18E-02 582 422 692 1M30V3Z 2.08E-02 4.20E-02 1.56E-02 1.67E-02 532 402 692 1M45M3Z 1.87E-02 2.43E-02 1.50E-02 1.63E-02 512 572 702 1M45S3Z 2.17E-02 4.36E-02 9.49E-03 1.53E-02 522 432 702 1M45V3Z 2.47E-02 6.39E-02 1.37E-02 1.48E-02 622 432 702 1M60M3Z 1.62E-02 2.10E-02 1.28E-02 1.40E-02 512 472 702 1M60S3Z 2.52E-02 4.04E-02 8.51E-03 3.04E-02 612 432 692 1M60V3Z 2.46E-02 5.58E-02 1.12E-02 1.37E-02 572 432 702 1M75M3Z 1.49E-02 3.55E-02 1.08E-02 1.20E-02 462 472 702 1M75S3Z 2.21E-02 3.03E-02 8.18E-03 2.66E-02 672 512 702 1M75V3Z 2.27E-02 4.89E-02 9.63E-03 1.81E-02 482 472 702 1M90M3Z 1.36E-02 4.26E-02 9.28E-03 1.03E-02 672 472 702 1M90S3Z 1.84E-02 3.80E-02 7.47E-03 1.88E-02 552 572 702 1M90V3Z 1.99E-02 4.69E-02 8.39E-03 1.81E-02 562 472 692 1M05M3Z 1.28E-02 4.10E-02 8.58E-03 9.73E-03 622 472 702 1M05S3Z 1.67E-02 3.39E-02 6.58E-03 9.31E-03 492 522 692 1M05V3Z 1.77E-02 4.26E-02 7.76E-03 1.59E-02 402 472 692 1M20M3Z 1.18E-02 3.80E-02 7.90E-03 9.04E-03 622 472 692 1M20S3Z 1.55E-02 3.16E-02 5.50E-03 7.74E-03 562 432 702 1M20V3Z 1.72E-02 3.77E-02 6.86E-03 1.43E-02 442 472 702 1M35M3Z 1.13E-02 3.46E-02 6.87E-03 8.39E-03 632 472 702 1M35S3Z 1.44E-02 2.94E-02 4.98E-03 9.02E-03 542 482 702 1M35V3Z 1.66E-02 3.54E-02 6.50E-03 1.27E-02 412 522 702 1M50M3Z 1.09E-02 3.41E-02 6.53E-03 8.19E-03 622 472 702 167 Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1M50S3Z 1.41E-02 2.82E-02 4.50E-03 1.05E-02 412 482 702 1M50V3Z 1.64E-02 3.52E-02 6.27E-03 1.24E-02 502 522 702 1S06M3Z 1.76E-02 2.67E-02 1.35E-02 1.46E-02 492 682 412 1S06S3Z 2.97E-02 4.05E-02 2.08E-02 2.61E-02 432 622 412 1S06V3Z 2.76E-02 3.87E-02 2.08E-02 2.55E-02 542 582 412 1S15M3Z 1.72E-02 2.55E-02 1.27E-02 1.46E-02 492 482 712 1S15S3Z 2.26E-02 3.11E-02 1.55E-02 1.96E-02 712 522 402 1S15V3Z 2.34E-02 3.03E-02 1.84E-02 1.98E-02 542 682 412 1S30M3Z 1.86E-02 2.87E-02 1.24E-02 1.49E-02 442 522 712 1S30S3Z 1.64E-02 2.35E-02 1.25E-02 1.46E-02 482 622 412 1S30V3Z 2.48E-02 6.05E-02 1.60E-02 1.77E-02 482 422 712 1S45M3Z 3.14E-02 5.31E-02 1.17E-02 3.71E-02 652 522 712 1S45S3Z 1.31E-02 1.94E-02 1.02E-02 1.17E-02 632 622 492 1S45V3Z 2.72E-02 5.92E-02 1.29E-02 1.57E-02 492 472 702 1S60M3Z 3.25E-02 4.41E-02 1.11E-02 3.65E-02 672 572 712 1S60S3Z 1.09E-02 1.70E-02 7.97E-03 9.83E-03 512 472 442 1S60V3Z 2.56E-02 6.12E-02 1.06E-02 1.55E-02 522 432 702 1S75M3Z 2.47E-02 4.73E-02 9.40E-03 2.98E-02 652 432 702 1S75S3Z 9.92E-03 2.68E-02 6.76E-03 8.71E-03 462 472 402 1S75V3Z 2.28E-02 5.61E-02 9.62E-03 1.62E-02 472 432 702 1S90M3Z 2.14E-02 4.31E-02 8.83E-03 1.36E-02 642 432 712 1S90S3Z 8.84E-03 3.12E-02 5.89E-03 8.13E-03 562 472 492 1S90V3Z 2.13E-02 4.77E-02 8.42E-03 1.40E-02 542 432 702 1S05M3Z 1.95E-02 3.99E-02 7.31E-03 9.81E-03 592 482 702 1S05S3Z 8.26E-03 2.96E-02 5.17E-03 6.27E-03 422 472 442 1S05V3Z 2.00E-02 4.23E-02 7.84E-03 1.23E-02 542 482 712 1S20M3Z 1.76E-02 3.48E-02 6.70E-03 9.85E-03 562 482 702 1S20S3Z 7.54E-03 2.68E-02 4.78E-03 5.80E-03 532 472 492 1S20V3Z 1.85E-02 4.01E-02 6.92E-03 1.12E-02 542 482 702 1S35M3Z 1.60E-02 3.21E-02 6.03E-03 1.43E-02 552 522 702 1S35S3Z 6.97E-03 2.60E-02 4.09E-03 5.22E-03 512 472 402 1S35V3Z 1.71E-02 3.54E-02 6.08E-03 1.03E-02 452 432 702 1S50M3Z 1.53E-02 3.13E-02 5.47E-03 1.60E-02 442 472 702 1S50S3Z 6.57E-03 2.51E-02 3.91E-03 4.85E-03 722 472 642 168 Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1S50V3Z 1.65E-02 3.38E-02 5.41E-03 8.86E-03 612 432 702 1V06M3Z 8.03E-02 1.24E-01 3.14E-02 7.67E-02 442 582 702 1V06S3Z 7.87E-02 1.21E-01 3.02E-02 7.57E-02 462 622 692 1V06V3Z 9.86E-02 1.31E-01 4.17E-02 9.79E-02 492 582 702 1V15M3Z 4.27E-02 1.05E-01 1.94E-02 2.60E-02 682 582 422 1V15S3Z 4.06E-02 1.02E-01 1.79E-02 2.49E-02 722 622 442 1V15V3Z 8.08E-02 1.10E-01 2.56E-02 8.11E-02 642 622 692 1V30M3Z 2.40E-02 5.11E-02 1.53E-02 1.75E-02 622 482 662 1V30S3Z 2.15E-02 4.92E-02 1.39E-02 1.49E-02 722 522 692 1V30V3Z 6.34E-02 8.89E-02 1.89E-02 6.30E-02 422 572 702 1V45M3Z 2.45E-02 6.28E-02 1.31E-02 1.52E-02 482 472 702 1V45S3Z 2.18E-02 5.59E-02 1.17E-02 1.24E-02 522 432 702 1V45V3Z 5.13E-02 7.24E-02 1.51E-02 5.19E-02 422 522 702 1V60M3Z 2.49E-02 5.66E-02 1.21E-02 1.33E-02 482 472 652 1V60S3Z 2.20E-02 5.15E-02 9.39E-03 1.14E-02 572 432 702 1V60V3Z 4.10E-02 5.57E-02 1.28E-02 4.36E-02 602 572 702 1V75M3Z 2.31E-02 4.73E-02 9.86E-03 1.83E-02 522 472 702 1V75S3Z 2.04E-02 4.36E-02 8.37E-03 1.66E-02 482 432 642 1V75V3Z 3.21E-02 3.94E-02 1.10E-02 3.72E-02 582 512 702 1V90M3Z 2.02E-02 4.68E-02 9.35E-03 1.78E-02 542 432 702 1V90S3Z 1.78E-02 4.50E-02 7.48E-03 1.61E-02 562 472 702 1V90V3Z 2.60E-02 3.29E-02 1.02E-02 3.14E-02 662 422 702 1V05M3Z 1.75E-02 4.22E-02 8.33E-03 1.60E-02 512 432 712 1V05S3Z 1.52E-02 3.90E-02 6.57E-03 1.38E-02 492 472 702 1V05V3Z 2.19E-02 2.89E-02 8.93E-03 2.70E-02 522 512 702 1V20M3Z 1.54E-02 3.95E-02 7.28E-03 1.31E-02 462 432 702 1V20S3Z 1.32E-02 3.51E-02 5.78E-03 1.18E-02 442 472 702 1V20V3Z 1.88E-02 2.54E-02 8.03E-03 2.38E-02 642 462 702 1V35M3Z 1.36E-02 3.53E-02 6.16E-03 1.10E-02 412 482 702 1V35S3Z 1.16E-02 3.26E-02 5.26E-03 9.93E-03 412 472 702 1V35V3Z 1.66E-02 2.29E-02 6.57E-03 2.16E-02 642 512 702 1V50M3Z 1.26E-02 3.41E-02 5.83E-03 1.01E-02 412 482 712 1V50S3Z 1.09E-02 3.17E-02 4.69E-03 8.72E-03 622 472 702 1V50V3Z 1.55E-02 2.15E-02 6.48E-03 2.04E-02 652 512 692 169 Table H-5: Summary Phantom Dosimeter Tally Plane using ANSI 1991 at 3 Ft Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Max Min Ave 1M06M3A 1.74E-02 2.29E-02 1.28E-02 1.58E-02 262 182 12 1M06S3A 6.98E-03 1.15E-02 4.99E-03 5.75E-03 162 222 142 1M06V3A 1.32E-02 2.01E-02 9.10E-03 1.12E-02 312 222 2 1M15M3A 1.38E-02 1.77E-02 1.07E-02 1.27E-02 242 82 12 1M15S3A 7.24E-03 1.13E-02 5.45E-03 6.10E-03 282 222 2 1M15V3A 1.18E-02 1.73E-02 8.81E-03 1.00E-02 162 322 2 1M30M3A 1.06E-02 1.36E-02 8.70E-03 9.68E-03 162 122 12 1M30S3A 7.82E-03 2.40E-02 4.60E-03 5.74E-03 182 22 292 1M30V3A 1.04E-02 2.27E-02 7.65E-03 8.19E-03 82 2 292 1M45M3A 8.73E-03 1.16E-02 7.02E-03 7.59E-03 92 172 302 1M45S3A 1.13E-02 2.35E-02 4.56E-03 7.76E-03 122 32 302 1M45V3A 1.26E-02 3.44E-02 6.70E-03 7.18E-03 222 32 302 1M60M3A 7.46E-03 9.93E-03 5.50E-03 6.57E-03 142 72 302 1M60S3A 1.32E-02 2.16E-02 4.07E-03 1.62E-02 252 32 292 1M60V3A 1.26E-02 2.94E-02 5.45E-03 6.67E-03 172 32 302 1M75M3A 6.76E-03 1.77E-02 4.87E-03 5.66E-03 62 72 302 1M75S3A 1.16E-02 1.61E-02 3.88E-03 1.42E-02 272 112 302 1M75V3A 1.16E-02 2.56E-02 4.63E-03 9.11E-03 82 72 302 1M90M3A 6.30E-03 2.22E-02 4.04E-03 4.55E-03 232 72 302 1M90S3A 9.49E-03 2.00E-02 3.49E-03 9.90E-03 152 172 302 1M90V3A 1.01E-02 2.47E-02 3.99E-03 9.14E-03 162 72 292 1M05M3A 5.89E-03 2.17E-02 3.73E-03 4.41E-03 222 72 302 1M05S3A 8.63E-03 1.79E-02 3.05E-03 4.55E-03 92 122 292 1M05V3A 8.98E-03 2.23E-02 3.75E-03 8.12E-03 2 72 292 1M20M3A 5.44E-03 1.94E-02 3.36E-03 3.94E-03 182 72 292 1M20S3A 7.92E-03 1.66E-02 2.56E-03 3.67E-03 162 32 302 1M20V3A 8.76E-03 1.97E-02 3.27E-03 7.18E-03 42 72 302 1M35M3A 5.14E-03 1.76E-02 2.98E-03 3.67E-03 132 72 302 1M35S3A 7.37E-03 1.53E-02 2.37E-03 4.47E-03 142 82 302 1M35V3A 8.39E-03 1.83E-02 3.12E-03 6.37E-03 12 122 292 1M50M3A 5.00E-03 1.69E-02 2.70E-03 3.57E-03 222 72 302 1M50S3A 6.89E-03 1.41E-02 2.24E-03 5.25E-03 12 122 292 170 Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Max Min Ave 1M50V3A 7.95E-03 1.77E-02 2.67E-03 5.63E-03 162 122 302 1S06M3A 8.65E-03 1.33E-02 6.56E-03 6.99E-03 92 282 12 1S06S3A 1.49E-02 1.99E-02 1.04E-02 1.31E-02 312 272 12 1S06V3A 1.35E-02 1.89E-02 9.97E-03 1.22E-02 142 132 22 1S15M3A 7.95E-03 1.25E-02 6.00E-03 6.83E-03 192 82 262 1S15S3A 1.16E-02 1.59E-02 8.05E-03 1.01E-02 262 222 2 1S15V3A 1.18E-02 1.55E-02 9.16E-03 1.01E-02 142 182 22 1S30M3A 8.73E-03 1.48E-02 5.42E-03 6.63E-03 112 122 312 1S30S3A 8.20E-03 1.17E-02 6.24E-03 7.37E-03 262 122 12 1S30V3A 1.26E-02 3.23E-02 7.86E-03 8.85E-03 122 22 312 1S45M3A 1.58E-02 2.74E-02 5.24E-03 1.96E-02 252 122 312 1S45S3A 6.42E-03 9.60E-03 4.96E-03 5.87E-03 112 222 92 1S45V3A 1.39E-02 3.11E-02 6.28E-03 7.81E-03 92 72 302 1S60M3A 1.65E-02 2.22E-02 4.81E-03 1.88E-02 182 172 312 1S60S3A 5.27E-03 8.47E-03 3.69E-03 4.87E-03 312 72 42 1S60V3A 1.26E-02 3.26E-02 4.96E-03 6.88E-03 112 32 292 1S75M3A 1.23E-02 2.46E-02 4.23E-03 1.52E-02 252 82 302 1S75S3A 4.75E-03 1.39E-02 3.16E-03 4.22E-03 62 72 2 1S75V3A 1.12E-02 2.89E-02 4.39E-03 7.34E-03 112 32 312 1S90M3A 1.05E-02 2.19E-02 3.64E-03 6.22E-03 242 132 312 1S90S3A 4.24E-03 1.64E-02 2.71E-03 3.99E-03 62 72 92 1S90V3A 1.06E-02 2.45E-02 3.49E-03 6.80E-03 142 32 302 1S05M3A 9.51E-03 1.98E-02 3.14E-03 4.45E-03 2 82 302 1S05S3A 3.94E-03 1.56E-02 2.36E-03 3.01E-03 22 72 42 1S05V3A 1.03E-02 2.21E-02 3.74E-03 6.07E-03 142 82 292 1S20M3A 8.63E-03 1.76E-02 2.84E-03 4.73E-03 162 82 312 1S20S3A 3.58E-03 1.40E-02 2.17E-03 2.73E-03 62 72 92 1S20V3A 9.48E-03 2.08E-02 3.31E-03 5.44E-03 142 82 302 1S35M3A 7.86E-03 1.62E-02 2.54E-03 6.96E-03 152 122 302 1S35S3A 3.32E-03 1.33E-02 1.87E-03 2.40E-03 112 72 92 1S35V3A 8.75E-03 1.84E-02 2.87E-03 4.98E-03 162 32 302 1S50M3A 7.49E-03 1.59E-02 2.22E-03 7.94E-03 42 72 302 1S50S3A 2.82E-03 1.21E-02 1.53E-03 1.61E-03 62 72 92 1S50V3A 8.15E-03 1.72E-02 2.41E-03 4.00E-03 212 32 302 171 Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Max Min Ave 1V06M3A 4.32E-02 6.75E-02 1.61E-02 4.16E-02 42 182 302 1V06S3A 4.20E-02 6.53E-02 1.52E-02 4.06E-02 252 272 292 1V06V3A 5.26E-02 7.06E-02 2.11E-02 5.26E-02 252 232 302 1V15M3A 2.17E-02 5.58E-02 8.75E-03 1.29E-02 282 182 312 1V15S3A 2.14E-02 5.56E-02 8.80E-03 1.27E-02 322 222 242 1V15V3A 4.30E-02 5.88E-02 1.20E-02 4.33E-02 62 222 302 1V30M3A 1.14E-02 2.61E-02 7.16E-03 8.11E-03 72 182 302 1V30S3A 1.09E-02 2.61E-02 6.77E-03 7.36E-03 322 122 292 1V30V3A 3.33E-02 4.65E-02 8.67E-03 3.37E-02 2 172 302 1V45M3A 1.19E-02 3.21E-02 5.89E-03 6.96E-03 32 72 302 1V45S3A 1.12E-02 3.00E-02 5.73E-03 6.09E-03 72 32 242 1V45V3A 2.68E-02 3.77E-02 7.17E-03 2.73E-02 52 122 302 1V60M3A 1.22E-02 3.02E-02 5.34E-03 6.19E-03 132 72 252 1V60S3A 1.13E-02 2.76E-02 4.60E-03 5.55E-03 172 32 302 1V60V3A 2.12E-02 2.86E-02 5.78E-03 2.28E-02 202 172 302 1V75M3A 1.13E-02 2.44E-02 4.42E-03 8.86E-03 122 72 302 1V75S3A 1.05E-02 2.31E-02 4.03E-03 8.48E-03 82 32 302 1V75V3A 1.63E-02 2.04E-02 5.04E-03 1.91E-02 262 112 302 1V90M3A 9.80E-03 2.45E-02 4.09E-03 8.91E-03 142 32 292 1V90S3A 9.11E-03 2.39E-02 3.55E-03 8.31E-03 162 72 292 1V90V3A 1.30E-02 1.74E-02 4.30E-03 1.61E-02 82 62 302 1V05M3A 8.45E-03 2.18E-02 3.54E-03 7.63E-03 22 32 302 1V05S3A 7.77E-03 2.06E-02 3.11E-03 7.08E-03 92 72 302 1V05V3A 1.08E-02 1.50E-02 3.74E-03 1.38E-02 72 112 302 1V20M3A 7.39E-03 2.04E-02 3.08E-03 6.51E-03 62 32 302 1V20S3A 6.68E-03 1.84E-02 2.75E-03 5.95E-03 152 72 302 1V20V3A 9.27E-03 1.30E-02 3.47E-03 1.20E-02 12 92 292 1V35M3A 6.52E-03 1.80E-02 2.78E-03 5.27E-03 12 82 302 1V35S3A 5.85E-03 1.71E-02 2.53E-03 4.86E-03 12 72 302 1V35V3A 8.11E-03 1.15E-02 2.95E-03 1.11E-02 252 92 302 1V50M3A 6.02E-03 1.71E-02 2.70E-03 4.81E-03 12 82 312 1V50S3A 5.16E-03 1.61E-02 1.93E-03 4.07E-03 12 72 302 1V50V3A 7.52E-03 1.12E-02 2.81E-03 1.03E-02 252 112 312 172 Table H-6: Summary Phantom Dosimeter Tally Plane using ICRP-74 at 3 Ft Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1M06M3Z 3.26E-02 4.25E-02 2.41E-02 2.95E-02 1062 982 812 1M06S3Z 1.42E-02 2.28E-02 9.79E-03 1.18E-02 1112 1022 802 1M06V3Z 2.58E-02 3.81E-02 1.75E-02 2.20E-02 1112 1072 802 1M15M3Z 2.71E-02 3.48E-02 2.04E-02 2.53E-02 1042 972 812 1M15S3Z 1.39E-02 2.17E-02 1.04E-02 1.18E-02 932 972 802 1M15V3Z 2.24E-02 3.27E-02 1.65E-02 1.90E-02 1012 1122 802 1M30M3Z 2.11E-02 2.66E-02 1.76E-02 1.86E-02 962 922 802 1M30S3Z 1.48E-02 4.33E-02 8.90E-03 1.10E-02 982 822 1092 1M30V3Z 1.97E-02 4.09E-02 1.46E-02 1.57E-02 932 802 1092 1M45M3Z 1.77E-02 2.28E-02 1.42E-02 1.54E-02 892 972 1102 1M45S3Z 2.09E-02 4.24E-02 8.83E-03 1.45E-02 922 832 1102 1M45V3Z 2.35E-02 6.21E-02 1.28E-02 1.38E-02 1022 832 1102 1M60M3Z 1.52E-02 1.96E-02 1.20E-02 1.32E-02 912 872 1102 1M60S3Z 2.42E-02 3.91E-02 7.89E-03 2.95E-02 1052 832 1092 1M60V3Z 2.34E-02 5.36E-02 1.05E-02 1.28E-02 972 832 1102 1M75M3Z 1.39E-02 3.40E-02 1.01E-02 1.14E-02 862 872 1102 1M75S3Z 2.13E-02 2.93E-02 7.57E-03 2.58E-02 1072 912 1102 1M75V3Z 2.16E-02 4.69E-02 8.99E-03 1.71E-02 882 872 1102 1M90M3Z 1.27E-02 4.10E-02 8.62E-03 9.63E-03 1122 872 1102 1M90S3Z 1.76E-02 3.66E-02 6.89E-03 1.81E-02 952 972 1102 1M90V3Z 1.88E-02 4.52E-02 7.78E-03 1.71E-02 962 872 1092 1M05M3Z 1.20E-02 3.93E-02 7.94E-03 9.11E-03 1022 872 1102 1M05S3Z 1.60E-02 3.28E-02 6.02E-03 8.69E-03 892 922 1092 1M05V3Z 1.68E-02 4.08E-02 7.26E-03 1.52E-02 802 872 1092 1M20M3Z 1.11E-02 3.65E-02 7.24E-03 8.43E-03 1022 872 1092 1M20S3Z 1.47E-02 3.03E-02 5.05E-03 7.14E-03 962 832 1102 1M20V3Z 1.64E-02 3.61E-02 6.35E-03 1.35E-02 842 872 1102 1M35M3Z 1.06E-02 3.32E-02 6.33E-03 7.77E-03 912 872 1102 1M35S3Z 1.37E-02 2.80E-02 4.61E-03 8.50E-03 942 882 1102 1M35V3Z 1.57E-02 3.38E-02 6.06E-03 1.20E-02 812 922 1102 1M50M3Z 1.02E-02 3.24E-02 5.99E-03 7.66E-03 932 872 1102 1M50S3Z 1.34E-02 2.70E-02 4.21E-03 1.01E-02 812 882 1102 173 Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1M50V3Z 1.55E-02 3.36E-02 5.77E-03 1.16E-02 902 922 1102 1S06M3Z 1.66E-02 2.53E-02 1.26E-02 1.36E-02 892 1082 812 1S06S3Z 2.86E-02 3.90E-02 2.00E-02 2.52E-02 832 1022 812 1S06V3Z 2.64E-02 3.72E-02 1.98E-02 2.42E-02 992 982 812 1S15M3Z 1.61E-02 2.40E-02 1.18E-02 1.37E-02 892 882 1112 1S15S3Z 2.17E-02 2.98E-02 1.50E-02 1.88E-02 1112 1022 802 1S15V3Z 2.23E-02 2.91E-02 1.74E-02 1.90E-02 1122 1082 822 1S30M3Z 1.74E-02 2.72E-02 1.15E-02 1.38E-02 802 922 1112 1S30S3Z 1.55E-02 2.22E-02 1.18E-02 1.39E-02 1082 1022 812 1S30V3Z 2.36E-02 5.85E-02 1.51E-02 1.68E-02 922 822 1112 1S45M3Z 3.01E-02 5.14E-02 1.09E-02 3.60E-02 1052 922 1112 1S45S3Z 1.23E-02 1.83E-02 9.58E-03 1.12E-02 912 1022 892 1S45V3Z 2.60E-02 5.70E-02 1.21E-02 1.49E-02 892 872 1102 1S60M3Z 3.12E-02 4.18E-02 1.03E-02 3.51E-02 1072 972 1112 1S60S3Z 1.02E-02 1.61E-02 7.31E-03 9.29E-03 962 872 842 1S60V3Z 2.44E-02 5.93E-02 9.98E-03 1.46E-02 922 832 1102 1S75M3Z 2.36E-02 4.56E-02 8.77E-03 2.86E-02 1052 832 1102 1S75S3Z 9.23E-03 2.57E-02 6.21E-03 8.15E-03 862 872 802 1S75V3Z 2.17E-02 5.38E-02 8.96E-03 1.51E-02 872 832 1102 1S90M3Z 2.04E-02 4.12E-02 8.17E-03 1.27E-02 1042 832 1112 1S90S3Z 8.23E-03 3.00E-02 5.41E-03 7.66E-03 962 872 892 1S90V3Z 2.03E-02 4.59E-02 7.76E-03 1.32E-02 942 832 1102 1S05M3Z 1.86E-02 3.82E-02 6.82E-03 9.09E-03 992 882 1102 1S05S3Z 7.67E-03 2.85E-02 4.73E-03 5.86E-03 822 872 842 1S05V3Z 1.91E-02 4.06E-02 7.29E-03 1.16E-02 942 882 1092 1S20M3Z 1.67E-02 3.34E-02 6.16E-03 9.34E-03 962 882 1102 1S20S3Z 6.98E-03 2.57E-02 4.35E-03 5.38E-03 862 872 892 1S20V3Z 1.76E-02 3.83E-02 6.45E-03 1.04E-02 942 882 1102 1S35M3Z 1.52E-02 3.09E-02 5.61E-03 1.37E-02 952 922 1102 1S35S3Z 6.47E-03 2.46E-02 3.75E-03 4.78E-03 912 872 802 1S35V3Z 1.63E-02 3.39E-02 5.61E-03 9.58E-03 962 832 1102 1S50M3Z 1.45E-02 2.98E-02 5.00E-03 1.53E-02 842 872 1102 1S50S3Z 6.09E-03 2.39E-02 3.52E-03 4.31E-03 1122 872 1042 1S50V3Z 1.57E-02 3.24E-02 5.05E-03 8.28E-03 1012 832 1102 174 Tally Total (mrem/hr/kg) Dosimeter Position for Configuration Ave Max Min Reference Ave Max Min 1V06M3Z 7.82E-02 1.21E-01 3.01E-02 7.51E-02 842 982 1102 1V06S3Z 7.68E-02 1.19E-01 2.89E-02 7.42E-02 1002 1022 1092 1V06V3Z 9.62E-02 1.28E-01 4.01E-02 9.57E-02 952 1022 1102 1V15M3Z 4.11E-02 1.02E-01 1.82E-02 2.48E-02 1082 982 822 1V15S3Z 3.93E-02 1.00E-01 1.68E-02 2.37E-02 1122 1022 1042 1V15V3Z 7.87E-02 1.07E-01 2.43E-02 7.91E-02 862 1022 1092 1V30M3Z 2.27E-02 4.92E-02 1.43E-02 1.65E-02 1022 882 1062 1V30S3Z 2.05E-02 4.76E-02 1.30E-02 1.40E-02 1122 922 1092 1V30V3Z 6.15E-02 8.61E-02 1.77E-02 6.13E-02 802 972 1102 1V45M3Z 2.32E-02 6.02E-02 1.22E-02 1.41E-02 832 872 1102 1V45S3Z 2.09E-02 5.42E-02 1.10E-02 1.16E-02 922 832 1042 1V45V3Z 4.97E-02 7.00E-02 1.41E-02 5.04E-02 852 922 1102 1V60M3Z 2.37E-02 5.47E-02 1.13E-02 1.25E-02 882 872 1052 1V60S3Z 2.10E-02 4.99E-02 8.80E-03 1.06E-02 972 832 1102 1V60V3Z 3.96E-02 5.36E-02 1.20E-02 4.23E-02 1002 972 1102 1V75M3Z 2.19E-02 4.55E-02 9.19E-03 1.74E-02 922 872 1102 1V75S3Z 1.95E-02 4.21E-02 7.83E-03 1.58E-02 882 832 1102 1V75V3Z 3.09E-02 3.81E-02 1.03E-02 3.59E-02 982 912 1102 1V90M3Z 1.92E-02 4.50E-02 8.68E-03 1.71E-02 942 832 1102 1V90S3Z 1.69E-02 4.35E-02 6.93E-03 1.54E-02 962 872 1092 1V90V3Z 2.49E-02 3.17E-02 9.37E-03 3.02E-02 1062 912 1102 1V05M3Z 1.66E-02 4.05E-02 7.73E-03 1.52E-02 912 832 1112 1V05S3Z 1.45E-02 3.76E-02 6.10E-03 1.32E-02 892 872 1102 1V05V3Z 2.09E-02 2.78E-02 8.20E-03 2.61E-02 912 972 1102 1V20M3Z 1.45E-02 3.77E-02 6.73E-03 1.24E-02 862 832 1102 1V20S3Z 1.25E-02 3.37E-02 5.35E-03 1.12E-02 952 872 1102 1V20V3Z 1.79E-02 2.44E-02 7.42E-03 2.29E-02 1052 862 1102 1V35M3Z 1.28E-02 3.37E-02 5.67E-03 1.04E-02 812 832 1102 1V35S3Z 1.10E-02 3.13E-02 4.92E-03 9.28E-03 812 872 1102 1V35V3Z 1.58E-02 2.19E-02 6.11E-03 2.09E-02 922 912 1102 1V50M3Z 1.19E-02 3.24E-02 5.38E-03 9.50E-03 812 882 1112 1V50S3Z 1.03E-02 3.04E-02 4.37E-03 8.18E-03 1022 872 1102 1V50V3Z 1.47E-02 2.06E-02 6.00E-03 1.96E-02 1052 912 1092 175 Appendix E: Estimated Dose Using Phantom's Dosimeter Lattice 176 Table E-1: Summary Whole Body Dose using ANSI 1977 at 1 Ft ICRP 26 M w/oB 4.17E-02 5.16E-03 1.81E-02 4.31E-02 7.34E-03 2.68E-02 2.86E-02 9.36E-03 2.51E-02 1.91E-02 8.31E-03 1.91E-02 1.31E-02 8.59E-03 1.31E-02 9.67E-03 7.02E-03 9.71E-03 7.41E-03 5.42E-03 7.73E-03 5.72E-03 4.70E-03 6.58E-03 4.75E-03 3.70E-03 5.90E-03 4.08E-03 2.94E-03 Configuration 1M06M1A 1M06S1A 1M06V1A 1M15M1A 1M15S1A 1M15V1A 1M30M1A 1M30S1A 1M30V1A 1M45M1A 1M45S1A 1M45V1A 1M60M1A 1M60S1A 1M60V1A 1M75M1A 1M75S1A 1M75V1A 1M90M1A 1M90S1A 1M90V1A 1M05M1A 1M05S1A 1M05V1A 1M20M1A 1M20S1A 1M20V1A 1M35M1A 1M35S1A MwB 5.14E-02 6.36E-03 2.19E-02 5.10E-02 1.06E-02 3.11E-02 3.38E-02 1.37E-02 3.45E-02 2.37E-02 1.20E-02 2.96E-02 1.78E-02 1.14E-02 2.27E-02 1.42E-02 1.02E-02 1.74E-02 1.13E-02 8.24E-03 1.39E-02 9.12E-03 7.22E-03 1.17E-02 7.70E-03 5.88E-03 1.02E-02 6.67E-03 4.92E-03 Female 3.15E-02 4.12E-03 1.33E-02 2.76E-02 7.05E-03 1.89E-02 1.85E-02 1.05E-02 2.51E-02 1.37E-02 8.98E-03 2.27E-02 1.14E-02 8.83E-03 1.73E-02 9.63E-03 8.16E-03 1.36E-02 7.86E-03 6.72E-03 1.11E-02 6.71E-03 5.76E-03 9.54E-03 5.92E-03 4.79E-03 8.39E-03 4.92E-03 3.97E-03 MwB 3.97E-02 4.35E-03 1.66E-02 3.78E-02 6.77E-03 2.38E-02 2.47E-02 1.06E-02 2.23E-02 1.70E-02 7.58E-03 1.79E-02 1.22E-02 7.20E-03 1.34E-02 9.49E-03 5.91E-03 1.02E-02 7.43E-03 4.46E-03 8.18E-03 5.86E-03 3.89E-03 6.72E-03 4.93E-03 3.22E-03 5.72E-03 4.30E-03 2.86E-03 ICRP 60 M w/o B 3.64E-02 3.96E-03 1.53E-02 3.51E-02 5.70E-03 2.24E-02 2.30E-02 9.19E-03 1.91E-02 1.55E-02 6.36E-03 1.44E-02 1.06E-02 6.25E-03 1.02E-02 7.97E-03 4.87E-03 7.69E-03 6.13E-03 3.52E-03 6.13E-03 4.73E-03 3.05E-03 5.03E-03 3.95E-03 2.50E-03 4.29E-03 3.44E-03 2.20E-03 Female 2.37E-02 2.57E-03 9.70E-03 1.91E-02 3.97E-03 1.41E-02 1.25E-02 8.06E-03 1.47E-02 9.04E-03 5.19E-03 1.24E-02 7.07E-03 5.13E-03 9.07E-03 5.80E-03 4.31E-03 7.25E-03 4.66E-03 3.25E-03 5.96E-03 3.93E-03 2.72E-03 5.02E-03 3.51E-03 2.35E-03 4.29E-03 2.90E-03 2.10E-03 177 Configuration 1M35V1A 1M50M1A 1M50S1A 1M50V1A 1S06M1A 1S06S1A 1S06V1A 1S15M1A 1S15S1A 1S15V1A 1S30M1A 1S30S1A 1S30V1A 1S45M1A 1S45S1A 1S45V1A 1S60M1A 1S60S1A 1S60V1A 1S75M1A 1S75S1A 1S75V1A 1S90M1A 1S90S1A 1S90V1A 1S05M1A 1S05S1A 1S05V1A 1S20M1A 1S20S1A 1S20V1A MwB 9.05E-03 5.85E-03 4.42E-03 8.44E-03 8.28E-03 4.44E-02 2.93E-02 1.63E-02 4.35E-02 4.08E-02 1.62E-02 2.69E-02 4.21E-02 1.58E-02 1.72E-02 3.31E-02 1.47E-02 1.18E-02 2.48E-02 1.28E-02 8.41E-03 1.95E-02 1.03E-02 5.95E-03 1.58E-02 8.87E-03 4.63E-03 1.32E-02 6.87E-03 3.89E-03 1.10E-02 ICRP 26 M w/oB 5.37E-03 3.40E-03 2.51E-03 4.98E-03 6.60E-03 3.60E-02 2.36E-02 1.14E-02 3.80E-02 3.44E-02 1.13E-02 2.38E-02 2.91E-02 1.17E-02 1.50E-02 1.94E-02 1.06E-02 1.02E-02 1.38E-02 8.64E-03 7.18E-03 1.08E-02 6.67E-03 4.97E-03 9.15E-03 5.76E-03 3.80E-03 7.77E-03 4.19E-03 3.18E-03 6.61E-03 Female 7.49E-03 4.52E-03 3.63E-03 7.18E-03 5.33E-03 2.75E-02 1.84E-02 1.18E-02 2.20E-02 2.53E-02 1.18E-02 1.34E-02 3.09E-02 1.19E-02 8.79E-03 2.47E-02 1.16E-02 6.04E-03 1.94E-02 1.01E-02 4.39E-03 1.56E-02 8.28E-03 3.38E-03 1.29E-02 7.09E-03 2.73E-03 1.10E-02 5.47E-03 2.28E-03 9.17E-03 MwB 5.07E-03 3.72E-03 2.64E-03 4.70E-03 5.41E-03 3.52E-02 2.06E-02 1.06E-02 3.27E-02 2.93E-02 1.06E-02 1.98E-02 2.63E-02 9.71E-03 1.25E-02 2.02E-02 9.16E-03 8.56E-03 1.57E-02 7.25E-03 6.08E-03 1.24E-02 5.52E-03 4.29E-03 9.80E-03 4.81E-03 3.33E-03 8.06E-03 3.97E-03 2.79E-03 6.84E-03 ICRP 60 M w/o B 3.84E-03 2.90E-03 2.00E-03 3.55E-03 4.85E-03 3.24E-02 1.87E-02 8.93E-03 3.09E-02 2.72E-02 8.92E-03 1.87E-02 2.20E-02 8.33E-03 1.18E-02 1.56E-02 7.80E-03 8.03E-03 1.20E-02 5.86E-03 5.67E-03 9.53E-03 4.31E-03 3.96E-03 7.58E-03 3.77E-03 3.05E-03 6.27E-03 3.08E-03 2.55E-03 5.39E-03 Female 3.82E-03 2.66E-03 2.00E-03 3.69E-03 3.05E-03 2.17E-02 1.19E-02 7.01E-03 1.55E-02 1.69E-02 7.02E-03 8.99E-03 1.74E-02 6.57E-03 5.83E-03 1.35E-02 6.68E-03 3.96E-03 1.13E-02 5.08E-03 2.86E-03 9.31E-03 3.90E-03 2.23E-03 7.47E-03 3.38E-03 1.81E-03 6.31E-03 2.85E-03 1.51E-03 5.41E-03 178 Configuration 1S35M1A 1S35S1A 1S35V1A 1S50M1A 1S50S1A 1S50V1A 1V06M1A 1V06S1A 1V06V1A 1V15M1A 1V15S1A 1V15V1A 1V30M1A 1V30S1A 1V30V1A 1V45M1A 1V45S1A 1V45V1A 1V60M1A 1V60S1A 1V60V1A 1V75M1A 1V75S1A 1V75V1A 1V90M1A 1V90S1A 1V90V1A 1V05M1A 1V05S1A 1V05V1A 1V20M1A MwB 5.67E-03 3.18E-03 9.25E-03 5.00E-03 2.82E-03 8.64E-03 2.35E-02 2.33E-02 1.25E-01 2.81E-02 2.70E-02 1.03E-01 3.25E-02 3.08E-02 6.53E-02 2.53E-02 2.39E-02 4.16E-02 1.76E-02 1.58E-02 2.80E-02 1.32E-02 1.18E-02 2.01E-02 1.07E-02 8.45E-03 1.49E-02 8.49E-03 6.82E-03 1.19E-02 6.93E-03 ICRP 26 M w/oB 3.27E-03 2.55E-03 5.62E-03 2.80E-03 2.24E-03 5.19E-03 1.88E-02 1.89E-02 7.66E-02 2.42E-02 2.36E-02 6.82E-02 2.40E-02 2.28E-02 4.43E-02 1.73E-02 1.65E-02 2.94E-02 1.13E-02 1.01E-02 2.00E-02 8.14E-03 7.36E-03 1.44E-02 6.78E-03 5.10E-03 1.08E-02 5.31E-03 4.16E-03 8.57E-03 4.29E-03 Female 4.48E-03 1.90E-03 7.76E-03 4.02E-03 1.85E-03 7.37E-03 1.59E-02 1.57E-02 1.05E-01 1.69E-02 1.59E-02 7.96E-02 2.31E-02 2.21E-02 5.00E-02 1.88E-02 1.76E-02 3.17E-02 1.25E-02 1.11E-02 2.12E-02 9.55E-03 8.20E-03 1.57E-02 7.53E-03 6.20E-03 1.16E-02 6.29E-03 4.98E-03 9.48E-03 5.15E-03 MwB 3.37E-03 2.27E-03 5.78E-03 2.99E-03 2.00E-03 5.39E-03 1.63E-02 1.71E-02 8.56E-02 2.06E-02 2.08E-02 7.18E-02 2.05E-02 1.99E-02 4.56E-02 1.54E-02 1.48E-02 2.93E-02 1.09E-02 9.81E-03 1.93E-02 8.20E-03 7.37E-03 1.38E-02 6.74E-03 5.23E-03 1.03E-02 5.39E-03 4.27E-03 8.08E-03 4.44E-03 ICRP 60 M w/o B 2.57E-03 2.06E-03 4.57E-03 2.26E-03 1.80E-03 4.24E-03 1.47E-02 1.57E-02 6.96E-02 1.93E-02 1.97E-02 6.01E-02 1.77E-02 1.73E-02 3.86E-02 1.27E-02 1.23E-02 2.52E-02 8.78E-03 7.89E-03 1.66E-02 6.50E-03 5.89E-03 1.19E-02 5.45E-03 4.12E-03 8.91E-03 4.32E-03 3.38E-03 6.98E-03 3.56E-03 Female 2.42E-03 1.24E-03 4.58E-03 2.22E-03 1.22E-03 4.37E-03 1.02E-02 1.10E-02 7.03E-02 1.17E-02 1.19E-02 5.28E-02 1.30E-02 1.30E-02 3.34E-02 1.02E-02 9.73E-03 2.14E-02 6.80E-03 6.05E-03 1.39E-02 5.26E-03 4.48E-03 1.02E-02 4.23E-03 3.43E-03 7.62E-03 3.63E-03 2.80E-03 6.16E-03 3.01E-03 179 Configuration 1V20S1A 1V20V1A 1V35M1A 1V35S1A 1V35V1A 1V50M1A 1V50S1A 1V50V1A MwB 5.40E-03 9.73E-03 5.82E-03 4.53E-03 8.29E-03 5.11E-03 4.13E-03 7.44E-03 ICRP 26 M w/oB 3.32E-03 7.06E-03 3.63E-03 2.85E-03 5.99E-03 3.07E-03 2.60E-03 5.31E-03 Female 3.97E-03 7.78E-03 4.36E-03 3.21E-03 6.68E-03 3.93E-03 2.96E-03 6.08E-03 MwB 3.41E-03 6.64E-03 3.74E-03 2.86E-03 5.68E-03 3.24E-03 2.65E-03 5.06E-03 ICRP 60 M w/o B 2.72E-03 5.75E-03 3.01E-03 2.30E-03 4.91E-03 2.56E-03 2.14E-03 4.35E-03 Female 2.27E-03 5.08E-03 2.57E-03 1.81E-03 4.39E-03 2.30E-03 1.72E-03 3.97E-03 180 Table E-2: Summary Whole Body Dose using ANSI 1991 at 1 Ft ICRP 26 M w/o B 9.07E-02 1.08E-02 3.94E-02 9.39E-02 1.61E-02 5.83E-02 6.20E-02 2.04E-02 5.47E-02 4.12E-02 1.82E-02 4.17E-02 2.83E-02 1.87E-02 2.86E-02 2.05E-02 1.53E-02 2.13E-02 1.58E-02 1.18E-02 1.70E-02 1.21E-02 1.03E-02 1.45E-02 1.04E-02 8.12E-03 1.29E-02 8.75E-03 6.49E-03 Configuration 1M06M1B 1M06S1B 1M06V1B 1M15M1B 1M15S1B 1M15V1B 1M30M1B 1M30S1B 1M30V1B 1M45M1B 1M45S1B 1M45V1B 1M60M1B 1M60S1B 1M60V1B 1M75M1B 1M75S1B 1M75V1B 1M90M1B 1M90S1B 1M90V1B 1M05M1B 1M05S1B 1M05V1B 1M20M1B 1M20S1B 1M20V1B 1M35M1B 1M35S1B MwB 1.12E-01 1.33E-02 4.79E-02 1.11E-01 2.30E-02 6.77E-02 7.34E-02 2.98E-02 7.51E-02 5.09E-02 2.61E-02 6.44E-02 3.87E-02 2.49E-02 4.95E-02 3.03E-02 2.22E-02 3.79E-02 2.42E-02 1.80E-02 3.03E-02 1.94E-02 1.58E-02 2.55E-02 1.68E-02 1.29E-02 2.23E-02 1.43E-02 1.08E-02 Female 6.86E-02 8.64E-03 2.92E-02 5.98E-02 1.53E-02 4.11E-02 4.01E-02 2.27E-02 5.45E-02 2.97E-02 1.95E-02 4.93E-02 2.47E-02 1.92E-02 3.76E-02 2.06E-02 1.77E-02 2.96E-02 1.66E-02 1.46E-02 2.42E-02 1.42E-02 1.25E-02 2.08E-02 1.27E-02 1.05E-02 1.83E-02 1.04E-02 8.68E-03 MwB 8.63E-02 9.14E-03 3.62E-02 8.25E-02 1.48E-02 5.19E-02 5.39E-02 2.31E-02 4.85E-02 3.67E-02 1.66E-02 3.90E-02 2.66E-02 1.57E-02 2.93E-02 2.02E-02 1.29E-02 2.24E-02 1.60E-02 9.76E-03 1.79E-02 1.25E-02 8.52E-03 1.47E-02 1.08E-02 7.08E-03 1.26E-02 9.24E-03 6.31E-03 ICRP 60 M w/o B 7.92E-02 8.30E-03 3.34E-02 7.69E-02 1.25E-02 4.87E-02 5.01E-02 2.00E-02 4.16E-02 3.34E-02 1.39E-02 3.14E-02 2.32E-02 1.36E-02 2.23E-02 1.70E-02 1.07E-02 1.69E-02 1.32E-02 7.71E-03 1.34E-02 1.01E-02 6.70E-03 1.11E-02 8.63E-03 5.49E-03 9.45E-03 7.39E-03 4.86E-03 Female 5.17E-02 5.42E-03 2.12E-02 4.17E-02 8.65E-03 3.06E-02 2.73E-02 1.75E-02 3.20E-02 1.98E-02 1.13E-02 2.69E-02 1.55E-02 1.11E-02 1.98E-02 1.24E-02 9.38E-03 1.58E-02 9.91E-03 7.08E-03 1.30E-02 8.36E-03 5.94E-03 1.10E-02 7.44E-03 5.14E-03 9.38E-03 6.14E-03 4.59E-03 181 Configuration 1M35V1B 1M50M1B 1M50S1B 1M50V1B 1S06M1B 1S06S1B 1S06V1B 1S15M1B 1S15S1B 1S15V1B 1S30M1B 1S30S1B 1S30V1B 1S45M1B 1S45S1B 1S45V1B 1S60M1B 1S60S1B 1S60V1B 1S75M1B 1S75S1B 1S75V1B 1S90M1B 1S90S1B 1S90V1B 1S05M1B 1S05S1B 1S05V1B 1S20M1B 1S20S1B 1S20V1B MwB 1.98E-02 1.29E-02 9.73E-03 1.85E-02 1.82E-02 9.64E-02 6.40E-02 3.50E-02 9.47E-02 8.90E-02 3.51E-02 5.88E-02 9.17E-02 3.37E-02 3.76E-02 7.22E-02 3.14E-02 2.58E-02 5.42E-02 2.75E-02 1.85E-02 4.26E-02 2.24E-02 1.31E-02 3.45E-02 1.91E-02 1.02E-02 2.87E-02 1.48E-02 8.59E-03 2.40E-02 ICRP 26 M w/o B 1.18E-02 7.51E-03 5.54E-03 1.09E-02 1.45E-02 7.82E-02 5.15E-02 2.44E-02 8.27E-02 7.50E-02 2.45E-02 5.19E-02 6.34E-02 2.47E-02 3.29E-02 4.24E-02 2.26E-02 2.23E-02 3.03E-02 1.85E-02 1.58E-02 2.38E-02 1.45E-02 1.10E-02 2.00E-02 1.24E-02 8.38E-03 1.70E-02 9.02E-03 7.02E-03 1.45E-02 Female 1.64E-02 9.92E-03 7.94E-03 1.57E-02 1.17E-02 5.94E-02 4.03E-02 2.53E-02 4.78E-02 5.51E-02 2.54E-02 2.93E-02 6.73E-02 2.58E-02 1.92E-02 5.38E-02 2.48E-02 1.32E-02 4.22E-02 2.19E-02 9.64E-03 3.40E-02 1.80E-02 7.43E-03 2.81E-02 1.48E-02 6.00E-03 2.39E-02 1.19E-02 5.02E-03 2.00E-02 MwB 1.11E-02 8.21E-03 5.80E-03 1.03E-02 1.19E-02 7.69E-02 4.50E-02 2.28E-02 7.13E-02 6.38E-02 2.28E-02 4.32E-02 5.74E-02 2.07E-02 2.74E-02 4.42E-02 1.96E-02 1.87E-02 3.42E-02 1.55E-02 1.34E-02 2.71E-02 1.20E-02 9.44E-03 2.14E-02 1.04E-02 7.33E-03 1.76E-02 8.56E-03 6.15E-03 1.50E-02 ICRP 60 M w/o B 8.47E-03 6.41E-03 4.41E-03 7.81E-03 1.07E-02 7.08E-02 4.08E-02 1.93E-02 6.73E-02 5.92E-02 1.93E-02 4.09E-02 4.79E-02 1.77E-02 2.58E-02 3.42E-02 1.67E-02 1.76E-02 2.62E-02 1.25E-02 1.25E-02 2.09E-02 9.35E-03 8.71E-03 1.66E-02 8.17E-03 6.72E-03 1.37E-02 6.62E-03 5.63E-03 1.18E-02 Female 8.37E-03 5.83E-03 4.37E-03 8.08E-03 6.74E-03 4.73E-02 2.60E-02 1.50E-02 3.38E-02 3.68E-02 1.51E-02 1.96E-02 3.78E-02 1.44E-02 1.27E-02 2.95E-02 1.44E-02 8.64E-03 2.46E-02 1.10E-02 6.27E-03 2.03E-02 8.47E-03 4.88E-03 1.63E-02 7.01E-03 3.96E-03 1.38E-02 6.22E-03 3.30E-03 1.18E-02 182 Configuration 1S35M1B 1S35S1B 1S35V1B 1S50M1B 1S50S1B 1S50V1B 1V06M1B 1V06S1B 1V06V1B 1V15M1B 1V15S1B 1V15V1B 1V30M1B 1V30S1B 1V30V1B 1V45M1B 1V45S1B 1V45V1B 1V60M1B 1V60S1B 1V60V1B 1V75M1B 1V75S1B 1V75V1B 1V90M1B 1V90S1B 1V90V1B 1V05M1B 1V05S1B 1V05V1B 1V20M1B MwB 1.26E-02 7.04E-03 2.02E-02 1.10E-02 6.26E-03 1.89E-02 5.13E-02 5.03E-02 2.70E-01 6.11E-02 5.89E-02 2.24E-01 6.98E-02 6.69E-02 1.42E-01 5.48E-02 5.21E-02 9.07E-02 3.79E-02 3.45E-02 6.11E-02 2.84E-02 2.58E-02 4.40E-02 2.23E-02 1.85E-02 3.26E-02 1.81E-02 1.49E-02 2.60E-02 1.49E-02 ICRP 26 M w/o B 7.48E-03 5.64E-03 1.23E-02 6.20E-03 4.97E-03 1.14E-02 4.10E-02 4.07E-02 1.66E-01 5.27E-02 5.13E-02 1.48E-01 5.17E-02 4.97E-02 9.63E-02 3.77E-02 3.60E-02 6.40E-02 2.43E-02 2.20E-02 4.36E-02 1.74E-02 1.62E-02 3.16E-02 1.40E-02 1.12E-02 2.36E-02 1.12E-02 9.15E-03 1.88E-02 9.21E-03 Female 9.62E-03 4.18E-03 1.69E-02 8.82E-03 4.09E-03 1.61E-02 3.46E-02 3.44E-02 2.28E-01 3.65E-02 3.45E-02 1.72E-01 4.97E-02 4.79E-02 1.09E-01 4.07E-02 3.83E-02 6.90E-02 2.69E-02 2.42E-02 4.63E-02 2.07E-02 1.79E-02 3.42E-02 1.61E-02 1.35E-02 2.53E-02 1.34E-02 1.09E-02 2.07E-02 1.09E-02 MwB 7.59E-03 5.02E-03 1.27E-02 6.59E-03 4.42E-03 1.18E-02 3.55E-02 3.70E-02 1.86E-01 4.49E-02 4.53E-02 1.56E-01 4.42E-02 4.34E-02 9.92E-02 3.34E-02 3.22E-02 6.38E-02 2.35E-02 2.14E-02 4.21E-02 1.76E-02 1.61E-02 3.01E-02 1.41E-02 1.15E-02 2.25E-02 1.15E-02 9.37E-03 1.77E-02 9.53E-03 ICRP 60 M w/o B 5.89E-03 4.55E-03 1.00E-02 4.99E-03 3.99E-03 9.31E-03 3.21E-02 3.38E-02 1.51E-01 4.21E-02 4.28E-02 1.30E-01 3.82E-02 3.76E-02 8.40E-02 2.77E-02 2.68E-02 5.49E-02 1.90E-02 1.73E-02 3.63E-02 1.40E-02 1.29E-02 2.60E-02 1.13E-02 9.05E-03 1.95E-02 9.17E-03 7.44E-03 1.53E-02 7.65E-03 Female 5.21E-03 2.73E-03 1.00E-02 4.85E-03 2.68E-03 9.56E-03 2.22E-02 2.42E-02 1.52E-01 2.52E-02 2.58E-02 1.14E-01 2.81E-02 2.81E-02 7.25E-02 2.21E-02 2.11E-02 4.65E-02 1.47E-02 1.32E-02 3.02E-02 1.14E-02 9.76E-03 2.23E-02 9.10E-03 7.51E-03 1.66E-02 7.69E-03 6.10E-03 1.34E-02 6.36E-03 183 Configuration 1V20S1B 1V20V1B 1V35M1B 1V35S1B 1V35V1B 1V50M1B 1V50S1B 1V50V1B MwB 1.19E-02 2.13E-02 1.25E-02 9.98E-03 1.82E-02 1.12E-02 9.08E-03 1.63E-02 ICRP 26 M w/o B 7.33E-03 1.55E-02 7.85E-03 6.31E-03 1.31E-02 6.78E-03 5.74E-03 1.16E-02 Female 8.67E-03 1.70E-02 9.26E-03 7.04E-03 1.46E-02 8.61E-03 6.49E-03 1.33E-02 MwB 7.51E-03 1.45E-02 8.09E-03 6.30E-03 1.25E-02 7.14E-03 5.83E-03 1.11E-02 ICRP 60 M w/o B 5.99E-03 1.26E-02 6.53E-03 5.08E-03 1.08E-02 5.65E-03 4.71E-03 9.54E-03 Female 4.96E-03 1.11E-02 5.47E-03 3.95E-03 9.60E-03 5.04E-03 3.76E-03 8.68E-03 184 Table E-3: Summary Whole Body Dose using ICRP-74 at 1 Ft ICRP 26 M w/o B 7.73E-02 9.22E-03 3.36E-02 8.02E-02 1.38E-02 4.98E-02 5.30E-02 1.74E-02 4.67E-02 3.52E-02 1.55E-02 3.56E-02 2.42E-02 1.60E-02 2.45E-02 1.75E-02 1.31E-02 1.82E-02 1.35E-02 1.01E-02 1.45E-02 1.04E-02 8.81E-03 1.24E-02 8.92E-03 6.95E-03 1.11E-02 7.52E-03 5.56E-03 Configuration M w B 1M06M1B 1M06S1B 1M06V1B 1M15M1B 1M15S1B 1M15V1B 1M30M1B 1M30S1B 1M30V1B 1M45M1B 1M45S1B 1M45V1B 1M60M1B 1M60S1B 1M60V1B 1M75M1B 1M75S1B 1M75V1B 1M90M1B 1M90S1B 1M90V1B 1M05M1B 1M05S1B 1M05V1B 1M20M1B 1M20S1B 1M20V1B 1M35M1B 1M35S1B 9.53E-02 1.14E-02 4.09E-02 9.47E-02 1.97E-02 5.78E-02 6.27E-02 2.54E-02 6.41E-02 4.35E-02 2.23E-02 5.49E-02 3.30E-02 2.12E-02 4.23E-02 2.59E-02 1.89E-02 3.24E-02 2.07E-02 1.53E-02 2.59E-02 1.66E-02 1.35E-02 2.18E-02 1.44E-02 1.10E-02 1.90E-02 1.23E-02 9.26E-03 Female 5.84E-02 7.39E-03 2.49E-02 5.10E-02 1.31E-02 3.51E-02 3.42E-02 1.93E-02 4.65E-02 2.54E-02 1.66E-02 4.20E-02 2.11E-02 1.63E-02 3.21E-02 1.76E-02 1.51E-02 2.53E-02 1.42E-02 1.25E-02 2.06E-02 1.21E-02 1.07E-02 1.78E-02 1.08E-02 8.91E-03 1.56E-02 8.92E-03 7.41E-03 MwB 7.35E-02 7.81E-03 3.08E-02 7.04E-02 1.26E-02 4.42E-02 4.60E-02 1.97E-02 4.13E-02 3.13E-02 1.42E-02 3.33E-02 2.27E-02 1.34E-02 2.50E-02 1.73E-02 1.10E-02 1.91E-02 1.36E-02 8.33E-03 1.53E-02 1.07E-02 7.28E-03 1.26E-02 9.21E-03 6.05E-03 1.07E-02 7.92E-03 5.39E-03 ICRP 60 M w/o B 6.74E-02 7.09E-03 2.84E-02 6.55E-02 1.07E-02 4.15E-02 4.27E-02 1.70E-02 3.55E-02 2.86E-02 1.19E-02 2.68E-02 1.98E-02 1.16E-02 1.91E-02 1.45E-02 9.10E-03 1.44E-02 1.13E-02 6.58E-03 1.15E-02 8.62E-03 5.73E-03 9.47E-03 7.39E-03 4.70E-03 8.08E-03 6.33E-03 4.16E-03 Female 4.39E-02 4.63E-03 1.80E-02 3.54E-02 7.37E-03 2.60E-02 2.32E-02 1.49E-02 2.72E-02 1.68E-02 9.62E-03 2.29E-02 1.32E-02 9.48E-03 1.68E-02 1.06E-02 7.99E-03 1.35E-02 8.45E-03 6.02E-03 1.11E-02 7.12E-03 5.06E-03 9.35E-03 6.36E-03 4.38E-03 8.00E-03 5.24E-03 3.92E-03 185 Configuration M w B 1M35V1B 1M50M1B 1M50S1B 1M50V1B 1S06M1B 1S06S1B 1S06V1B 1S15M1B 1S15S1B 1S15V1B 1S30M1B 1S30S1B 1S30V1B 1S45M1B 1S45S1B 1S45V1B 1S60M1B 1S60S1B 1S60V1B 1S75M1B 1S75S1B 1S75V1B 1S90M1B 1S90S1B 1S90V1B 1S05M1B 1S05S1B 1S05V1B 1S20M1B 1S20S1B 1S20V1B 1.69E-02 1.10E-02 8.32E-03 1.58E-02 1.56E-02 8.20E-02 5.45E-02 2.98E-02 8.08E-02 7.60E-02 3.00E-02 5.02E-02 7.83E-02 2.88E-02 3.21E-02 6.17E-02 2.68E-02 2.21E-02 4.63E-02 2.35E-02 1.59E-02 3.64E-02 1.91E-02 1.13E-02 2.95E-02 1.63E-02 8.75E-03 2.46E-02 1.27E-02 7.37E-03 2.05E-02 ICRP 26 M w/o B 1.01E-02 6.45E-03 4.74E-03 9.35E-03 1.24E-02 6.65E-02 4.39E-02 2.09E-02 7.06E-02 6.40E-02 2.09E-02 4.43E-02 5.42E-02 2.11E-02 2.81E-02 3.63E-02 1.93E-02 1.91E-02 2.59E-02 1.58E-02 1.35E-02 2.03E-02 1.24E-02 9.40E-03 1.71E-02 1.06E-02 7.18E-03 1.46E-02 7.72E-03 6.03E-03 1.24E-02 Female 1.40E-02 8.47E-03 6.78E-03 1.34E-02 1.00E-02 5.05E-02 3.43E-02 2.15E-02 4.07E-02 4.70E-02 2.17E-02 2.49E-02 5.74E-02 2.20E-02 1.64E-02 4.59E-02 2.12E-02 1.13E-02 3.60E-02 1.87E-02 8.23E-03 2.90E-02 1.54E-02 6.35E-03 2.40E-02 1.27E-02 5.14E-03 2.04E-02 1.02E-02 4.29E-03 1.70E-02 MwB 9.53E-03 7.03E-03 4.96E-03 8.83E-03 1.02E-02 6.53E-02 3.83E-02 1.94E-02 6.08E-02 5.45E-02 1.95E-02 3.68E-02 4.89E-02 1.77E-02 2.34E-02 3.77E-02 1.68E-02 1.60E-02 2.92E-02 1.33E-02 1.14E-02 2.32E-02 1.02E-02 8.08E-03 1.83E-02 8.92E-03 6.27E-03 1.51E-02 7.32E-03 5.28E-03 1.28E-02 ICRP 60 M w/o B 7.25E-03 5.50E-03 3.77E-03 6.67E-03 9.14E-03 6.02E-02 3.47E-02 1.64E-02 5.73E-02 5.05E-02 1.65E-02 3.49E-02 4.09E-02 1.52E-02 2.21E-02 2.93E-02 1.43E-02 1.50E-02 2.24E-02 1.07E-02 1.07E-02 1.78E-02 8.00E-03 7.46E-03 1.42E-02 7.00E-03 5.75E-03 1.18E-02 5.66E-03 4.83E-03 1.01E-02 Female 7.14E-03 4.97E-03 3.73E-03 6.90E-03 5.76E-03 4.02E-02 2.22E-02 1.28E-02 2.87E-02 3.13E-02 1.28E-02 1.66E-02 3.22E-02 1.23E-02 1.08E-02 2.51E-02 1.23E-02 7.36E-03 2.10E-02 9.40E-03 5.34E-03 1.73E-02 7.23E-03 4.16E-03 1.39E-02 5.98E-03 3.38E-03 1.17E-02 5.31E-03 2.81E-03 1.00E-02 186 Configuration M w B 1S35M1B 1S35S1B 1S35V1B 1S50M1B 1S50S1B 1S50V1B 1V06M1B 1V06S1B 1V06V1B 1V15M1B 1V15S1B 1V15V1B 1V30M1B 1V30S1B 1V30V1B 1V45M1B 1V45S1B 1V45V1B 1V60M1B 1V60S1B 1V60V1B 1V75M1B 1V75S1B 1V75V1B 1V90M1B 1V90S1B 1V90V1B 1V05M1B 1V05S1B 1V05V1B 1V20M1B 1.08E-02 6.04E-03 1.73E-02 9.41E-03 5.37E-03 1.62E-02 4.37E-02 4.28E-02 2.30E-01 5.22E-02 5.02E-02 1.91E-01 5.96E-02 5.71E-02 1.21E-01 4.68E-02 4.44E-02 7.73E-02 3.24E-02 2.95E-02 5.21E-02 2.43E-02 2.21E-02 3.76E-02 1.91E-02 1.58E-02 2.78E-02 1.55E-02 1.28E-02 2.22E-02 1.27E-02 ICRP 26 M w/o B 6.41E-03 4.84E-03 1.05E-02 5.31E-03 4.26E-03 9.74E-03 3.50E-02 3.47E-02 1.41E-01 4.50E-02 4.38E-02 1.26E-01 4.41E-02 4.24E-02 8.22E-02 3.22E-02 3.07E-02 5.46E-02 2.08E-02 1.88E-02 3.72E-02 1.49E-02 1.38E-02 2.70E-02 1.20E-02 9.59E-03 2.02E-02 9.62E-03 7.83E-03 1.60E-02 7.90E-03 Female 8.21E-03 3.58E-03 1.44E-02 7.54E-03 3.50E-03 1.37E-02 2.95E-02 2.92E-02 1.94E-01 3.11E-02 2.94E-02 1.47E-01 4.24E-02 4.08E-02 9.24E-02 3.46E-02 3.26E-02 5.88E-02 2.29E-02 2.06E-02 3.94E-02 1.76E-02 1.52E-02 2.92E-02 1.37E-02 1.15E-02 2.16E-02 1.14E-02 9.27E-03 1.76E-02 9.31E-03 MwB 6.50E-03 4.30E-03 1.08E-02 5.64E-03 3.79E-03 1.01E-02 3.03E-02 3.15E-02 1.58E-01 3.83E-02 3.86E-02 1.33E-01 3.77E-02 3.70E-02 8.45E-02 2.85E-02 2.74E-02 5.44E-02 2.01E-02 1.83E-02 3.59E-02 1.51E-02 1.38E-02 2.57E-02 1.21E-02 9.80E-03 1.92E-02 9.81E-03 8.00E-03 1.51E-02 8.16E-03 ICRP 60 M w/o B 5.04E-03 3.90E-03 8.57E-03 4.27E-03 3.42E-03 7.96E-03 2.74E-02 2.87E-02 1.28E-01 3.59E-02 3.65E-02 1.11E-01 3.26E-02 3.21E-02 7.16E-02 2.36E-02 2.29E-02 4.68E-02 1.62E-02 1.47E-02 3.09E-02 1.20E-02 1.10E-02 2.22E-02 9.69E-03 7.73E-03 1.66E-02 7.85E-03 6.36E-03 1.30E-02 6.55E-03 Female 4.44E-03 2.33E-03 8.52E-03 4.14E-03 2.29E-03 8.15E-03 1.89E-02 2.06E-02 1.29E-01 2.14E-02 2.19E-02 9.73E-02 2.39E-02 2.39E-02 6.17E-02 1.88E-02 1.80E-02 3.96E-02 1.25E-02 1.12E-02 2.58E-02 9.74E-03 8.31E-03 1.90E-02 7.77E-03 6.39E-03 1.41E-02 6.56E-03 5.20E-03 1.14E-02 5.43E-03 187 Configuration M w B 1V20S1B 1V20V1B 1V35M1B 1V35S1B 1V35V1B 1V50M1B 1V50S1B 1V50V1B 1.02E-02 1.82E-02 1.07E-02 8.53E-03 1.55E-02 9.62E-03 7.77E-03 1.39E-02 ICRP 26 M w/o B 6.28E-03 1.32E-02 6.73E-03 5.41E-03 1.12E-02 5.81E-03 4.92E-03 9.95E-03 Female 7.40E-03 1.45E-02 7.92E-03 6.01E-03 1.24E-02 7.36E-03 5.54E-03 1.13E-02 MwB 6.42E-03 1.24E-02 6.93E-03 5.39E-03 1.06E-02 6.11E-03 4.98E-03 9.48E-03 ICRP 60 M w/o B 5.13E-03 1.08E-02 5.60E-03 4.35E-03 9.21E-03 4.84E-03 4.03E-03 8.15E-03 Female 4.23E-03 9.45E-03 4.68E-03 3.37E-03 8.18E-03 4.30E-03 3.20E-03 7.40E-03 188 Table E-4: Summary Whole Body Dose using ANSI 1977 at 3 Ft ICRP 26 M w/o B Female 9.47E-03 4.22E-03 7.40E-03 8.01E-03 4.31E-03 6.92E-03 7.06E-03 5.14E-03 6.33E-03 5.31E-03 3.87E-03 6.53E-03 4.31E-03 4.89E-03 6.21E-03 3.71E-03 4.72E-03 5.56E-03 3.17E-03 4.10E-03 4.74E-03 2.58E-03 3.30E-03 3.87E-03 2.36E-03 2.60E-03 3.49E-03 2.11E-03 2.20E-03 3.22E-03 8.07E-03 3.24E-03 6.25E-03 6.72E-03 3.31E-03 5.72E-03 5.22E-03 4.32E-03 4.88E-03 4.30E-03 3.87E-03 5.52E-03 3.56E-03 5.42E-03 5.57E-03 2.93E-03 5.98E-03 5.15E-03 2.58E-03 4.72E-03 4.72E-03 2.23E-03 3.88E-03 4.40E-03 2.07E-03 3.27E-03 4.09E-03 1.87E-03 3.03E-03 4.01E-03 Configuration 1M06M3Z 1M06S3Z 1M06V3Z 1M15M3Z 1M15S3Z 1M15V3Z 1M30M3Z 1M30S3Z 1M30V3Z 1M45M3Z 1M45S3Z 1M45V3Z 1M60M3Z 1M60S3Z 1M60V3Z 1M75M3Z 1M75S3Z 1M75V3Z 1M90M3Z 1M90S3Z 1M90V3Z 1M05M3Z 1M05S3Z 1M05V3Z 1M20M3Z 1M20S3Z 1M20V3Z 1M35M3Z 1M35S3Z 1M35V3Z MwB 1.20E-02 5.23E-03 9.24E-03 1.00E-02 5.33E-03 8.64E-03 8.58E-03 6.13E-03 7.72E-03 6.62E-03 5.50E-03 7.70E-03 5.44E-03 6.81E-03 7.30E-03 4.65E-03 7.13E-03 6.67E-03 3.98E-03 5.64E-03 6.09E-03 3.33E-03 4.68E-03 5.38E-03 3.05E-03 4.12E-03 4.95E-03 2.74E-03 3.70E-03 4.73E-03 MwB 9.39E-03 3.98E-03 7.20E-03 7.84E-03 4.05E-03 6.62E-03 6.51E-03 4.98E-03 5.85E-03 4.97E-03 3.71E-03 6.46E-03 4.16E-03 4.78E-03 5.63E-03 3.48E-03 5.24E-03 4.95E-03 3.01E-03 4.36E-03 4.41E-03 2.51E-03 3.64E-03 3.80E-03 2.30E-03 3.02E-03 3.48E-03 2.03E-03 2.50E-03 3.22E-03 ICRP 60 M w/o B 8.56E-03 3.65E-03 6.58E-03 7.17E-03 3.71E-03 6.04E-03 6.00E-03 4.65E-03 5.38E-03 4.54E-03 3.17E-03 6.07E-03 3.78E-03 4.14E-03 5.26E-03 3.17E-03 4.43E-03 4.58E-03 2.74E-03 3.84E-03 3.96E-03 2.27E-03 3.18E-03 3.30E-03 2.07E-03 2.51E-03 2.99E-03 1.81E-03 2.00E-03 2.72E-03 Female 6.28E-03 2.40E-03 4.81E-03 5.21E-03 2.44E-03 4.28E-03 3.83E-03 3.53E-03 3.58E-03 3.12E-03 2.41E-03 4.72E-03 2.65E-03 3.67E-03 4.24E-03 2.10E-03 4.31E-03 3.73E-03 1.89E-03 3.62E-03 3.32E-03 1.64E-03 3.00E-03 3.02E-03 1.52E-03 2.34E-03 2.79E-03 1.33E-03 1.97E-03 2.65E-03 189 Configuration 1M50M3Z 1M50S3Z 1M50V3Z 1S06M3Z 1S06S3Z 1S06V3Z 1S15M3Z 1S15S3Z 1S15V3Z 1S30M3Z 1S30S3Z 1S30V3Z 1S45M3Z 1S45S3Z 1S45V3Z 1S60M3Z 1S60S3Z 1S60V3Z 1S75M3Z 1S75S3Z 1S75V3Z 1S90M3Z 1S90S3Z 1S90V3Z 1S05M3Z 1S05S3Z 1S05V3Z 1S20M3Z 1S20S3Z 1S20V3Z 1S35M3Z MwB 2.61E-03 3.71E-03 4.49E-03 5.76E-03 1.04E-02 9.21E-03 5.67E-03 8.50E-03 8.91E-03 5.82E-03 6.96E-03 8.94E-03 8.17E-03 5.38E-03 8.12E-03 9.01E-03 4.40E-03 7.47E-03 7.33E-03 3.52E-03 6.94E-03 5.68E-03 3.01E-03 5.95E-03 4.36E-03 2.44E-03 5.81E-03 4.26E-03 2.08E-03 5.39E-03 4.05E-03 ICRP 26 M w/o B Female 1.98E-03 2.29E-03 2.96E-03 4.56E-03 8.25E-03 7.21E-03 4.55E-03 6.86E-03 7.15E-03 4.61E-03 5.77E-03 7.48E-03 5.95E-03 4.49E-03 6.86E-03 5.86E-03 3.66E-03 6.33E-03 5.28E-03 2.86E-03 5.50E-03 4.03E-03 2.44E-03 4.34E-03 2.64E-03 1.97E-03 4.04E-03 2.58E-03 1.61E-03 3.53E-03 2.63E-03 1.85E-03 3.05E-03 3.90E-03 3.83E-03 6.91E-03 6.51E-03 3.83E-03 5.66E-03 5.79E-03 4.02E-03 4.18E-03 6.04E-03 6.43E-03 3.26E-03 5.96E-03 7.66E-03 2.63E-03 5.82E-03 6.01E-03 2.22E-03 5.61E-03 4.70E-03 1.95E-03 4.92E-03 3.63E-03 1.59E-03 4.72E-03 3.52E-03 1.51E-03 4.53E-03 3.53E-03 MwB 1.92E-03 2.43E-03 3.06E-03 4.24E-03 8.24E-03 7.15E-03 4.24E-03 6.57E-03 6.75E-03 4.16E-03 5.25E-03 7.08E-03 6.02E-03 4.02E-03 6.66E-03 6.38E-03 3.29E-03 5.73E-03 5.48E-03 2.58E-03 5.01E-03 4.04E-03 2.23E-03 4.18E-03 2.86E-03 1.82E-03 4.02E-03 2.75E-03 1.52E-03 3.66E-03 2.63E-03 ICRP 60 M w/o B 1.71E-03 1.96E-03 2.55E-03 3.84E-03 7.54E-03 6.49E-03 3.87E-03 6.02E-03 6.16E-03 3.76E-03 4.85E-03 6.59E-03 5.27E-03 3.72E-03 6.23E-03 5.33E-03 3.04E-03 5.35E-03 4.80E-03 2.36E-03 4.53E-03 3.48E-03 2.04E-03 3.65E-03 2.28E-03 1.66E-03 3.43E-03 2.20E-03 1.36E-03 3.04E-03 2.16E-03 Female 1.31E-03 1.90E-03 2.58E-03 2.70E-03 5.48E-03 5.00E-03 2.77E-03 4.30E-03 4.25E-03 2.73E-03 3.02E-03 4.76E-03 4.62E-03 2.32E-03 4.93E-03 5.31E-03 1.87E-03 4.41E-03 4.43E-03 1.54E-03 3.95E-03 3.25E-03 1.38E-03 3.36E-03 2.27E-03 1.14E-03 3.16E-03 2.17E-03 1.06E-03 2.97E-03 2.22E-03 190 Configuration 1S35S3Z 1S35V3Z 1S50M3Z 1S50S3Z 1S50V3Z 1V06M3Z 1V06S3Z 1V06V3Z 1V15M3Z 1V15S3Z 1V15V3Z 1V30M3Z 1V30S3Z 1V30V3Z 1V45M3Z 1V45S3Z 1V45V3Z 1V60M3Z 1V60S3Z 1V60V3Z 1V75M3Z 1V75S3Z 1V75V3Z 1V90M3Z 1V90S3Z 1V90V3Z 1V05M3Z 1V05S3Z 1V05V3Z 1V20M3Z 1V20S3Z MwB 2.02E-03 4.79E-03 3.89E-03 1.67E-03 4.38E-03 2.02E-02 1.98E-02 2.53E-02 1.29E-02 1.36E-02 2.15E-02 7.40E-03 7.04E-03 1.79E-02 7.59E-03 7.10E-03 1.43E-02 7.11E-03 6.63E-03 1.19E-02 6.50E-03 6.32E-03 9.88E-03 5.80E-03 5.52E-03 8.28E-03 5.32E-03 5.17E-03 6.85E-03 4.97E-03 4.46E-03 ICRP 26 M w/o B Female 1.59E-03 2.91E-03 2.64E-03 1.31E-03 2.52E-03 1.32E-02 1.30E-02 1.68E-02 8.87E-03 9.70E-03 1.43E-02 6.07E-03 5.77E-03 1.22E-02 6.40E-03 6.04E-03 9.59E-03 6.09E-03 5.69E-03 8.03E-03 5.44E-03 5.37E-03 6.53E-03 4.48E-03 4.34E-03 5.50E-03 3.90E-03 3.82E-03 4.48E-03 3.56E-03 3.17E-03 1.29E-03 4.07E-03 3.38E-03 1.09E-03 3.81E-03 1.76E-02 1.73E-02 2.18E-02 1.02E-02 1.06E-02 1.87E-02 4.78E-03 4.57E-03 1.46E-02 5.46E-03 5.08E-03 1.20E-02 5.25E-03 4.86E-03 9.99E-03 5.11E-03 4.82E-03 8.35E-03 4.74E-03 4.36E-03 6.84E-03 4.36E-03 4.10E-03 5.85E-03 4.04E-03 3.75E-03 MwB 1.48E-03 3.15E-03 2.58E-03 1.22E-03 2.84E-03 1.48E-02 1.52E-02 1.91E-02 9.12E-03 1.10E-02 1.62E-02 5.53E-03 5.28E-03 1.33E-02 6.27E-03 5.94E-03 1.05E-02 5.58E-03 5.10E-03 8.79E-03 4.72E-03 4.57E-03 7.17E-03 4.18E-03 3.96E-03 6.08E-03 3.77E-03 3.69E-03 4.98E-03 3.49E-03 3.04E-03 ICRP 60 M w/o B 1.34E-03 2.52E-03 2.16E-03 1.10E-03 2.22E-03 1.24E-02 1.29E-02 1.63E-02 7.80E-03 9.65E-03 1.38E-02 5.09E-03 4.86E-03 1.15E-02 5.87E-03 5.58E-03 8.97E-03 5.24E-03 4.78E-03 7.50E-03 4.37E-03 4.25E-03 6.05E-03 3.74E-03 3.57E-03 5.15E-03 3.30E-03 3.24E-03 4.19E-03 3.03E-03 2.61E-03 Female 9.02E-04 2.58E-03 2.17E-03 7.53E-04 2.39E-03 1.26E-02 1.31E-02 1.63E-02 6.97E-03 8.55E-03 1.39E-02 3.44E-03 3.31E-03 1.07E-02 4.57E-03 4.33E-03 8.71E-03 4.09E-03 3.69E-03 7.26E-03 3.61E-03 3.37E-03 5.95E-03 3.34E-03 3.03E-03 4.93E-03 3.01E-03 2.84E-03 4.18E-03 2.75E-03 2.47E-03 191 Configuration 1V20V3Z 1V35M3Z 1V35S3Z 1V35V3Z 1V50M3Z 1V50S3Z 1V50V3Z MwB 5.96E-03 4.44E-03 4.08E-03 5.31E-03 3.99E-03 3.68E-03 4.77E-03 ICRP 26 M w/o B Female 3.97E-03 3.16E-03 2.90E-03 3.64E-03 2.80E-03 2.58E-03 3.21E-03 5.08E-03 3.56E-03 3.35E-03 4.40E-03 3.28E-03 2.99E-03 4.09E-03 MwB 4.40E-03 3.12E-03 2.83E-03 3.97E-03 2.76E-03 2.48E-03 3.55E-03 ICRP 60 M w/o B 3.73E-03 2.70E-03 2.43E-03 3.42E-03 2.36E-03 2.11E-03 3.02E-03 Female 3.69E-03 2.41E-03 2.24E-03 3.24E-03 2.19E-03 1.93E-03 3.01E-03 192 Table E-5: Summary Whole Body Dose using ANSI 1991 at 3 Ft ICRP 26 M w/o B Female 2.08E-02 9.29E-03 1.63E-02 1.84E-02 9.51E-03 1.46E-02 1.61E-02 1.13E-02 1.35E-02 1.24E-02 8.54E-03 1.37E-02 9.95E-03 1.07E-02 1.31E-02 8.69E-03 1.03E-02 1.21E-02 7.09E-03 8.94E-03 1.01E-02 6.00E-03 7.24E-03 8.12E-03 5.49E-03 5.73E-03 7.32E-03 4.71E-03 4.87E-03 1.77E-02 7.12E-03 1.37E-02 1.52E-02 7.29E-03 1.24E-02 1.21E-02 9.44E-03 1.03E-02 9.85E-03 8.45E-03 1.15E-02 8.15E-03 1.18E-02 1.16E-02 6.86E-03 1.30E-02 1.09E-02 5.79E-03 1.03E-02 1.01E-02 5.23E-03 8.46E-03 9.41E-03 4.85E-03 7.14E-03 8.70E-03 4.43E-03 6.63E-03 Configuration 1M06M3A 1M06S3A 1M06V3A 1M15M3A 1M15S3A 1M15V3A 1M30M3A 1M30S3A 1M30V3A 1M45M3A 1M45S3A 1M45V3A 1M60M3A 1M60S3A 1M60V3A 1M75M3A 1M75S3A 1M75V3A 1M90M3A 1M90S3A 1M90V3A 1M05M3A 1M05S3A 1M05V3A 1M20M3A 1M20S3A 1M20V3A 1M35M3A 1M35S3A MwB 2.63E-02 1.15E-02 2.03E-02 2.30E-02 1.18E-02 1.83E-02 1.97E-02 1.34E-02 1.64E-02 1.53E-02 1.21E-02 1.62E-02 1.25E-02 1.49E-02 1.53E-02 1.08E-02 1.56E-02 1.44E-02 8.96E-03 1.23E-02 1.29E-02 7.76E-03 1.02E-02 1.13E-02 7.08E-03 9.03E-03 1.04E-02 6.27E-03 8.14E-03 MwB 2.06E-02 8.75E-03 1.58E-02 1.77E-02 8.91E-03 1.42E-02 1.47E-02 1.09E-02 1.25E-02 1.14E-02 8.16E-03 1.35E-02 9.47E-03 1.05E-02 1.19E-02 8.04E-03 1.14E-02 1.07E-02 6.83E-03 9.50E-03 9.39E-03 5.83E-03 7.97E-03 8.00E-03 5.24E-03 6.62E-03 7.29E-03 4.59E-03 5.50E-03 ICRP 60 M w/o B 1.88E-02 8.01E-03 1.44E-02 1.62E-02 8.17E-03 1.29E-02 1.35E-02 1.02E-02 1.15E-02 1.04E-02 6.98E-03 1.27E-02 8.62E-03 9.07E-03 1.12E-02 7.32E-03 9.70E-03 9.91E-03 6.21E-03 8.38E-03 8.44E-03 5.25E-03 6.97E-03 6.95E-03 4.71E-03 5.52E-03 6.28E-03 4.07E-03 4.42E-03 Female 1.37E-02 5.25E-03 1.05E-02 1.15E-02 5.35E-03 9.45E-03 8.62E-03 7.69E-03 7.65E-03 7.00E-03 5.27E-03 9.77E-03 5.99E-03 7.99E-03 8.94E-03 4.86E-03 9.37E-03 7.91E-03 4.30E-03 7.89E-03 7.11E-03 3.81E-03 6.55E-03 6.52E-03 3.45E-03 5.11E-03 5.97E-03 3.12E-03 4.30E-03 193 Configuration 1M35V3A 1M50M3A 1M50S3A 1M50V3A 1S06M3A 1S06S3A 1S06V3A 1S15M3A 1S15S3A 1S15V3A 1S30M3A 1S30S3A 1S30V3A 1S45M3A 1S45S3A 1S45V3A 1S60M3A 1S60S3A 1S60V3A 1S75M3A 1S75S3A 1S75V3A 1S90M3A 1S90S3A 1S90V3A 1S05M3A 1S05S3A 1S05V3A 1S20M3A 1S20S3A 1S20V3A MwB 1.01E-02 5.81E-03 8.14E-03 9.87E-03 1.27E-02 2.27E-02 2.02E-02 1.30E-02 1.87E-02 1.84E-02 1.30E-02 1.53E-02 1.91E-02 1.86E-02 1.19E-02 1.70E-02 1.99E-02 9.76E-03 1.64E-02 1.62E-02 7.81E-03 1.52E-02 1.29E-02 6.68E-03 1.30E-02 1.03E-02 5.45E-03 1.24E-02 9.56E-03 4.64E-03 1.12E-02 ICRP 26 M w/o B Female 6.90E-03 4.42E-03 5.03E-03 6.51E-03 1.00E-02 1.81E-02 1.59E-02 1.04E-02 1.51E-02 1.48E-02 1.03E-02 1.27E-02 1.59E-02 1.37E-02 9.93E-03 1.44E-02 1.30E-02 8.11E-03 1.39E-02 1.16E-02 6.34E-03 1.21E-02 9.09E-03 5.42E-03 9.53E-03 6.39E-03 4.40E-03 8.63E-03 5.76E-03 3.59E-03 7.32E-03 8.61E-03 4.09E-03 6.67E-03 8.52E-03 8.42E-03 1.51E-02 1.42E-02 8.71E-03 1.24E-02 1.21E-02 9.03E-03 9.15E-03 1.30E-02 1.46E-02 7.18E-03 1.26E-02 1.70E-02 5.81E-03 1.27E-02 1.34E-02 4.91E-03 1.23E-02 1.05E-02 4.32E-03 1.08E-02 8.17E-03 3.52E-03 1.02E-02 8.06E-03 3.34E-03 9.50E-03 MwB 6.94E-03 4.28E-03 5.34E-03 6.73E-03 9.31E-03 1.80E-02 1.57E-02 9.58E-03 1.44E-02 1.41E-02 9.24E-03 1.15E-02 1.51E-02 1.36E-02 8.86E-03 1.42E-02 1.41E-02 7.28E-03 1.26E-02 1.20E-02 5.71E-03 1.10E-02 9.11E-03 4.94E-03 9.17E-03 6.70E-03 4.05E-03 8.51E-03 6.22E-03 3.37E-03 7.65E-03 ICRP 60 M w/o B 5.88E-03 3.81E-03 4.30E-03 5.61E-03 8.43E-03 1.65E-02 1.42E-02 8.72E-03 1.32E-02 1.29E-02 8.34E-03 1.07E-02 1.41E-02 1.20E-02 8.20E-03 1.33E-02 1.18E-02 6.73E-03 1.17E-02 1.05E-02 5.22E-03 9.93E-03 7.86E-03 4.52E-03 8.00E-03 5.41E-03 3.70E-03 7.27E-03 4.95E-03 3.02E-03 6.34E-03 Female 5.78E-03 2.90E-03 4.16E-03 5.65E-03 5.91E-03 1.19E-02 1.09E-02 6.15E-03 9.37E-03 9.05E-03 6.08E-03 6.60E-03 1.03E-02 1.04E-02 5.09E-03 1.07E-02 1.17E-02 4.12E-03 9.63E-03 9.78E-03 3.39E-03 8.61E-03 7.27E-03 3.05E-03 7.35E-03 5.04E-03 2.51E-03 6.76E-03 5.02E-03 2.33E-03 6.26E-03 194 Configuration 1S35M3A 1S35S3A 1S35V3A 1S50M3A 1S50S3A 1S50V3A 1V06M3A 1V06S3A 1V06V3A 1V15M3A 1V15S3A 1V15V3A 1V30M3A 1V30S3A 1V30V3A 1V45M3A 1V45S3A 1V45V3A 1V60M3A 1V60S3A 1V60V3A 1V75M3A 1V75S3A 1V75V3A 1V90M3A 1V90S3A 1V90V3A 1V05M3A 1V05S3A 1V05V3A 1V20M3A MwB 9.40E-03 4.49E-03 1.04E-02 8.54E-03 3.72E-03 9.62E-03 4.40E-02 4.30E-02 5.50E-02 2.89E-02 2.97E-02 4.68E-02 1.74E-02 1.55E-02 3.89E-02 1.73E-02 1.56E-02 3.10E-02 1.59E-02 1.46E-02 2.59E-02 1.46E-02 1.39E-02 2.15E-02 1.32E-02 1.21E-02 1.80E-02 1.24E-02 1.13E-02 1.50E-02 1.11E-02 ICRP 26 M w/o B Female 6.20E-03 3.54E-03 6.34E-03 5.80E-03 2.93E-03 5.57E-03 2.89E-02 2.83E-02 3.67E-02 2.01E-02 2.12E-02 3.12E-02 1.43E-02 1.27E-02 2.67E-02 1.45E-02 1.33E-02 2.09E-02 1.33E-02 1.25E-02 1.75E-02 1.21E-02 1.18E-02 1.43E-02 1.02E-02 9.53E-03 1.20E-02 9.11E-03 8.40E-03 9.80E-03 7.85E-03 8.09E-03 2.86E-03 8.79E-03 7.40E-03 2.41E-03 8.32E-03 3.80E-02 3.73E-02 4.73E-02 2.25E-02 2.31E-02 4.04E-02 1.08E-02 1.00E-02 3.17E-02 1.23E-02 1.11E-02 2.60E-02 1.20E-02 1.06E-02 2.17E-02 1.15E-02 1.05E-02 1.81E-02 1.05E-02 9.55E-03 1.49E-02 9.94E-03 8.94E-03 1.27E-02 9.14E-03 MwB 6.24E-03 3.29E-03 6.90E-03 5.65E-03 2.71E-03 6.25E-03 3.22E-02 3.30E-02 4.16E-02 2.04E-02 2.39E-02 3.52E-02 1.29E-02 1.16E-02 2.90E-02 1.42E-02 1.30E-02 2.29E-02 1.23E-02 1.12E-02 1.92E-02 1.07E-02 1.00E-02 1.57E-02 9.58E-03 8.69E-03 1.33E-02 8.69E-03 8.12E-03 1.09E-02 7.69E-03 ICRP 60 M w/o B 5.17E-03 2.97E-03 5.56E-03 4.74E-03 2.45E-03 4.90E-03 2.71E-02 2.81E-02 3.55E-02 1.75E-02 2.10E-02 3.00E-02 1.19E-02 1.07E-02 2.49E-02 1.33E-02 1.22E-02 1.96E-02 1.15E-02 1.05E-02 1.64E-02 9.82E-03 9.33E-03 1.32E-02 8.59E-03 7.82E-03 1.12E-02 7.61E-03 7.14E-03 9.16E-03 6.62E-03 Female 5.19E-03 1.99E-03 5.65E-03 4.74E-03 1.66E-03 5.21E-03 2.74E-02 2.85E-02 3.54E-02 1.53E-02 1.86E-02 3.01E-02 7.69E-03 7.22E-03 2.33E-02 1.02E-02 9.41E-03 1.89E-02 9.22E-03 8.04E-03 1.58E-02 8.17E-03 7.37E-03 1.29E-02 7.45E-03 6.63E-03 1.07E-02 6.76E-03 6.20E-03 9.09E-03 6.15E-03 195 Configuration 1V20S3A 1V20V3A 1V35M3A 1V35S3A 1V35V3A 1V50M3A 1V50S3A 1V50V3A MwB 9.79E-03 1.30E-02 9.80E-03 8.97E-03 1.16E-02 8.76E-03 8.07E-03 1.04E-02 ICRP 26 M w/o B Female 6.98E-03 8.69E-03 6.89E-03 6.40E-03 8.01E-03 6.15E-03 5.66E-03 7.02E-03 8.18E-03 1.10E-02 7.98E-03 7.32E-03 9.58E-03 7.18E-03 6.54E-03 8.92E-03 MwB 6.68E-03 9.62E-03 6.84E-03 6.22E-03 8.71E-03 6.07E-03 5.44E-03 7.75E-03 ICRP 60 M w/o B 5.75E-03 8.17E-03 5.86E-03 5.36E-03 7.50E-03 5.20E-03 4.64E-03 6.62E-03 Female 5.40E-03 8.03E-03 5.38E-03 4.90E-03 7.06E-03 4.80E-03 4.22E-03 6.55E-03 196 Table E-6: Summary Whole Body Dose using ICRP-74 at 3 Ft ICRP 26 M w/o B 1.78E-02 7.96E-03 1.39E-02 1.58E-02 8.15E-03 1.25E-02 1.38E-02 9.66E-03 1.15E-02 1.06E-02 7.33E-03 1.17E-02 8.53E-03 9.16E-03 1.12E-02 7.46E-03 8.84E-03 1.04E-02 6.09E-03 7.63E-03 8.64E-03 5.15E-03 6.19E-03 6.95E-03 4.71E-03 4.91E-03 6.26E-03 4.04E-03 4.17E-03 Configuration M w B 1M06M3Z 1M06S3Z 1M06V3Z 1M15M3Z 1M15S3Z 1M15V3Z 1M30M3Z 1M30S3Z 1M30V3Z 1M45M3Z 1M45S3Z 1M45V3Z 1M60M3Z 1M60S3Z 1M60V3Z 1M75M3Z 1M75S3Z 1M75V3Z 1M90M3Z 1M90S3Z 1M90V3Z 1M05M3Z 1M05S3Z 1M05V3Z 1M20M3Z 1M20S3Z 1M20V3Z 1M35M3Z 1M35S3Z 2.24E-02 9.86E-03 1.73E-02 1.96E-02 1.01E-02 1.56E-02 1.69E-02 1.15E-02 1.40E-02 1.31E-02 1.03E-02 1.38E-02 1.07E-02 1.27E-02 1.30E-02 9.30E-03 1.33E-02 1.23E-02 7.69E-03 1.05E-02 1.11E-02 6.65E-03 8.74E-03 9.62E-03 6.07E-03 7.73E-03 8.84E-03 5.39E-03 6.96E-03 Female 1.50E-02 6.08E-03 1.17E-02 1.29E-02 6.22E-03 1.05E-02 1.03E-02 8.05E-03 8.83E-03 8.41E-03 7.22E-03 9.79E-03 6.97E-03 1.01E-02 9.86E-03 5.87E-03 1.11E-02 9.33E-03 4.95E-03 8.77E-03 8.59E-03 4.47E-03 7.20E-03 8.03E-03 4.15E-03 6.10E-03 7.43E-03 3.80E-03 5.66E-03 MwB 1.76E-02 7.49E-03 1.35E-02 1.51E-02 7.63E-03 1.21E-02 1.26E-02 9.31E-03 1.07E-02 9.74E-03 6.99E-03 1.15E-02 8.11E-03 8.93E-03 1.02E-02 6.89E-03 9.76E-03 9.11E-03 5.86E-03 8.11E-03 8.03E-03 5.00E-03 6.81E-03 6.83E-03 4.48E-03 5.66E-03 6.22E-03 3.94E-03 4.70E-03 ICRP 60 M w/o B 1.60E-02 6.86E-03 1.23E-02 1.39E-02 6.99E-03 1.10E-02 1.16E-02 8.70E-03 9.83E-03 8.89E-03 5.98E-03 1.08E-02 7.38E-03 7.74E-03 9.55E-03 6.28E-03 8.28E-03 8.47E-03 5.32E-03 7.15E-03 7.22E-03 4.50E-03 5.95E-03 5.94E-03 4.03E-03 4.72E-03 5.36E-03 3.49E-03 3.78E-03 Female 1.17E-02 4.47E-03 8.93E-03 9.78E-03 4.55E-03 8.03E-03 7.34E-03 6.55E-03 6.51E-03 5.96E-03 4.49E-03 8.32E-03 5.12E-03 6.81E-03 7.62E-03 4.15E-03 7.97E-03 6.74E-03 3.67E-03 6.72E-03 6.06E-03 3.26E-03 5.58E-03 5.56E-03 2.95E-03 4.35E-03 5.09E-03 2.67E-03 3.67E-03 197 Configuration M w B 1M35V3Z 1M50M3Z 1M50S3Z 1M50V3Z 1S06M3Z 1S06S3Z 1S06V3Z 1S15M3Z 1S15S3Z 1S15V3Z 1S30M3Z 1S30S3Z 1S30V3Z 1S45M3Z 1S45S3Z 1S45V3Z 1S60M3Z 1S60S3Z 1S60V3Z 1S75M3Z 1S75S3Z 1S75V3Z 1S90M3Z 1S90S3Z 1S90V3Z 1S05M3Z 1S05S3Z 1S05V3Z 1S20M3Z 1S20S3Z 1S20V3Z 8.60E-03 4.98E-03 6.97E-03 8.44E-03 1.08E-02 1.94E-02 1.73E-02 1.11E-02 1.59E-02 1.57E-02 1.11E-02 1.31E-02 1.63E-02 1.59E-02 1.02E-02 1.46E-02 1.70E-02 8.38E-03 1.40E-02 1.38E-02 6.70E-03 1.30E-02 1.10E-02 5.74E-03 1.11E-02 8.77E-03 4.67E-03 1.05E-02 8.18E-03 3.98E-03 9.60E-03 ICRP 26 M w/o B 5.90E-03 3.79E-03 4.31E-03 5.57E-03 8.58E-03 1.54E-02 1.36E-02 8.90E-03 1.29E-02 1.26E-02 8.80E-03 1.09E-02 1.36E-02 1.17E-02 8.52E-03 1.23E-02 1.11E-02 6.97E-03 1.19E-02 9.89E-03 5.45E-03 1.03E-02 7.79E-03 4.66E-03 8.15E-03 5.48E-03 3.77E-03 7.37E-03 4.94E-03 3.09E-03 6.26E-03 Female 7.35E-03 3.50E-03 5.70E-03 7.28E-03 7.19E-03 1.28E-02 1.21E-02 7.44E-03 1.05E-02 1.03E-02 7.72E-03 7.81E-03 1.11E-02 1.24E-02 6.14E-03 1.08E-02 1.45E-02 4.97E-03 1.09E-02 1.14E-02 4.20E-03 1.05E-02 9.00E-03 3.70E-03 9.18E-03 6.98E-03 3.01E-03 8.67E-03 6.89E-03 2.87E-03 8.11E-03 MwB 5.93E-03 3.66E-03 4.57E-03 5.75E-03 7.96E-03 1.54E-02 1.34E-02 8.18E-03 1.23E-02 1.20E-02 7.90E-03 9.87E-03 1.29E-02 1.16E-02 7.58E-03 1.21E-02 1.20E-02 6.24E-03 1.07E-02 1.03E-02 4.89E-03 9.38E-03 7.80E-03 4.24E-03 7.84E-03 5.74E-03 3.47E-03 7.26E-03 5.32E-03 2.89E-03 6.53E-03 ICRP 60 M w/o B 5.03E-03 3.26E-03 3.69E-03 4.79E-03 7.20E-03 1.41E-02 1.21E-02 7.44E-03 1.13E-02 1.10E-02 7.13E-03 9.12E-03 1.20E-02 1.02E-02 7.02E-03 1.14E-02 1.01E-02 5.77E-03 1.00E-02 8.94E-03 4.48E-03 8.49E-03 6.73E-03 3.88E-03 6.84E-03 4.64E-03 3.17E-03 6.20E-03 4.24E-03 2.59E-03 5.41E-03 Female 4.93E-03 2.48E-03 3.56E-03 4.82E-03 5.04E-03 1.01E-02 9.27E-03 5.24E-03 7.96E-03 7.70E-03 5.19E-03 5.61E-03 8.78E-03 8.85E-03 4.34E-03 9.10E-03 1.00E-02 3.52E-03 8.21E-03 8.34E-03 2.90E-03 7.34E-03 6.20E-03 2.61E-03 6.27E-03 4.30E-03 2.14E-03 5.76E-03 4.29E-03 2.00E-03 5.33E-03 198 Configuration M w B 1S35M3Z 1S35S3Z 1S35V3Z 1S50M3Z 1S50S3Z 1S50V3Z 1V06M3Z 1V06S3Z 1V06V3Z 1V15M3Z 1V15S3Z 1V15V3Z 1V30M3Z 1V30S3Z 1V30V3Z 1V45M3Z 1V45S3Z 1V45V3Z 1V60M3Z 1V60S3Z 1V60V3Z 1V75M3Z 1V75S3Z 1V75V3Z 1V90M3Z 1V90S3Z 1V90V3Z 1V05M3Z 1V05S3Z 1V05V3Z 1V20M3Z 8.03E-03 3.85E-03 8.85E-03 7.30E-03 3.19E-03 8.22E-03 3.75E-02 3.66E-02 4.69E-02 2.47E-02 2.54E-02 3.98E-02 1.49E-02 1.33E-02 3.31E-02 1.48E-02 1.33E-02 2.65E-02 1.36E-02 1.24E-02 2.21E-02 1.25E-02 1.18E-02 1.84E-02 1.13E-02 1.04E-02 1.54E-02 1.06E-02 9.70E-03 1.28E-02 9.47E-03 ICRP 26 M w/o B 5.30E-03 3.04E-03 5.43E-03 4.96E-03 2.52E-03 4.77E-03 2.46E-02 2.41E-02 3.12E-02 1.72E-02 1.81E-02 2.66E-02 1.22E-02 1.09E-02 2.27E-02 1.24E-02 1.13E-02 1.79E-02 1.14E-02 1.07E-02 1.50E-02 1.04E-02 1.01E-02 1.22E-02 8.73E-03 8.14E-03 1.03E-02 7.81E-03 7.19E-03 8.36E-03 6.73E-03 Female 6.90E-03 2.45E-03 7.50E-03 6.32E-03 2.06E-03 7.10E-03 3.24E-02 3.17E-02 4.02E-02 1.92E-02 1.96E-02 3.44E-02 9.27E-03 8.56E-03 2.70E-02 1.05E-02 9.47E-03 2.21E-02 1.02E-02 9.06E-03 1.85E-02 9.86E-03 8.99E-03 1.55E-02 8.98E-03 8.14E-03 1.27E-02 8.49E-03 7.63E-03 1.08E-02 7.79E-03 MwB 5.33E-03 2.83E-03 5.90E-03 4.83E-03 2.33E-03 5.34E-03 2.74E-02 2.81E-02 3.54E-02 1.74E-02 2.04E-02 2.99E-02 1.11E-02 9.92E-03 2.47E-02 1.21E-02 1.11E-02 1.96E-02 1.06E-02 9.55E-03 1.63E-02 9.11E-03 8.56E-03 1.34E-02 8.20E-03 7.42E-03 1.13E-02 7.43E-03 6.94E-03 9.28E-03 6.58E-03 ICRP 60 M w/o B 4.42E-03 2.55E-03 4.76E-03 4.05E-03 2.10E-03 4.19E-03 2.31E-02 2.39E-02 3.02E-02 1.49E-02 1.79E-02 2.55E-02 1.02E-02 9.12E-03 2.13E-02 1.13E-02 1.04E-02 1.67E-02 9.83E-03 8.96E-03 1.40E-02 8.39E-03 7.97E-03 1.13E-02 7.35E-03 6.68E-03 9.60E-03 6.51E-03 6.10E-03 7.81E-03 5.67E-03 Female 4.43E-03 1.70E-03 4.82E-03 4.04E-03 1.42E-03 4.44E-03 2.33E-02 2.42E-02 3.01E-02 1.30E-02 1.58E-02 2.56E-02 6.55E-03 6.15E-03 1.98E-02 8.69E-03 8.01E-03 1.61E-02 7.85E-03 6.85E-03 1.34E-02 6.97E-03 6.28E-03 1.10E-02 6.36E-03 5.65E-03 9.12E-03 5.77E-03 5.29E-03 7.74E-03 5.24E-03 199 Configuration M w B 1V20S3Z 1V20V3Z 1V35M3Z 1V35S3Z 1V35V3Z 1V50M3Z 1V50S3Z 1V50V3Z 8.36E-03 1.11E-02 8.38E-03 7.67E-03 9.93E-03 7.49E-03 6.90E-03 8.90E-03 ICRP 26 M w/o B 5.96E-03 7.42E-03 5.89E-03 5.48E-03 6.84E-03 5.26E-03 4.85E-03 6.00E-03 Female 6.98E-03 9.41E-03 6.81E-03 6.25E-03 8.17E-03 6.13E-03 5.58E-03 7.60E-03 MwB 5.71E-03 8.20E-03 5.85E-03 5.32E-03 7.43E-03 5.18E-03 4.66E-03 6.62E-03 ICRP 60 M w/o B 4.91E-03 6.97E-03 5.02E-03 4.59E-03 6.40E-03 4.44E-03 3.97E-03 5.65E-03 Female 4.60E-03 6.84E-03 4.59E-03 4.18E-03 6.02E-03 4.10E-03 3.60E-03 5.58E-03 200 Appendix F: Comparison Of Different Conversion Factors Using Dosimeter Reference Position 201 APPENDIX F.1: COMPARISON AT 1 FOOT Table F.1-1: MxxM1 MxxM1 Distance ANSI 1977 ANSI 1991 M06M1 6 1.55E-01 8.16E-02 M15M1 15 1.17E-01 6.13E-02 M30M1 30 7.54E-02 3.91E-02 M45M1 45 5.03E-02 2.59E-02 M60M1 60 3.87E-02 1.97E-02 M75M1 75 3.06E-02 1.54E-02 M90M1 90 2.40E-02 1.19E-02 M05M1 105 1.99E-02 9.78E-03 M20M1 120 1.64E-02 8.16E-03 M35M1 135 1.44E-02 7.06E-03 M50M1 150 1.33E-02 6.74E-03 Table F.1-2: SxxM1 SxxM1 Distance ANSI 1977 ANSI 1991 S06M1 6 1.92E-02 9.48E-03 S15M1 15 3.33E-02 1.66E-02 S30M1 30 4.62E-02 2.41E-02 S45M1 45 8.23E-02 4.35E-02 S60M1 60 5.42E-02 2.81E-02 S75M1 75 3.33E-02 1.68E-02 S90M1 90 2.12E-02 1.04E-02 S05M1 105 1.51E-02 7.33E-03 S20M1 120 1.25E-02 6.13E-03 S35M1 135 1.15E-02 5.57E-03 S50M1 150 1.03E-02 4.80E-03 ICRP 74 1.81E-02 3.15E-02 4.44E-02 7.94E-02 5.20E-02 3.17E-02 1.99E-02 1.41E-02 1.18E-02 1.08E-02 9.71E-03 ICRP 74 1.50E-01 1.13E-01 7.28E-02 4.84E-02 3.70E-02 2.91E-02 2.27E-02 1.87E-02 1.56E-02 1.36E-02 1.25E-02 202 Table F.1-3: VxxM1 VxxM1 Distance ANSI 1977 ANSI 1991 V06M1 6 4.52E-02 2.25E-02 V15M1 15 5.72E-02 2.98E-02 V30M1 30 5.81E-02 2.98E-02 V45M1 45 3.70E-02 1.84E-02 V60M1 60 3.03E-02 1.50E-02 V75M1 75 2.51E-02 1.24E-02 V90M1 90 2.05E-02 1.03E-02 V05M1 105 1.71E-02 8.41E-03 V20M1 120 1.44E-02 7.13E-03 V35M1 135 1.24E-02 6.11E-03 V50M1 150 1.15E-02 5.47E-03 ICRP 74 4.27E-02 5.51E-02 5.56E-02 3.51E-02 2.87E-02 2.37E-02 1.96E-02 1.61E-02 1.37E-02 1.17E-02 1.09E-02 Table F.1-4: MxxS1 MxxS1 Distance ANSI 1977 ANSI 1991 M06S1 6 1.15E-02 5.50E-03 M15S1 15 3.89E-02 2.01E-02 M30S1 30 2.28E-02 1.18E-02 M45S1 45 6.54E-02 3.55E-02 M60S1 60 4.86E-02 2.53E-02 M75S1 75 2.85E-02 1.49E-02 M90S1 90 1.80E-02 9.24E-03 M05S1 105 1.28E-02 5.88E-03 M20S1 120 1.02E-02 4.45E-03 M35S1 135 8.29E-03 4.07E-03 M50S1 150 7.37E-03 3.36E-03 ICRP 74 1.07E-02 3.79E-02 2.20E-02 6.39E-02 4.70E-02 2.75E-02 1.72E-02 1.21E-02 9.57E-03 7.83E-03 6.96E-03 203 Table F.1-5: SxxS1 SxxS1 Distance ANSI 1977 ANSI 1991 S06S1 6 1.16E-01 6.16E-02 S15S1 15 7.77E-02 4.07E-02 S30S1 30 4.01E-02 2.02E-02 S45S1 45 2.52E-02 1.21E-02 S60S1 60 1.70E-02 8.26E-03 S75S1 75 1.30E-02 6.09E-03 S90S1 90 1.07E-02 4.68E-03 S05S1 105 8.40E-03 3.67E-03 S20S1 120 6.74E-03 3.12E-03 S35S1 135 5.76E-03 2.64E-03 S50S1 150 5.73E-03 2.27E-03 ICRP 74 1.13E-01 7.58E-02 3.86E-02 2.39E-02 1.60E-02 1.22E-02 9.92E-03 7.86E-03 6.31E-03 5.27E-03 5.32E-03 Table F.1-6: VxxS1 VxxS1 Distance ANSI 1977 ANSI 1991 V06S1 6 4.20E-02 2.05E-02 V15S1 15 5.39E-02 2.76E-02 V30S1 30 5.00E-02 2.61E-02 V45S1 45 2.83E-02 1.46E-02 V60S1 60 2.16E-02 1.05E-02 V75S1 75 1.68E-02 8.29E-03 V90S1 90 1.32E-02 6.50E-03 V05S1 105 1.15E-02 5.28E-03 V20S1 120 9.03E-03 4.27E-03 V35S1 135 8.01E-03 3.64E-03 V50S1 150 7.28E-03 3.35E-03 ICRP 74 3.93E-02 5.23E-02 4.81E-02 2.71E-02 2.06E-02 1.60E-02 1.26E-02 1.09E-02 8.56E-03 7.59E-03 6.89E-03 204 Table F.1-7: MxxV1 MxxV1 Distance ANSI 1977 ANSI 1991 M06V1 6 4.74E-02 2.24E-02 M15V1 15 7.29E-02 3.75E-02 M30V1 30 7.57E-02 3.86E-02 M45V1 45 5.15E-02 2.55E-02 M60V1 60 5.40E-02 2.78E-02 M75V1 75 5.72E-02 2.89E-02 M90V1 90 5.27E-02 2.73E-02 M05V1 105 4.82E-02 2.48E-02 M20V1 120 4.30E-02 2.23E-02 M35V1 135 3.92E-02 2.04E-02 M50V1 150 3.81E-02 1.96E-02 ICRP 74 4.43E-02 7.00E-02 7.23E-02 4.85E-02 5.18E-02 5.48E-02 5.07E-02 4.63E-02 4.14E-02 3.77E-02 3.64E-02 Table F.1-8: SxxV1 SxxV1 Distance ANSI 1977 ANSI 1991 S06V1 6 7.30E-02 3.56E-02 S15V1 15 9.24E-02 4.50E-02 S30V1 30 7.80E-02 3.76E-02 S45V1 45 7.44E-02 3.78E-02 S60V1 60 8.25E-02 4.27E-02 S75V1 75 7.61E-02 3.97E-02 S90V1 90 6.63E-02 3.45E-02 S05V1 105 5.78E-02 3.01E-02 S20V1 120 4.97E-02 2.56E-02 S35V1 135 4.23E-02 2.19E-02 S50V1 150 3.95E-02 2.03E-02 ICRP 74 6.84E-02 8.66E-02 7.27E-02 7.07E-02 7.93E-02 7.31E-02 6.38E-02 5.58E-02 4.78E-02 4.06E-02 3.79E-02 205 Table F.1-9: VxxV1 VxxV1 Distance ANSI 1977 ANSI 1991 V06V1 6 7.56E-01 4.08E-01 V15V1 15 5.15E-01 2.76E-01 V30V1 30 3.05E-01 1.62E-01 V45V1 45 1.97E-01 1.05E-01 V60V1 60 1.39E-01 7.31E-02 V75V1 75 1.02E-01 5.36E-02 V90V1 90 7.72E-02 4.03E-02 V05V1 105 6.15E-02 3.24E-02 V20V1 120 5.11E-02 2.66E-02 V35V1 135 4.37E-02 2.25E-02 V50V1 150 4.07E-02 2.09E-02 ICRP 74 7.36E-01 5.00E-01 2.95E-01 1.91E-01 1.34E-01 9.87E-02 7.45E-02 5.94E-02 4.93E-02 4.19E-02 3.91E-02 206 APPENDIX F.2: COMPARISON AT 3 FOOT Table F.2-1: MxxM3 MxxM3 Distance ANSI 1977 ANSI 1991 M06M3 6 3.06E-02 1.58E-02 M15M3 15 2.65E-02 1.27E-02 M30M3 30 1.95E-02 9.68E-03 M45M3 45 1.63E-02 7.59E-03 M60M3 60 1.40E-02 6.57E-03 M75M3 75 1.20E-02 5.66E-03 M90M3 90 1.03E-02 4.55E-03 M05M3 105 9.73E-03 4.41E-03 M20M3 120 9.04E-03 3.94E-03 M35M3 135 8.39E-03 3.67E-03 M50M3 150 8.19E-03 3.57E-03 Table F.2-2: SxxM3 SxxM3 Distance ANSI 1977 ANSI 1991 S06M3 6 1.46E-02 6.99E-03 S15M3 15 1.46E-02 6.83E-03 S30M3 30 1.49E-02 6.63E-03 S45M3 45 3.71E-02 1.96E-02 S60M3 60 3.65E-02 1.88E-02 S75M3 75 2.98E-02 1.52E-02 S90M3 90 1.36E-02 6.22E-03 S05M3 105 9.81E-03 4.45E-03 S20M3 120 9.85E-03 4.73E-03 S35M3 135 1.43E-02 6.96E-03 S50M3 150 1.60E-02 7.94E-03 ICRP 74 1.36E-02 1.37E-02 1.38E-02 3.60E-02 3.51E-02 2.86E-02 1.27E-02 9.09E-03 9.34E-03 1.37E-02 1.53E-02 ICRP 74 2.95E-02 2.53E-02 1.86E-02 1.54E-02 1.32E-02 1.14E-02 9.63E-03 9.11E-03 8.43E-03 7.77E-03 7.66E-03 207 Table F.2-3: VxxM3 VxxM3 Distance ANSI 1977 ANSI 1991 V06M3 6 7.67E-02 4.16E-02 V15M3 15 2.60E-02 1.29E-02 V30M3 30 1.75E-02 8.11E-03 V45M3 45 1.52E-02 6.96E-03 V60M3 60 1.33E-02 6.19E-03 V75M3 75 1.83E-02 8.86E-03 V90M3 90 1.78E-02 8.91E-03 V05M3 105 1.60E-02 7.63E-03 V20M3 120 1.31E-02 6.51E-03 V35M3 135 1.10E-02 5.27E-03 V50M3 150 1.01E-02 4.81E-03 ICRP 74 7.51E-02 2.48E-02 1.65E-02 1.41E-02 1.25E-02 1.74E-02 1.71E-02 1.52E-02 1.24E-02 1.04E-02 9.50E-03 Table F.2-4: MxxS3 MxxS3 Distance ANSI 1977 ANSI 1991 M06S3 6 1.27E-02 5.75E-03 M15S3 15 1.26E-02 6.10E-03 M30S3 30 1.18E-02 5.74E-03 M45S3 45 1.53E-02 7.76E-03 M60S3 60 3.04E-02 1.62E-02 M75S3 75 2.66E-02 1.42E-02 M90S3 90 1.88E-02 9.90E-03 M05S3 105 9.31E-03 4.55E-03 M20S3 120 7.74E-03 3.67E-03 M35S3 135 9.02E-03 4.47E-03 M50S3 150 1.05E-02 5.25E-03 ICRP 74 1.18E-02 1.18E-02 1.10E-02 1.45E-02 2.95E-02 2.58E-02 1.81E-02 8.69E-03 7.14E-03 8.50E-03 1.01E-02 208 Table F.2-5: SxxS3 SxxS3 Distance ANSI 1977 ANSI 1991 S06S3 6 2.61E-02 1.31E-02 S15S3 15 1.96E-02 1.01E-02 S30S3 30 1.46E-02 7.37E-03 S45S3 45 1.17E-02 5.87E-03 S60S3 60 9.83E-03 4.87E-03 S75S3 75 8.71E-03 4.22E-03 S90S3 90 8.13E-03 3.99E-03 S05S3 105 6.27E-03 3.01E-03 S20S3 120 5.80E-03 2.73E-03 S35S3 135 5.22E-03 2.40E-03 S50S3 150 4.85E-03 1.61E-03 ICRP 74 2.52E-02 1.88E-02 1.39E-02 1.12E-02 9.29E-03 8.15E-03 7.66E-03 5.86E-03 5.38E-03 4.78E-03 4.31E-03 Table F.2-6: VxxS3 VxxS3 Distance ANSI 1977 ANSI 1991 V06S3 6 7.57E-02 4.06E-02 V15S3 15 2.49E-02 1.27E-02 V30S3 30 1.49E-02 7.36E-03 V45S3 45 1.24E-02 6.09E-03 V60S3 60 1.14E-02 5.55E-03 V75S3 75 1.66E-02 8.48E-03 V90S3 90 1.61E-02 8.31E-03 V05S3 105 1.38E-02 7.08E-03 V20S3 120 1.18E-02 5.95E-03 V35S3 135 9.93E-03 4.86E-03 V50S3 150 8.72E-03 4.07E-03 ICRP 74 7.42E-02 2.37E-02 1.40E-02 1.16E-02 1.06E-02 1.58E-02 1.54E-02 1.32E-02 1.12E-02 9.28E-03 8.18E-03 209 Table F.2-7: MxxV3 MxxV3 Distance ANSI 1977 ANSI 1991 M06V3 6 2.30E-02 1.12E-02 M15V3 15 2.00E-02 1.00E-02 M30V3 30 1.67E-02 8.19E-03 M45V3 45 1.48E-02 7.18E-03 M60V3 60 1.37E-02 6.67E-03 M75V3 75 1.81E-02 9.11E-03 M90V3 90 1.81E-02 9.14E-03 M05V3 105 1.59E-02 8.12E-03 M20V3 120 1.43E-02 7.18E-03 M35V3 135 1.27E-02 6.37E-03 M50V3 150 1.24E-02 5.63E-03 ICRP 74 2.20E-02 1.90E-02 1.57E-02 1.38E-02 1.28E-02 1.71E-02 1.71E-02 1.52E-02 1.35E-02 1.20E-02 1.16E-02 Table F.2-8: SxxV3 SxxV3 Distance ANSI 1977 ANSI 1991 S06V3 6 2.55E-02 1.22E-02 S15V3 15 1.98E-02 1.01E-02 S30V3 30 1.77E-02 8.85E-03 S45V3 45 1.57E-02 7.81E-03 S60V3 60 1.55E-02 6.88E-03 S75V3 75 1.62E-02 7.34E-03 S90V3 90 1.40E-02 6.80E-03 S05V3 105 1.23E-02 6.07E-03 S20V3 120 1.12E-02 5.44E-03 S35V3 135 1.03E-02 4.98E-03 S50V3 150 8.86E-03 4.00E-03 ICRP 74 2.42E-02 1.90E-02 1.68E-02 1.49E-02 1.46E-02 1.51E-02 1.32E-02 1.16E-02 1.04E-02 9.58E-03 8.28E-03 210 Table F.2-9: VxxV3 VxxV3 Distance ANSI 1977 ANSI 1991 V06V3 6 9.79E-02 5.26E-02 V15V3 15 8.11E-02 4.33E-02 V30V3 30 6.30E-02 3.37E-02 V45V3 45 5.19E-02 2.73E-02 V60V3 60 4.36E-02 2.28E-02 V75V3 75 3.72E-02 1.91E-02 V90V3 90 3.14E-02 1.61E-02 V05V3 105 2.70E-02 1.38E-02 V20V3 120 2.38E-02 1.20E-02 V35V3 135 2.16E-02 1.11E-02 V50V3 150 2.04E-02 1.03E-02 ICRP 74 9.57E-02 7.91E-02 6.13E-02 5.04E-02 4.23E-02 3.59E-02 3.02E-02 2.61E-02 2.29E-02 2.09E-02 1.96E-02 211 APPENDIX F.3: GRAPHICAL COMPARISON AT 1 FOOT MxxM1 Dosimeter Reference Values 0.180 0.160 mrem/hr/kg 0.140 0.120 0.100 0.080 0.060 0.040 0.020 0.000 ANSI 1977 ANSI 1991 ICRP 74 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox Figure F.3-1: MxxM1. SxxM1 Dosimeter Reference Values 0.090 0.080 mrem/hr/kg 0.070 0.060 0.050 0.040 0.030 0.020 0.010 0.000 ANSI 1977 ANSI 1991 ICRP 74 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox 212 Figure F.3-2: SxxM1. VxxM1 Dosimeter Reference Values 7.000E-02 6.000E-02 mrem/hr/kg 5.000E-02 4.000E-02 3.000E-02 2.000E-02 1.000E-02 0.000E+00 0 15 30 45 60 75 90 105 120 135 150 ANSI 1977 ANSI 1991 ICRP 74 Source Distance Inside Glovebox Figure F.3-3: VxxM1. MxxS1 Dosimeter Reference Values 0.070 0.060 mrem/hr/kg 0.050 0.040 0.030 0.020 0.010 0.000 ANSI 1977 ANSI 1991 ICRP 74 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox Figure F.3-4: MxxS1. 213 SxxS1 Dosimeter Reference Values 0.140 0.120 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 ANSI 1977 ANSI 1991 ICRP 74 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox Figure F.3-5: SxxS1. VxxS1 Dosimeter Reference Values 6.000E-02 5.000E-02 mrem/hr/kg 4.000E-02 3.000E-02 2.000E-02 1.000E-02 0.000E+00 0 15 30 45 60 75 90 105 120 135 150 ANSI 1977 ANSI 1991 ICRP 74 Source Distance Inside Glovebox Figure F.3-6: VxxS1. 214 MxxV1 Dosimeter Reference Values 0.080 0.070 0.060 0.050 0.040 0.030 0.020 0.010 0.000 mrem/hr/kg ANSI 1977 ANSI 1991 ICRP 74 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox Figure F.3-7: MxxV1. SxxV1 Dosimeter Reference Values 0.100 0.090 0.080 0.070 0.060 0.050 0.040 0.030 0.020 0.010 0.000 mrem/hr/kg ANSI 1977 ANSI 1991 ICRP 74 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox Figure F.3-8: SxxV1. 215 VxxV1 Dosimeter Reference Values 8.000E-01 7.000E-01 mrem/hr/kg 6.000E-01 5.000E-01 4.000E-01 3.000E-01 2.000E-01 1.000E-01 0.000E+00 0 15 30 45 60 75 90 105 120 135 150 ANSI 1977 ANSI 1991 ICRP 74 Source Distance Inside Glovebox Figure F.3-9: VxxV1. 216 APPENDIX F.4: GRAPHICAL COMPARISON AT 3 FOOT MxxM3 Dosimeter Reference Values 0.035 0.030 mrem/hr/kg 0.025 0.020 0.015 0.010 0.005 0.000 ANSI 1977 ANSI 1991 ICRP 74 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox Figure F.4-1: MxxM3. SxxM3 Dosimeter Reference Values 0.040 0.035 0.030 0.025 0.020 0.015 0.010 0.005 0.000 mrem/hr/kg ANSI 1977 ANSI 1991 ICRP 74 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox 217 Figure F.4-2: SxxM3. VxxM3 Dosimeter Reference Values 9.000E-02 8.000E-02 7.000E-02 6.000E-02 5.000E-02 4.000E-02 3.000E-02 2.000E-02 1.000E-02 0.000E+00 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg ANSI 1977 ANSI 1991 ICRP 74 Source Distance Inside Glovebox Figure F.4-3: VxxM3. MxxS3 Dosimeter Reference Values 0.035 0.030 mrem/hr/kg 0.025 0.020 0.015 0.010 0.005 0.000 ANSI 1977 ANSI 1991 ICRP 74 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox Figure F.4-4: MxxS3. 218 SxxS3 Dosimeter Reference Values 0.030 0.025 mrem/hr/kg 0.020 0.015 0.010 0.005 0.000 ANSI 1977 ANSI 1991 ICRP 74 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox Figure F.4-5: SxxS3. VxxS3 Dosimeter Reference Values 8.000E-02 7.000E-02 mrem/hr/kg 6.000E-02 5.000E-02 4.000E-02 3.000E-02 2.000E-02 1.000E-02 0.000E+00 0 15 30 45 60 75 90 105 120 135 150 ANSI 1977 ANSI 1991 ICRP 74 Source Distance Inside Glovebox Figure F.4-6: VxxS3. 219 MxxV3 Dosimeter Reference Values 0.025 0.020 mrem/hr/kg 0.015 0.010 0.005 0.000 ANSI 1977 ANSI 1991 ICRP 74 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox Figure F.4-7: MxxV3. SxxV3 Dosimeter Reference Values 0.030 0.025 mrem/hr/kg 0.020 0.015 0.010 0.005 0.000 ANSI 1977 ANSI 1991 ICRP 74 0 15 30 45 60 75 90 105 120 135 150 Source Distance Inside Glovebox Figure F.4-8: SxxV3. 220 VxxV3 Dosimeter Reference Values 1.200E-01 1.000E-01 mrem/hr/kg 8.000E-02 6.000E-02 4.000E-02 2.000E-02 0.000E+00 0 15 30 45 60 75 90 105 120 135 150 ANSI 1977 ANSI 1991 ICRP 74 Source Distance Inside Glovebox Figure F.4-9: VxxV3. 221 Appendix G: Comparison Of Whole Body Dose With Dosimeter With Various Tally Plane Doses 222 APPENDIX G.1: ICRP 26 ANSI 1977 AT 1 FOOT MxxM1 - ICRP 26 / ANSI 1977 0.350 0.300 0.250 0.200 0.150 0.100 0.050 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum Dosimeter Reference Male w/ Breasts Male without Breasts Female mrem/hr/kg Source Distance inside Glovebox Figure G.1-1: MxxM1- ICRP 26 ANSI 1977. SxxM1- ICRP 26 / ANSI 1977 0.180 0.160 0.140 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.120 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.1-2: SxxM1- ICRP 26 ANSI 1977. 223 VxxM1- ICRP 26 / ANSI 1977 0.300 0.250 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure G.1-3: VxxM1- ICRP 26 ANSI 1977. MxxS1- ICRP 26 / ANSI 1977 0.160 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.1-4: MxxS1- ICRP 26 ANSI 1977. 224 SxxS1- ICRP 26 / ANSI 1977 0.300 0.250 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure G.1-5: SxxS1- ICRP 26 ANSI 1977. VxxS1- ICRP 26 / ANSI 1977 0.300 0.250 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure G.1-6: VxxS1- ICRP 26 ANSI 1977. 225 MxxV1- ICRP 26 / ANSI 1977 0.350 0.300 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.250 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure G.1-7: MxxV1- ICRP 26 ANSI 1977. SxxV1- ICRP 26 / ANSI 1977 0.400 0.350 0.300 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.250 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure G.1-8: SxxV1- ICRP 26 ANSI 1977. 226 VxxV1- ICRP 26 / ANSI 1977 1.000 0.800 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female mrem/hr/kg 0.600 0.400 0.200 0.000 0 15 30 45 60 75 90 105 120 135 150 Source Distance inside Glovebox Figure G.1-9: VxxV1- ICRP 26 ANSI 1977. 227 APPENDIX G.2: ICRP 26 ANSI 1991 AT 1 FOOT MxxM1 - ICRP 26 / ANSI 1991 0.200 0.150 0.100 0.050 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum Dosimeter Reference Male w/ Breasts Male without Breasts Female mrem/hr/kg Source Distance inside Glovebox Figure G.2-1: MxxM1- ICRP 26 ANSI 1991. SxxM1- ICRP 26 / ANSI 1991 0.100 0.090 0.080 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.070 0.060 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.2-2: SxxM1- ICRP 26 ANSI 1991. 228 VxxM1- ICRP 26 / ANSI 1991 0.160 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.2-3: VxxM1- ICRP 26 ANSI 1991. MxxS1- ICRP 26 / ANSI 1991 0.080 0.070 0.060 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox 229 Figure G.2-4: MxxS1- ICRP 26 ANSI 1991. SxxS1- ICRP 26 / ANSI 1991 0.160 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.2-5: SxxS1- ICRP 26 ANSI 1991. VxxS1- ICRP 26 / ANSI 1991 0.160 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox 230 Figure G.2-6: VxxS1- ICRP 26 ANSI 1991. MxxV1- ICRP 26 / ANSI 1991 0.180 0.160 0.140 0.120 0.100 0.080 0.060 0.040 0.020 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female mrem/hr/kg Source Distance inside Glovebox Figure G.2-7: MxxV1- ICRP 26 ANSI 1991. SxxV1- ICRP 26 / ANSI 1991 0.200 0.180 0.160 0.140 0.120 0.100 0.080 0.060 0.040 0.020 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female mrem/hr/kg Source Distance inside Glovebox 231 Figure G.2-8: SxxV1- ICRP 26 ANSI 1991. VxxV1- ICRP 26 / ANSI 1991 0.600 0.500 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.400 0.300 0.200 0.100 0.000 Source Distance inside Glovebox Figure G.2-9: VxxV1- ICRP 26 ANSI 1991. 232 APPENDIX G.3: ICRP 60 ANSI 1991 AT 1 FOOT MxxM1 - ICRP 60 / ANSI 1991 0.200 0.150 0.100 0.050 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum Dosimeter Reference Male w/ Breasts Male without Breasts Female mrem/hr/kg Source Distance inside Glovebox Figure G.3-1: MxxM1- ICRP 60 ANSI 1991. SxxM1- ICRP 60 / ANSI 1991 0.100 0.090 0.080 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.070 0.060 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.3-2: SxxM1- ICRP 60 ANSI 1991. 233 VxxM1- ICRP 60 / ANSI 1991 0.160 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.3-3: VxxM1- ICRP 60 ANSI 1991. MxxS1- ICRP 60 / ANSI 1991 0.080 0.070 0.060 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.3-4: MxxS1- ICRP 60 ANSI 1991. 234 SxxS1- ICRP 60 / ANSI 1991 0.160 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.3-5: SxxS1- ICRP 60 ANSI 1991. VxxS1- ICRP 60 / ANSI 1991 0.160 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.3-6: VxxS1- ICRP 60 ANSI 1991. 235 MxxV1- ICRP 60 / ANSI 1991 0.180 0.160 0.140 0.120 0.100 0.080 0.060 0.040 0.020 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female mrem/hr/kg Source Distance inside Glovebox Figure G.3-7: MxxV1- ICRP 60 ANSI 1991. SxxV1- ICRP 60 / ANSI 1991 0.200 0.180 0.160 0.140 0.120 0.100 0.080 0.060 0.040 0.020 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female mrem/hr/kg Source Distance inside Glovebox Figure G.3-8: SxxV1- ICRP 60 ANSI 1991. 236 VxxV1- ICRP 60 / ANSI 1991 0.600 0.500 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.400 0.300 0.200 0.100 0.000 Source Distance inside Glovebox Figure G.3-9: VxxV1- ICRP 60 ANSI 1991. 237 APPENDIX G.4: ICRP 60 ICRP 74 AT 1 FOOT MxxM1 - ICRP 60 / ICRP-74 0.300 mrem/hr/kg 0.250 0.200 0.150 0.100 0.050 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum Dosimeter Reference Male w/ Breasts Male without Breasts Female Source Distance inside Glovebox Figure G.4-1: MxxM1- ICRP 60 ICRP 74. SxxM1- ICRP 60 / ICRP-74 0.180 0.160 0.140 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.120 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.4-2: SxxM1- ICRP 60 ICRP 74. 238 VxxM1- ICRP 60 / ICRP-74 0.300 0.250 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure G.4-3: VxxM1- ICRP 60 ICRP 74. MxxS1- ICRP 60 / ICRP-74 0.160 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.4-4: MxxS1- ICRP 60 ICRP 74. 239 SxxS1- ICRP 60 / ICRP-74 0.300 0.250 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure G.4-5: SxxS1- ICRP 60 ICRP 74. VxxS1- ICRP 60 / ICRP-74 0.300 0.250 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure G.4-6: VxxS1- ICRP 60 ICRP 74. 240 MxxV1- ICRP 60 / ICRP-74 0.300 0.250 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure G.4-7: MxxV1- ICRP 60 ICRP 74. SxxV1- ICRP 60 / ICRP-74 0.400 0.350 0.300 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.250 0.200 0.150 0.100 0.050 0.000 Source Distance inside Glovebox Figure G.4-8: SxxV1- ICRP 60 ICRP 74. 241 VxxV1- ICRP 60 / ICRP-74 1.000 0.800 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female mrem/hr/kg 0.600 0.400 0.200 0.000 0 15 30 45 60 75 90 105 120 135 150 Source Distance inside Glovebox Figure G.4-9: VxxV1 ICRP 60 ICRP 74. 242 APPENDIX G.5: ICRP 26 ANSI 1977 AT 3 FOOT MxxM3 - ICRP 26 / ANSI 1977 0.050 0.040 0.030 0.020 0.010 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum Dosimeter Reference Male w/ Breasts Male without Breasts Female mrem/hr/kg Source Distance inside Glovebox Figure G.5-1: MxxM3- ICRP 26 ANSI 1977. SxxM3- ICRP 26 / ANSI 1977 0.060 0.050 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.5-2: SxxM3- ICRP 26 ANSI 1977. 243 VxxM3- ICRP 26 / ANSI 1977 0.140 0.120 Average mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 0 15 30 45 60 75 90 105 120 135 150 Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female Source Distance inside Glovebox Figure G.5-3: VxxM3- ICRP 26 ANSI 1977. MxxS3- ICRP 26 / ANSI 1977 0.050 0.045 0.040 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.035 0.030 0.025 0.020 0.015 0.010 0.005 0.000 Source Distance inside Glovebox Figure G.5-4: MxxS3- ICRP 26 ANSI 1977. 244 SxxS3- ICRP 26 / ANSI 1977 0.045 0.040 0.035 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.030 0.025 0.020 0.015 0.010 0.005 0.000 Source Distance inside Glovebox Figure G.5-5: SxxS3- ICRP 26 ANSI 1977. VxxS3- ICRP 26 / ANSI 1977 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.5-6: VxxS3- ICRP 26 ANSI 1977. 245 MxxV3- ICRP 26 / ANSI 1977 0.070 0.060 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.5-7: MxxV3- ICRP 26 ANSI 1977. SxxV3- ICRP 26 / ANSI 1977 0.070 0.060 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.5-8: SxxV3- ICRP 26 ANSI 1977. 246 VxxV3- ICRP 26 / ANSI 1977 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.5-9: VxxV3- ICRP 26 ANSI 1977. 247 APPENDIX G.6: ICRP 26 ANSI 1991 AT 3 FOOT MxxM3 - ICRP 26 / ANSI 1991 0.030 mrem/hr/kg 0.025 0.020 0.015 0.010 0.005 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum Dosimeter Reference Male w/ Breasts Male without Breasts Female Source Distance inside Glovebox Figure G.6-1: MxxM3- ICRP 26 ANSI 1991. SxxM3- ICRP 26 / ANSI 1991 0.030 0.025 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.020 0.015 0.010 0.005 0.000 Source Distance inside Glovebox Figure G.6-2: SxxM3- ICRP 26 ANSI 1991. 248 VxxM3- ICRP 26 / ANSI 1991 0.080 0.070 0.060 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.6-3: VxxM3- ICRP 26 ANSI 1991. MxxS3- ICRP 26/ANSI 1991 0.030 0.025 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.020 0.015 0.010 0.005 0.000 Source Distance inside Glovebox Figure G.6-4: MxxS3- ICRP 26 ANSI 1991. 249 SxxS3- ICRP 26 / ANSI 1991 0.025 0.020 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female mrem/hr/kg 0.015 0.010 0.005 0.000 0 15 30 45 60 75 90 105 120 135 150 Source Distance inside Glovebox Figure G.6-5: SxxS3- ICRP 26 ANSI 1991. VxxS3- ICRP 26 / ANSI 1991 0.070 0.060 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.6-6: VxxS3- ICRP 26 ANSI 1991. 250 MxxV3- ICRP 26 / ANSI 1991 0.040 0.035 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.030 0.025 0.020 0.015 0.010 0.005 0.000 Source Distance inside Glovebox Figure G.6-7: MxxV3- ICRP 26 ANSI 1991. SxxV3- ICRP 26 / ANSI 1991 0.035 0.030 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.025 0.020 0.015 0.010 0.005 0.000 Source Distance inside Glovebox Figure G.6-8: SxxV3- ICRP 26 ANSI 1991. 251 VxxV3- ICRP 26 / ANSI 1991 0.080 0.070 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.060 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.6-9: VxxV3- ICRP 26 ANSI 1991. 252 APPENDIX G.7: ICRP 60 ANSI 1991 AT 3 FOOT MxxM3 - ICRP 60 /ANSI 1991 0.025 0.020 0.015 0.010 0.005 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum Dosimeter Reference Male w/ Breasts Male without Breasts Female mrem/hr/kg Source Distance inside Glovebox Figure G.7-1: MxxM3- ICRP 60 ANSI 1991. SxxM3- ICRP 60 /ANSI 1991 0.030 0.025 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.020 0.015 0.010 0.005 0.000 Source Distance inside Glovebox Figure G.7-2: SxxM3- ICRP 60 ANSI 1991. 253 VxxM3- ICRP 60 /ANSI 1991 0.080 0.070 0.060 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.7-3: VxxM3- ICRP 60 ANSI 1991. MxxS3- ICRP 60 /ANSI 1991 0.030 0.025 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.020 0.015 0.010 0.005 0.000 Source Distance inside Glovebox Figure G.7-4: MxxS3- ICRP 60 ANSI 1991. 254 SxxS3- ICRP 60 /ANSI 1991 0.025 0.020 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female mrem/hr/kg 0.015 0.010 0.005 0.000 0 15 30 45 60 75 90 105 120 135 150 Source Distance inside Glovebox Figure G.7-5: SxxS3- ICRP 60 ANSI 1991. VxxS3- ICRP 60 /ANSI 1991 0.070 0.060 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.7-6: VxxS3- ICRP 60 ANSI 1991. 255 MxxV3- ICRP 60 /ANSI 1991 0.040 0.035 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.030 0.025 0.020 0.015 0.010 0.005 0.000 Source Distance inside Glovebox Figure G.7-7: MxxV3- ICRP 60 ANSI 1991. SxxV3- ICRP 60 /ANSI 1991 0.035 0.030 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.025 0.020 0.015 0.010 0.005 0.000 Source Distance inside Glovebox Figure G.7-8: SxxV3- ICRP 60 ANSI 1991. 256 VxxV3- ICRP 60 /ANSI 1991 0.080 0.070 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.060 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.7-9: VxxV3- ICRP 60 ANSI 1991. 257 APPENDIX G.8: ICRP 60 ICRP 74 AT 3 FOOT MxxM3 - ICRP 60 / ICRP-74 0.050 0.040 0.030 0.020 0.010 0.000 0 15 30 45 60 75 90 105 120 135 150 Average Maximum Minimum Dosimeter Reference Male w/ Breasts Male without Breasts Female mrem/hr/kg Source Distance inside Glovebox Figure G.8-1: MxxM3- ICRP 60 ICRP 74. SxxM3- ICRP 60 / ICRP-74 0.060 0.050 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.8-2: SxxM3- ICRP 60 ICRP 74. 258 VxxM3- ICRP 60 / ICRP-74 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.8-3: VxxM3- ICRP 60 ICRP 74. MxxS3- ICRP 60 / ICRP-74 0.050 0.045 0.040 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.035 0.030 0.025 0.020 0.015 0.010 0.005 0.000 Source Distance inside Glovebox Figure G.8-4: MxxS3- ICRP 60 ICRP 74. 259 SxxS3- ICRP 60 / ICRP-74 0.045 0.040 0.035 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.030 0.025 0.020 0.015 0.010 0.005 0.000 Source Distance inside Glovebox Figure G.8-5: SxxS3- ICRP 60 ICRP 74. VxxS3- ICRP 60 / ICRP-74 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.8-6: VxxS31- ICRP 60 ICRP 74. 260 MxxV3- ICRP 60 / ICRP-74 0.070 0.060 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.8-7: MxxV3- ICRP 60 ICRP 74. SxxV3- ICRP 60 / ICRP-74 0.070 0.060 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.050 0.040 0.030 0.020 0.010 0.000 Source Distance inside Glovebox Figure G.8-8: SxxV3- ICRP 60 ICRP 74. 261 VxxV3- ICRP 60 / ICRP-74 0.140 0.120 Average Maximum Minimum DosimeterReference Male w/ Breasts Male without Breasts Female 0 15 30 45 60 75 90 105 120 135 150 mrem/hr/kg 0.100 0.080 0.060 0.040 0.020 0.000 Source Distance inside Glovebox Figure G.8-9: VxxV3 ICRP 60 ICRP 74. 262 Appendix H: Distribution Of Average, Maximum, And Minimum Dosimeter Values 263 APPENDIX H.1: DETAILED TABLES FOR THE LOCATION OF THE AVERAGE, MAXIMUM, AND MINIMUM DOSIMETER VALUES Table H.1-1: ANSI 1977 at 1 ft - Location of Various Dosimeter Values ANSI 1977 Location for ANSI 1977 Location for Configuration Ave Max Min Configuration Ave Max Min 1M06M1Z 1M06S1Z 1M06V1Z 1M15M1Z 1M15S1Z 1M15V1Z 1M30M1Z 1M30S1Z 1M30V1Z 1M45M1Z 1M45S1Z 1M45V1Z 1M60M1Z 1M60S1Z 1M60V1Z 1M75M1Z 1M75S1Z 1M75V1Z 1M90M1Z 1M90S1Z 1M90V1Z 1M05M1Z 1M05S1Z 1M05V1Z 1M20M1Z 1M20S1Z 1M20V1Z 1M35M1Z 552 612 412 572 412 622 482 502 622 482 562 442 562 722 642 532 672 642 622 612 642 462 672 642 462 422 622 582 652 522 672 652 562 462 472 572 472 522 572 522 522 512 522 522 512 522 522 522 522 522 522 522 522 522 522 522 412 692 692 412 692 692 412 692 692 412 692 692 712 692 702 702 642 702 702 692 702 702 692 702 702 692 712 692 264 1S75V1Z 1S90M1Z 1S90S1Z 1S90V1Z 1S05M1Z 1S05S1Z 1S05V1Z 1S20M1Z 1S20S1Z 1S20V1Z 1S35M1Z 1S35S1Z 1S35V1Z 1S50M1Z 1S50S1Z 1S50V1Z 1V06M1Z 1V06S1Z 1V06V1Z 1V15M1Z 1V15S1Z 1V15V1Z 1V30M1Z 1V30S1Z 1V30V1Z 1V45M1Z 1V45S1Z 1V45V1Z 532 502 612 472 632 612 652 632 662 672 442 512 582 632 662 422 542 562 492 632 672 522 582 622 462 582 622 432 472 482 522 482 482 522 482 482 522 482 482 522 482 482 522 482 582 622 602 442 462 602 432 472 602 482 522 602 702 712 442 692 702 492 692 712 402 702 712 442 702 702 492 702 712 692 722 712 692 722 712 692 712 712 692 692 ANSI 1977 Configuration 1M35S1Z 1M35V1Z 1M50M1Z 1M50S1Z 1M50V1Z 1S06M1Z 1S06S1Z 1S06V1Z 1S15M1Z 1S15S1Z 1S15V1Z 1S30M1Z 1S30S1Z 1S30V1Z 1S45M1Z 1S45S1Z 1S45V1Z 1S60M1Z 1S60S1Z 1S60V1Z 1S75M1Z 1S75S1Z Location for ANSI 1977 Location for Ave Max Min Configuration Ave Max Min 672 522 592 1V60M1Z 582 482 712 562 572 702 1V60S1Z 672 522 692 432 522 702 1V60V1Z 452 552 702 462 522 492 1V75M1Z 632 482 702 402 572 702 1V75S1Z 672 522 692 592 482 702 1V75V1Z 642 522 702 642 672 402 1V90M1Z 632 482 712 542 632 712 1V90S1Z 462 522 402 472 542 712 1V90V1Z 662 522 702 512 672 402 1V05M1Z 572 482 702 632 432 712 1V05S1Z 722 522 492 562 532 712 1V05V1Z 662 482 702 512 472 402 1V20M1Z 632 482 692 502 482 712 1V20S1Z 722 522 402 462 492 712 1V20V1Z 662 522 692 462 472 402 1V35M1Z 632 482 712 462 482 712 1V35S1Z 722 522 402 452 492 712 1V35V1Z 412 522 702 462 522 402 1V50M1Z 542 482 702 442 482 702 1V50S1Z 722 522 402 632 492 702 1V50V1Z 432 482 702 662 522 402 265 Table H.1-2: ANSI 1977 at 1 ft - Location of Various Dosimeter Values ANSI 1991 Location for ANSI 1991 Location for Configuration Ave Max Min Configuration Ave Max Min 1M06M1Z 1M06S1Z 1M06V1Z 1M15M1Z 1M15S1Z 1M15V1Z 1M30M1Z 1M30S1Z 1M30V1Z 1M45M1Z 1M45S1Z 1M45V1Z 1M60M1Z 1M60S1Z 1M60V1Z 1M75M1Z 1M75S1Z 1M75V1Z 1M90M1Z 1M90S1Z 1M90V1Z 1M05M1Z 1M05S1Z 1M05V1Z 1M20M1Z 1M20S1Z 1M20V1Z 1M35M1Z 1M35S1Z 1M35V1Z 1M50M1Z 152 212 112 322 222 272 192 102 222 82 162 42 162 82 242 132 272 242 222 212 32 222 22 242 62 22 162 182 22 22 32 252 122 272 252 162 62 72 172 72 122 122 122 122 112 122 122 112 122 122 122 122 122 122 122 122 122 122 122 122 122 122 12 192 292 12 292 292 12 292 292 12 292 292 312 302 292 302 292 292 302 292 292 302 292 302 302 292 292 292 292 302 292 266 1S75V1Z 1S90M1Z 1S90S1Z 1S90V1Z 1S05M1Z 1S05S1Z 1S05V1Z 1S20M1Z 1S20S1Z 1S20V1Z 1S35M1Z 1S35S1Z 1S35V1Z 1S50M1Z 1S50S1Z 1S50V1Z 1V06M1Z 1V06S1Z 1V06V1Z 1V15M1Z 1V15S1Z 1V15V1Z 1V30M1Z 1V30S1Z 1V30V1Z 1V45M1Z 1V45S1Z 1V45V1Z 1V60M1Z 1V60S1Z 1V60V1Z 142 102 112 72 232 112 252 232 112 272 42 162 92 232 62 122 192 212 102 232 272 122 182 222 182 182 222 72 182 222 52 82 82 122 82 82 122 82 82 122 82 82 122 82 82 122 132 182 222 202 42 62 202 32 72 202 82 122 202 82 122 202 302 312 292 302 302 42 302 312 92 292 302 192 302 312 42 302 312 292 322 312 292 282 312 292 292 312 292 312 312 292 302 ANSI 1991 Location for ANSI 1991 Location for Configuration Ave Max Min Configuration Ave Max Min 1M50S1Z 1V75M1Z 82 302 22 122 292 232 1M50V1Z 1V75S1Z 2 122 302 272 122 292 1S06M1Z 1V75V1Z 192 172 122 302 82 302 1S06S1Z 1V90M1Z 242 272 42 2 82 312 1S06V1Z 1V90S1Z 142 272 122 292 12 312 1S15M1Z 1V90V1Z 72 142 312 242 122 302 1S15S1Z 1V05M1Z 112 272 172 2 82 302 1S15V1Z 1V05S1Z 182 272 122 292 32 312 1S30M1Z 1V05V1Z 162 132 312 262 82 292 1S30S1Z 1V20M1Z 62 72 72 2 82 312 1S30V1Z 1V20S1Z 102 322 122 242 82 312 1S45M1Z 1V20V1Z 62 12 122 302 92 312 1S45S1Z 1V35M1Z 62 232 72 2 82 312 1S45V1Z 1V35S1Z 82 312 2 62 322 122 1S60M1Z 1V35V1Z 52 2 122 302 92 312 1S60S1Z 1V50M1Z 62 122 142 2 82 302 1S60V1Z 1V50S1Z 42 322 122 292 82 312 1S75M1Z 1V50V1Z 182 32 92 302 82 302 1S75S1Z 212 122 292 267 Table H.1-3: ICRP 74 at 1 ft - Location of Various Dosimeter Values ICRP 74 Configuration 1M06M1Z 1M06S1Z 1M06V1Z 1M15M1Z 1M15S1Z 1M15V1Z 1M30M1Z 1M30S1Z 1M30V1Z 1M45M1Z 1M45S1Z 1M45V1Z 1M60M1Z 1M60S1Z 1M60V1Z 1M75M1Z 1M75S1Z 1M75V1Z 1M90M1Z 1M90S1Z 1M90V1Z 1M05M1Z 1M05S1Z 1M05V1Z 1M20M1Z 1M20S1Z 1M20V1Z 1M35M1Z 1M35S1Z 1M35V1Z 1M50M1Z Location for Ave Max Min 952 1052 812 1012 922 1092 862 1072 1092 1122 1052 812 812 962 1092 1072 862 1092 992 872 812 902 972 1092 1022 872 1092 882 922 812 962 972 1092 842 922 1092 962 922 1112 1122 912 1092 1042 922 1092 932 922 1102 1072 912 1102 1042 922 1102 1022 922 1102 1012 922 1092 832 922 1102 862 922 1102 1072 922 1092 1042 922 1102 862 922 1102 822 922 1092 962 922 1102 982 922 1092 1072 922 992 962 972 1102 832 922 1102 268 ICRP 74 Configuration 1S75V1Z 1S90M1Z 1S90S1Z 1S90V1Z 1S05M1Z 1S05S1Z 1S05V1Z 1S20M1Z 1S20S1Z 1S20V1Z 1S35M1Z 1S35S1Z 1S35V1Z 1S50M1Z 1S50S1Z 1S50V1Z 1V06M1Z 1V06S1Z 1V06V1Z 1V15M1Z 1V15S1Z 1V15V1Z 1V30M1Z 1V30S1Z 1V30V1Z 1V45M1Z 1V45S1Z 1V45V1Z 1V60M1Z 1V60S1Z 1V60V1Z Location for Ave Max Min 932 902 1012 872 1032 1012 1052 1032 1062 1072 842 912 982 1032 1062 822 992 1012 902 1032 1072 922 982 1022 862 982 1022 872 982 1072 852 872 882 922 882 882 922 882 882 922 882 882 922 882 882 922 932 982 1022 1002 842 862 1002 832 872 1002 882 922 1002 882 922 1002 1102 1112 842 1092 1102 892 1102 1112 802 1102 1112 842 1102 1102 892 1102 1112 1092 1122 1112 1092 1122 1112 1092 1112 1112 1092 1092 1112 1092 1102 ICRP 74 Location for ICRP 74 Location for Configuration Ave Max Min Configuration Ave Max Min 1M50S1Z 1V75M1Z 862 922 892 1032 882 1102 1M50V1Z 1V75S1Z 802 922 1102 1072 922 1092 1S06M1Z 1V75V1Z 992 882 1102 972 922 1102 1S06S1Z 1V90M1Z 1042 1072 802 1032 882 1112 1S06V1Z 1V90S1Z 942 1032 1112 862 922 802 1S15M1Z 1V90V1Z 872 942 1112 1042 922 1102 1S15S1Z 1V05M1Z 952 1072 802 972 882 1102 1S15V1Z 1V05S1Z 932 832 1112 1122 922 892 1S30M1Z 1V05V1Z 962 932 1112 1062 882 1102 1S30S1Z 1V20M1Z 912 872 802 872 882 1092 1S30V1Z 1V20S1Z 902 882 1112 1122 922 802 1S45M1Z 1V20V1Z 862 892 1112 1062 922 1092 1S45S1Z 1V35M1Z 862 872 802 1032 882 1112 1S45V1Z 1V35S1Z 862 882 1112 1122 922 802 1S60M1Z 1V35V1Z 852 892 1112 812 922 1102 1S60S1Z 1V50M1Z 862 922 802 942 882 1102 1S60V1Z 1V50S1Z 842 882 1102 1122 922 802 1S75M1Z 1V50V1Z 1032 892 1102 832 882 1102 1S75S1Z 1012 922 802 269 Table H.1-4: ANSI 1977 at 3 ft - Location of Various Dosimeter Values ANSI 1977 Location for ANSI 1977 Location for Configuration Ave Max Min Configuration Ave Max Min 1M06M3Z 1M06S3Z 1M06V3Z 1M15M3Z 1M15S3Z 1M15V3Z 1M30M3Z 1M30S3Z 1M30V3Z 1M45M3Z 1M45S3Z 1M45V3Z 1M60M3Z 1M60S3Z 1M60V3Z 1M75M3Z 1M75S3Z 1M75V3Z 1M90M3Z 1M90S3Z 1M90V3Z 1M05M3Z 1M05S3Z 1M05V3Z 1M20M3Z 1M20S3Z 1M20V3Z 1M35M3Z 1M35S3Z 1M35V3Z 1M50M3Z 662 662 662 642 532 612 562 582 532 512 522 622 512 612 572 462 672 482 672 552 562 622 492 402 622 562 442 632 542 412 622 582 622 672 572 572 722 522 422 402 572 432 432 472 432 432 472 512 472 472 572 472 472 522 472 472 432 472 472 482 522 472 412 402 402 412 402 402 402 692 692 702 702 702 702 692 702 702 702 702 702 702 692 702 692 692 692 702 702 702 702 702 702 270 1S75V3Z 1S90M3Z 1S90S3Z 1S90V3Z 1S05M3Z 1S05S3Z 1S05V3Z 1S20M3Z 1S20S3Z 1S20V3Z 1S35M3Z 1S35S3Z 1S35V3Z 1S50M3Z 1S50S3Z 1S50V3Z 1V06M3Z 1V06S3Z 1V06V3Z 1V15M3Z 1V15S3Z 1V15V3Z 1V30M3Z 1V30S3Z 1V30V3Z 1V45M3Z 1V45S3Z 1V45V3Z 1V60M3Z 1V60S3Z 1V60V3Z 472 642 562 542 592 422 542 562 532 542 552 512 452 442 722 612 442 462 492 682 722 642 622 722 422 482 522 422 482 572 602 432 432 472 432 482 472 482 482 472 482 522 472 432 472 472 432 582 622 582 582 622 622 482 522 572 472 432 522 472 432 572 702 712 492 702 702 442 712 702 492 702 702 402 702 702 642 702 702 692 702 422 442 692 662 692 702 702 702 702 652 702 702 ANSI 1977 Location for ANSI 1977 Location for Configuration Ave Max Min Configuration Ave Max Min 1M50S3Z 412 482 702 1V75M3Z 522 472 702 1M50V3Z 502 522 702 1V75S3Z 482 432 642 1S06M3Z 492 682 412 1V75V3Z 582 512 702 1S06S3Z 432 622 412 1V90M3Z 542 432 702 1S06V3Z 542 582 412 1V90S3Z 562 472 702 1S15M3Z 492 482 712 1V90V3Z 662 422 702 1S15S3Z 712 522 402 1V05M3Z 512 432 712 1S15V3Z 542 682 412 1V05S3Z 492 472 702 1S30M3Z 442 522 712 1V05V3Z 522 512 702 1S30S3Z 482 622 412 1V20M3Z 462 432 702 1S30V3Z 482 422 712 1V20S3Z 442 472 702 1S45M3Z 652 522 712 1V20V3Z 642 462 702 1S45S3Z 632 622 492 1V35M3Z 412 482 702 1S45V3Z 492 472 702 1V35S3Z 412 472 702 1S60M3Z 672 572 712 1V35V3Z 642 512 702 1S60S3Z 512 472 442 1V50M3Z 412 482 712 1S60V3Z 522 432 702 1V50S3Z 622 472 702 1S75M3Z 652 432 702 1V50V3Z 652 512 692 1S75S3Z 462 472 402 271 Table H.1-5: ANSI 1991 at 3 ft - Location of Various Dosimeter Values ANSI 1991 Location for ANSI 1991 Location for Configuration Ave Max Min Configuration Ave Max Min 1M06M3Z 1M06S3Z 1M06V3Z 1M15M3Z 1M15S3Z 1M15V3Z 1M30M3Z 1M30S3Z 1M30V3Z 1M45M3Z 1M45S3Z 1M45V3Z 1M60M3Z 1M60S3Z 1M60V3Z 1M75M3Z 1M75S3Z 1M75V3Z 1M90M3Z 1M90S3Z 1M90V3Z 1M05M3Z 1M05S3Z 1M05V3Z 1M20M3Z 1M20S3Z 1M20V3Z 1M35M3Z 1M35S3Z 1M35V3Z 1M50M3Z 262 162 312 242 282 162 162 182 82 92 122 222 142 252 172 62 272 82 232 152 162 222 92 2 182 162 42 132 142 12 222 182 222 222 82 222 322 122 22 2 172 32 32 72 32 32 72 112 72 72 172 72 72 122 72 72 32 72 72 82 122 72 12 142 2 12 2 2 12 292 292 302 302 302 302 292 302 302 302 302 302 302 292 302 292 292 292 302 302 302 302 292 302 272 1S75V3Z 1S90M3Z 1S90S3Z 1S90V3Z 1S05M3Z 1S05S3Z 1S05V3Z 1S20M3Z 1S20S3Z 1S20V3Z 1S35M3Z 1S35S3Z 1S35V3Z 1S50M3Z 1S50S3Z 1S50V3Z 1V06M3Z 1V06S3Z 1V06V3Z 1V15M3Z 1V15S3Z 1V15V3Z 1V30M3Z 1V30S3Z 1V30V3Z 1V45M3Z 1V45S3Z 1V45V3Z 1V60M3Z 1V60S3Z 1V60V3Z 112 242 62 142 2 22 142 162 62 142 152 112 162 42 62 212 42 252 252 282 322 62 72 322 2 32 72 52 132 172 202 32 132 72 32 82 72 82 82 72 82 122 72 32 72 72 32 182 272 232 182 222 222 182 122 172 72 32 122 72 32 172 312 312 92 302 302 42 292 312 92 302 302 92 302 302 92 302 302 292 302 312 242 302 302 292 302 302 242 302 252 302 302 ANSI 1991 Location for ANSI 1991 Location for Configuration Ave Max Min Configuration Ave Max Min 1M50S3Z 12 122 292 1V75M3Z 122 72 302 1M50V3Z 162 122 302 1V75S3Z 82 32 302 1S06M3Z 92 282 12 1V75V3Z 262 112 302 1S06S3Z 312 272 12 1V90M3Z 142 32 292 1S06V3Z 142 132 22 1V90S3Z 162 72 292 1S15M3Z 192 82 262 1V90V3Z 82 62 302 1S15S3Z 262 222 2 1V05M3Z 22 32 302 1S15V3Z 142 182 22 1V05S3Z 92 72 302 1S30M3Z 112 122 312 1V05V3Z 72 112 302 1S30S3Z 262 122 12 1V20M3Z 62 32 302 1S30V3Z 122 22 312 1V20S3Z 152 72 302 1S45M3Z 252 122 312 1V20V3Z 12 92 292 1S45S3Z 112 222 92 1V35M3Z 12 82 302 1S45V3Z 92 72 302 1V35S3Z 12 72 302 1S60M3Z 182 172 312 1V35V3Z 252 92 302 1S60S3Z 312 72 42 1V50M3Z 12 82 312 1S60V3Z 112 32 292 1V50S3Z 12 72 302 1S75M3Z 252 82 302 1V50V3Z 252 112 312 1S75S3Z 62 72 2 273 Table H.1-6: ICRP 74 at 3 ft - Location of Various Dosimeter Values ICRP 74 Configuration 1M06M3Z 1M06S3Z 1M06V3Z 1M15M3Z 1M15S3Z 1M15V3Z 1M30M3Z 1M30S3Z 1M30V3Z 1M45M3Z 1M45S3Z 1M45V3Z 1M60M3Z 1M60S3Z 1M60V3Z 1M75M3Z 1M75S3Z 1M75V3Z 1M90M3Z 1M90S3Z 1M90V3Z 1M05M3Z 1M05S3Z 1M05V3Z 1M20M3Z 1M20S3Z 1M20V3Z 1M35M3Z 1M35S3Z 1M35V3Z 1M50M3Z Location for Ave Max Min 1062 982 812 1112 1022 802 1112 1072 802 1042 972 812 932 972 802 1012 1122 802 962 922 802 982 822 1092 932 802 1092 892 972 1102 922 832 1102 1022 832 1102 912 872 1102 1052 832 1092 972 832 1102 862 872 1102 1072 912 1102 882 872 1102 1122 872 1102 952 972 1102 962 872 1092 1022 872 1102 892 922 1092 802 872 1092 1022 872 1092 962 832 1102 842 872 1102 912 872 1102 942 882 1102 812 922 1102 932 872 1102 274 ICRP 74 Configuration 1S75V3Z 1S90M3Z 1S90S3Z 1S90V3Z 1S05M3Z 1S05S3Z 1S05V3Z 1S20M3Z 1S20S3Z 1S20V3Z 1S35M3Z 1S35S3Z 1S35V3Z 1S50M3Z 1S50S3Z 1S50V3Z 1V06M3Z 1V06S3Z 1V06V3Z 1V15M3Z 1V15S3Z 1V15V3Z 1V30M3Z 1V30S3Z 1V30V3Z 1V45M3Z 1V45S3Z 1V45V3Z 1V60M3Z 1V60S3Z 1V60V3Z Location for Ave Max Min 872 1042 962 942 992 822 942 962 862 942 952 912 962 842 1122 1012 842 1002 952 1082 1122 862 1022 1122 802 832 922 852 882 972 1002 832 832 872 832 882 872 882 882 872 882 922 872 832 872 872 832 982 1022 1022 982 1022 1022 882 922 972 872 832 922 872 832 972 1102 1112 892 1102 1102 842 1092 1102 892 1102 1102 802 1102 1102 1042 1102 1102 1092 1102 822 1042 1092 1062 1092 1102 1102 1042 1102 1052 1102 1102 ICRP 74 Configuration 1M50S3Z 1M50V3Z 1S06M3Z 1S06S3Z 1S06V3Z 1S15M3Z 1S15S3Z 1S15V3Z 1S30M3Z 1S30S3Z 1S30V3Z 1S45M3Z 1S45S3Z 1S45V3Z 1S60M3Z 1S60S3Z 1S60V3Z 1S75M3Z 1S75S3Z Location for ICRP 74 Location for Ave Max Min Configuration Ave Max Min 812 882 1102 1V75M3Z 922 872 1102 902 922 1102 1V75S3Z 882 832 1102 892 1082 812 1V75V3Z 982 912 1102 832 1022 812 1V90M3Z 942 832 1102 992 982 812 1V90S3Z 962 872 1092 892 882 1112 1V90V3Z 1062 912 1102 1112 1022 802 1V05M3Z 912 832 1112 1122 1082 822 1V05S3Z 892 872 1102 802 922 1112 1V05V3Z 972 912 1102 1082 1022 812 1V20M3Z 862 832 1102 922 822 1112 1V20S3Z 952 872 1102 1052 922 1112 1V20V3Z 1052 862 1102 912 1022 892 1V35M3Z 812 832 1102 892 872 1102 1V35S3Z 812 872 1102 1072 972 1112 1V35V3Z 922 912 1102 962 872 842 1V50M3Z 812 882 1112 922 832 1102 1V50S3Z 1022 872 1102 1052 832 1102 1V50V3Z 1052 912 1092 862 872 802 275 APPENDIX H.2: SUMMARY TABLES FOR THE LOCATION OF THE AVERAGE DOSIMETER VALUES Table H.2-1: ANSI 1977 at 1 ft - Location of Average Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -16 -8 0 8 1 3 2 3 3 2 9 2 1 3 3 2 3 1 5 5 1 0 4 10 6 1 6 0 0 0 0 16 2 1 2 6 7 5 Table H.2-2: ANSI 1991 at 1 ft - Location of Average Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -16 -8 0 8 2 1 5 3 4 2 7 2 1 4 5 1 3 1 5 7 3 0 4 6 5 1 1 0 0 0 0 16 4 2 2 7 7 4 Table H.2-3: ICRP 74 at 1 ft - Location of Average Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -8 0 8 1 2 2 3 2 10 0 4 2 2 2 5 3 0 6 5 1 4 0 0 0 276 -16 3 1 3 5 8 0 16 4 1 2 4 8 6 Table H.2-4: ANSI 1977 at 3 ft - Location of Average Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -16 -8 0 8 1 5 3 1 5 1 4 6 6 1 5 3 7 2 6 2 1 1 3 2 5 3 4 1 0 0 1 16 1 5 2 6 3 3 Table H.2-5: ANSI 1991 at 3 ft - Location of Average Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -16 -8 0 8 3 7 2 1 3 1 7 4 5 0 5 2 8 3 9 3 1 1 1 1 2 7 4 2 0 0 3 16 3 3 2 3 1 2 Table H.2-6: ICRP 74 at 3 ft - Location of Average Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -16 -8 0 8 3 5 1 2 3 1 5 3 6 1 5 3 5 4 8 2 2 2 2 0 2 5 2 2 0 0 3 16 1 6 3 5 2 5 277 APPENDIX H.3: SUMMARY TABLES FOR THE LOCATION OF THE MAXIMUM DOSIMETER VALUES Table H.3-1: ANSI 1977 at 1 ft - Location of Maximum Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -16 -8 0 8 0 0 0 2 1 0 2 24 3 0 2 1 1 1 1 1 0 4 0 1 0 2 0 0 0 0 0 16 6 39 4 1 3 0 Table H.3-2: ANSI 1991 at 1 ft - Location of Maximum Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -16 -8 0 8 0 1 0 2 1 0 2 24 3 0 2 2 1 0 1 1 0 5 0 0 0 2 0 0 0 0 0 16 5 42 1 1 3 0 Table H.3-3: ICRP 74 at 1 ft - Location of Maximum Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -16 -8 0 8 0 0 0 2 1 0 2 23 3 0 2 2 1 0 1 1 0 5 0 1 0 2 0 0 0 0 0 278 16 6 40 3 1 3 0 Table H.3-4: ANSI 1977 at 3 ft - Location of Maximum Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -16 -8 0 8 1 0 3 18 0 0 1 10 0 0 5 0 0 0 0 5 0 0 0 0 0 0 0 2 0 0 0 16 28 10 7 7 1 1 Table H.3-5: ANSI 1991 at 3 ft - Location of Maximum Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -16 -8 0 8 1 0 2 16 0 0 1 10 2 0 4 2 0 0 0 5 0 0 0 1 0 0 0 1 0 0 0 16 28 11 5 7 2 1 Table H.3-6: ICRP 74 at 3 ft - Location of Maximum Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -16 -8 0 8 1 0 2 19 0 0 1 9 0 0 6 0 0 0 0 4 0 0 0 0 0 0 0 2 0 0 0 16 28 9 7 9 1 1 279 APPENDIX H.4: SUMMARY TABLES FOR THE LOCATION OF THE MINIMUM DOSIMETER VALUES Table H.4-1: ANSI 1977 at 1 ft - Location of Minimum Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -8 0 8 11 4 0 2 0 0 4 0 0 0 0 0 1 0 0 1 0 0 24 29 21 -16 0 0 0 0 0 0 16 0 0 0 0 0 2 Table H.4-2: ANSI 1991 at 1 ft - Location of Minimum Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -8 0 8 6 4 0 2 0 0 1 0 0 0 0 0 2 0 0 1 0 0 33 26 22 -16 0 0 0 0 0 1 16 0 0 0 0 0 1 Table H.4-3: ICRP 74 at 1 ft - Location of Minimum Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -8 0 8 11 4 0 2 0 0 4 0 0 0 0 0 1 0 0 0 0 0 24 31 20 280 -16 0 0 0 0 0 0 16 0 0 0 0 0 2 Table H.4-4: ANSI 1977 at 3 ft - Location of Minimum Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -8 0 8 8 7 1 3 0 0 3 0 0 0 0 0 0 0 0 2 1 1 11 53 9 -16 0 0 0 0 0 0 16 0 0 0 0 0 0 Table H.4-5: ANSI 1991 at 3 ft - Location of Minimum Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -8 0 8 5 6 2 2 0 0 5 0 0 1 0 0 0 0 0 2 1 1 16 48 10 -16 0 0 0 0 0 0 16 0 0 0 0 0 0 Table H.4-6: ICRP 74 at 3 ft - Location of Minimum Dosimeter Values Relative Z (cm) 74 66 58 50 42 34 26 Y (cm) for Phantom Tally Plane -8 0 8 8 6 2 2 0 0 3 0 0 0 0 0 0 0 0 3 1 1 13 52 8 -16 0 0 0 0 0 0 16 0 0 0 0 0 0 281 Appendix I: Glove box Experiment at NETL 282 GLOVE BOX EXPERIMENT AT NETL Objectives The glove box experiment at Nuclear Engineering Teaching Laboratory (NETL) at the University of Texas consisted of the following: Setup of the glove box located in the reactor bay at NETL with a given neutron source and a field of LANL dosimeters arranged in specific locations around the glove box. Expose dosimeters for 24 hours. Measure the neutron radiation field at various locations using a He-3 proportional counter. Construct an MCNP model of the above glove box setup and calculate the neutron radiation dose field at the various dosimeter locations. Compare results of the computational analysis (iii.) with that of the experiment (i. & ii.). Repeat steps iii and iv. using an anthropomorphic computational phantom in place of the field of LANL dosimeters. EXPERIMENTAL SETUP Description of Glove box The glove box (Fig. I-1) used was located on the 2nd level of the reactor bay at NETL. The body of the glove box was approximately 182.88 cm x 116.84 cm x 81.76 cm (72 x 46" x 323/16") and the bottom of the glove box was 90.17 cm (35 ) above the floor. The glove box was constructed of 0.3175 cm (1/8 ) stainless steel while the viewing windows were 0.3175 cm (1/8 ) leaded glass. 283 The lower viewing window was 155.89 cm x 22.86 cm (613/8" x 9") and contained four glove ports, each with an inner diameter of 20.96 cm (8 "). The lower viewing window was symmetrically placed within a panel 40.64 cm x 182.9 cm (16" x 72"). Each pair of glove ports was centered 55.88 cm (22") from the nearest side edge with the centers of each gloveport in a pair 38.10 cm (15") apart. Figure I-1: Glove Box Used for Experiment On the floor of the glove box against the front inside surface was a row of lead bricks across the width of the glove box and wrapped in yellow tape, which also covered the floor of the glove box. 284 Neutron Source A plutonium-beryllium (PuBe13) neutron source, M-797, made by Monsanto Research Corporation (Hertz 1961) was chosen since it was the smallest activity source available. It contained 7.86 g of Be and 15.97 g of Pu uniformly mixed and doubly encapsulated as shown in Fig. I-2 (Profio 1976) with dimensions given in inches. The dimensions of the outer container were 1.02" outer diameter x 1.46" high (2.5908 cm x 3.7084 cm). The source strength was listed as 1.81 x 106 n/s. The neutron source was placed on the floor of the glove box on the centerline of the right-hand pair of glove ports 15 cm from the inside surface of the glove box (Fig. I-3). Figure I-2: Plutonium-Beryllium Neutron Source 285 Figure I-3: Source Positioned Within Glove box Description of Dosimeters Los Alamos utilizes Model 8823 whole-body thermoluminescent dosimeter (TLD) to measure personnel exposure to beta, gamma, and neutron sources of radiation. This is a dual card dosimeter. The upper card in the dosimeter contains four TLD elements and is used for estimating the beta and gamma doses. The lower card with four TLD elements is surrounded on all sides by a cadmium box except on the anterior side of two of the elements and posterior to the other two elements. The anterior side represents an anti-albedo detector that measures the thermal energy neutrons incident on the front of the detector while the posterior side represents a classic albedo detector measuring the thermal energy neutrons exiting the body. There is a severe angular dependence for neutrons when the angle of incidence greater than 30 . This dependence can reduce the dose measured to 25% or less of the dose measured at 0 (Mallett 1997). For radiation environments with high-energy neutron radiation fields, a track-etch dosimeter (TED) is used in conjunction with the Model 8823 dosimeter. The TED 286 is sensitive to neutron radiations only. A TED consists of a hemispherical-shaped plastic case that contains a triangular polystyrene pyramid with sides that are inclined 40 to the base. A track-etch plastic foil is placed on each side of the pyramid and the base. The purpose of this arrangement is to minimize the angular dependence of the TED. Set p of Dosimeter Field u A small metal table was placed in front of the pair of glove ports on the right-hand side of the glove box. On the table, two slabs of 5.1 cm (2 in.) thick polyethylene (poly) were setup the first 30.5 cm (1 ft) away from the glove box and the second 91.5 cm (3 ft) from the glove box. On each an array of dosimeters were taped on as shown in Fig. I-4. Figure I-4: Setup of Dosimeters in Front of the Glove box The round yellow dosimeters are the LANL track edge dosimeters (TED) while the rectangular black dosimeters are the LANL 8823 TLDs. Twenty two TEDs, #1-#22, were used with #8 and #10 used as controls. Twenty two TLDs were used, numbers 386, 413, 287 464, 607, 754, 283, 286, 310, 328, 336, 365, 831, 833, 950, 954, 956, 988, 998, 091, 128 with 372 and 074 used as controls. The dosimeters were placed in squares 8 cm x 8cm that were marked on the poly slabs. The relative positions of the dosimeters on the poly slabs facing the front of the glove box with their identification number are shown in Table I-1. Each dosimeter occupied an 8 cm x 8 cm square with the center of the dosimeter at the position shown relative to the bottom of the poly block. Absolute positions for the center of each dosimeter are also provided. Table I-1: Setup of Dosimeters in Front of the Glove box. Y (cm) for Poly Slab at 30.5 cm (1 ft) 4 12 20 31.56 23.56 15.56 16 286 413 19 18 833 464 17 21 831 22 998 9 956 2 754 7 310 Y (cm) for Poly Slab at 91.5 cm (3 ft) Z (cm) Relative -20 -12 -4 Relative Absolute 55.56 47.56 39.56 64 6.85 336 15 56 -1.15 20 365 48 -9.15 91 11 40 -17.15 13 950 32 -25.15 3 954 5 24 -33.15 328 1 988 16 -41.15 128 4 8 -49.15 14 283 On the left-hand side, one poly block was placed on top of another against the left-hand side with one TLD, #607, and one TED, #12, placed at about floor level of the glove box. On the right-hand side, a poly block was placed on a stool against the right-hand side with one TLD, #386, and one TED, #6, placed at about floor level of the glove box. Fig. I-5 shows the setup of all of the poly slabs in relation to the glove box. 288 The left edge of the blue line down the middle of the table represents the centerline of the right-hand glove ports on which the source was placed inside the glove box. Figure I-5: Setup of Dosimeters Around the Glove box Setup to Measure Neutron Radiation Field To measure the neutron radiation field, a RSN-105S-M9, a miniature Helium-3 filled detector welded to the end of a stainless steel cable sheath (Fig. I-6), was used (Richards 2003). The small size permits accurate flux plotting without excessive counting times and with small error from flux perturbation by the detector. It provides high sensitivity while permitting operation at low voltage. The basic radiation counting system consisted of the He-3 proportional counter, a high voltage power supply feeding a preamplifier, an amplifier with output to an 289 oscilloscope, a single channel analyzer, a scaler, and a counter. A block diagram for this system is shown in Fig. I-7 Figure I-6: Helium-3 Proportional Counter HVPS Scope He-3 Proportional Counter Pre-Amplifier Amplifier SCA Scaler Counter Figure I-7: Block Diagram of Counting System When the detector element absorbs energy from an incident neutron, it produces a pulse current whose integral is proportional to the absorbed energy. This integrated pulse is converted to a voltage pulse, and then shaped by the preamplifier. The shaping amplifier provides additional amplification. The output pulses from this amplifier go to a single channel analyzer which coupled with the 290 scaler allows for the counting of all neutrons above a desired energy threshold. Figure I-8 shows the counting system while Fig. I-9 shows the setup for the counting at one of the specified dosimeter positions. Figure I-8: Setup of Counting System Figure I-9: Setup of Proportional Counter at a Given Dosimeter Position 291 EXPERIMENTAL RESULTS Radiation Dose Field Determined by Dosimeters Before the experiment, all of the dosimeters were kept together. Two TLDs and two TEDs were kept back as controls. The remaining dosimeters were exposed for 24 hours to the neutron field from the M-797 neutron source. After the experiment and upon return to Los Alamos, the dosimeters were taken to HSR-4, Health Physics Measurements Group, and read. The data files received from HSR-4 are provided in Appendix J. Table I-2 provides the dosimeter readings in mrem by TLD badge number. For the dosimeters placed on the poly slabs in front of the glove box, Table I-3 provides the TLD readings in mrem by location. Table I-4 provides the dosimeter readings in mrem by TED badge number while Tables I-5 and I3-6 provide the readings (mean and base) for the TEDs by location while Table I-7 provides a summary of the dosimeter readings. Table I-2: Badge 74 91 128 283 286 310 328 336 365 372 386 TLD Readings in mrem by Badge Number. Neutron 0.000 14.000 20.000 12.000 31.000 44.000 19.000 14.000 19.000 0.000 39.000 Badge 413 464 607 754 831 833 950 954 956 988 998 Neutron 44.000 51.000 14.000 62.000 57.000 45.000 14.000 17.000 46.000 13.000 67.000 292 Table I-3: TLD Readings in mrem by location. Z (cm) Relative 64 56 48 40 32 24 16 8 Y (cm) for Poly Slab at 91.5 cm Relative -20 -12 Absolute 55.56 47.56 6.85 14 -1.15 -9.15 14 -17.15 -25.15 17 -33.15 19 -41.15 20 -49.15 -4 39.56 19 14 13 12 Y (cm) for Poly Slab at 30.5 cm 4 12 20 31.56 23.56 15.56 31 44 45 51 57 67 46 62 44 Table I-4: TED Readings in mrem by Dosimeter Number. Base Foil 71 300 57 59 61 183 191 -7 245 -8 48 Dosimeter Mean Number Pyramidal 12 17 13 32 14 31 15 24 16 69 17 114 18 85 19 79 20 29 21 146 22 119 Base Foil 22 60 55 48 106 195 144 107 45 257 181 Dosimeter Mean Number Pyramidal 1 36 2 169 3 31 4 35 5 26 6 123 7 116 8 -6 9 138 10 -6 11 26 293 Table I-5: TED (Mean) Readings in mrem by Location. Y (cm) for Poly Slab at 91.5 cm Y (cm) for Poly Slab at 30.5 cm Relative -20 -12 -4 4 12 20 Absolute 55.56 47.56 39.56 31.56 23.56 15.56 6.85 24 69 -1.15 29 79 -9.15 26 85 -17.15 32 114 -25.15 31 26 146 119 -33.15 36 138 -41.15 35 169 -49.15 31 116 Z (cm) Relative 64 56 48 40 32 24 16 8 Table I-6: TED (Base) Readings in mrem by Location. Y (cm) for Poly Slab at 91.5 cm Y (cm) for Poly Slab at 30.5 cm Relative -20 -12 -4 4 12 20 Absolute 55.56 47.56 39.56 31.56 23.56 15.56 6.85 48 106 -1.15 45 107 -9.15 48 144 -17.15 60 195 -25.15 57 61 257 181 -33.15 71 245 -41.15 59 300 -49.15 55 191 Z (cm) Relative 64 56 48 40 32 24 16 8 294 Table I-7: Summary of Dosimeter Readings in mrem. 30.5 cm (1 ft) TLD TED (mean) 67 169 44 79 50 115 TED (base) 300 107 192 91.5 cm (3 ft) TLD TED (mean) 20 36 12 26 16 30 TED (base) 71 45 56 Max Min Ave Radiation Dose Field Determined by He-3 Proportional Counter The neutron radiation field was measured at several of the dosimeter locations at 30.5 cm (1 ft) and 91.5 cm (3 ft). Most were recorded with the poly slabs in place. The proportional counter was held in place by a clamp on a ring stand (Figure I9). The sensitive portion of the detector was placed approximately where the middle of the dosimeter had been located based on the grids that had been drawn on the poly slabs. In a few cases, the poly slab was removed after the detector was setup and measurements made. A count time of 5 minutes was used. For various dosimeter positions, the measured counts are listed in Table I-8. To determine the background, the source was removed from the glove box, put into a shielded container, and moved to a far corner of the reactor bay. The detector was placed at position 831 at 30.5 cm (1 ft). A five minute count yielded 198 counts. An overnight run was then begun; however, through a miscommunication, the equipment was removed the next morning before the data could be recorded. According to Associate Director of NETL, Sean O'Kelly (2003), the background in the reactor bay is 40 ct/min. 295 Table I-8: Neutron Radiation Field Measurements in ct/min by Location. Y (cm) for Poly Slab at 91.5 cm Y (cm) for Poly Slab at 30.5 cm Z (cm) Relative 64 56 48 40 32 24 16 8 Relative Absolute 6.85 -1.15 -9.15 -17.15 -25.15 -33.15 -41.15 -49.15 -20 55.56 -12 47.56 28 -4 39.56 4 31.56 12 23.56 39.4 48.6 58.4 71.2 69.2 81.4 79 71.8 20 15.56 38.3 59.8 70.4 29.6 MCNP MODEL OF NETL EXPERIMENT An MCNP model of the glove box was constructed based on the materials of construction and dimensional measurements taken. Each polyethylene slab was modeled with a simulated dosimeter field corresponding to the experimental setup. The gloves for the glove ports were not modeled based on the fact that gloves contribute little to the attenuation of neutrons due to the thickness of the gloves and the location of the source. The neutron energy spectrum for the M-797 neutron source was calculated using SOURCES 4C (Wilson 2002). A mesh tally was used to simulate the dosimeter field that was setup for the experiment. The second computational model involved inserting a computational phantom in place of a poly slab and removing the remaining poly slabs from the model. Each phantom also has a dosimeter lattice in front of the torso to simulate the possible positions that a dosimeter can be worn. It is a planar lattice projected onto a vertical cylindrical surface that lies just off the surface of the torso (within ~ 5 cm of the torso depending on location on the cylindrical surface). Figure I-10 296 provides a longitudinal medial view of the phantom. Beside it is the dosimeter lattice that is placed over and around the torso of the phantom. The highlighted tally represents the middle of the torso where the dosimeter is most likely worn. Table I-9 provides the tally number associated with the positions on the lattice. Sample input decks are provided in Appendix K. Figure I-10: Computational Phantom with Dosimeter Lattice. COMPUTATIONAL RESULTS Calculated Dose Using Mesh Tally When a mesh tally is used, an output file "mdata" is created with the tally results. Using an auxiliary program called "gridconv", the data in this file is converted from a binary format into a text format that can be used in a spreadsheet or by a graphics package to plot the data. Table I.10 provides the calculated dose in mrem by location. 297 Table I-9: Tally Number in Dosimeter Lattice by Location. Relative Relative Y (cm) for Phantom Tally Plane Z (cm) -16 -8 0 8 74 66 58 50 42 34 26 32 82 132 182 232 282 2 42 92 142 192 242 292 12 52 102 152 202 252 302 22 62 112 162 212 262 312 16 72 122 172 222 272 322 Table I-10: Calculated Dose by Location on Poly Slabs in mrem per 24 hr. Relative Relative Y (cm) for Poly Slab at 91.5 cm Relative Y (cm) for Poly Slab at 30.5 cm Z (cm) -20 -12 -4 4 12 20 64 56 48 40 32 24 16 8 47.7 50.6 48.9 39.5 24.7 16.6 16.3 16.6 49.4 51.9 51.4 41.0 26.4 17.6 17.0 17.2 47.8 50.4 49.6 39.9 25.2 16.9 16.0 16.1 112.2 134.0 160.3 191.3 221.8 195.8 114.9 76.5 109.1 129.8 154.7 183.2 210.7 183.4 105.3 69.7 105.1 123.8 144.3 168.1 191.7 163.3 89.9 57.9 In the following figures, the dose field is given in mrem per the 24 hour exposure of the experiment. Figure I-11 provides the dose field for the dosimeter locations on the poly slab at 30.5 cm while Figure I-12 provides a planar view that includes the dosimeter grid shown in relation to the outline of the glove box with glove ports and the neutron dose field in that plane. Figures 3-13 through 3-18 provide the same views for the dosimeter grids located on the other poly slabs. 298 Figure I-11: Grid View of Field on Poly Slab at 30.5 cm. in Front of Glove Box. Figure I-12: Planar View of Field at 30.5 cm. in Front of Glove Box. 299 Figure I-13: Grid View of Field on Poly Slab at 91.5 cm. in Front of Glove Box. Figure I-14: Planar View of Field at 91.5 cm. in Front of Glove Box. 300 Figure I-15: Grid View of Field on Poly Slab on Left Side of Glove Box. Figure I-16: Planar View of Field on Poly Slab on Left Side of Glove Box. 301 Figure I-17: Grid View of Field on Poly Slab on Right Side of Glove Box. Figure I-18: Planar View of Field on Poly Slab on Right Side of Glove Box. 302 Estimated Dose Using Computational Phantom with its Dosimeter Lattice The computational phantom was placed with its center either 30.5 cm or 91.5 cm (1 ft or 3 ft) in front of the glove box. This places the dosimeter lattice about 17 cm closer to the source than the centerline of the phantom. Tables I-11 and I-12 provide these dose estimates using the dosimeter lattice for the phantom at 30.5 cm or 91.5 cm (1 ft or 3 ft) respectively while Figures I-19 and I-20 provide the radiation field at the same location as the phantom dosimeter lattice. Table I-11: Estimated Dose (mrem) with Dosimeter Lattice at 30.5 cm Relative Y (cm) for Phantom Tally Plane & Phantom at 30.5 Relative cm Z (cm) 74 66 58 50 42 34 26 -16 215.3 256.9 314.6 382.4 452.9 499.2 -8 129.8 168.7 212.8 274.6 347.6 443.1 538.8 0 121.8 160.7 208.9 268.8 353.2 460.7 580.3 8 127.9 169.4 213.6 273.3 349.1 445.1 542.3 16 212.5 257.0 318.7 379.5 458.7 497.5 Table I-12: Estimated Dose (mrem) using Dosimeter Lattice of Phantom at 91.5 Relative Y (cm) for Phantom Tally Plane & Phantom Relative at 91.5 cm Z (cm) 74 66 58 50 42 34 26 -16 76.4 82.3 85.8 84.7 65.6 38.3 -8 51.4 57.2 62.2 66.3 68.5 55.6 32.1 0 49.7 54.2 59.6 63.4 65.6 54.6 31.3 303 8 52.1 56.6 62.0 67.0 68.2 54.6 31.9 16 73.9 81.9 87.5 85.0 65.8 37.5 Figure I-19: Estimated Dose Field with Phantom Dosimeter Lattice at 30.5 cm. Figure I-20: Estimated Dose Field with Phantom Dosimeter Lattice at 91.5 cm. 304 In accordance with ICRP 26 (1977), the effective dose equivalent was calculated based on the organ and tissue doses. For comparison, the effective dose was calculated based on ICRP 60 (1991). Table I-13 provides a summary of the dose estimates in mrem based on the estimated dose received by the tissues and organs. Table I-13: Estimated Dose from Computational Phantom in mrem. 30.5 cm (1 ft) 91.5 cm (3 ft) EDE (ICRP 26) ED (ICRP 60) EDE (ICRP 26) ED (ICRP 60) Male with breasts 117.0 97.9 22.1 17.2 Male w/o breasts 92.4 89.6 15.2 14.9 Female 85.1 72.3 19.5 15.1 COMPARISON OF COMPUTATIONAL AND EXPERIMENTAL RESULTS Comparison of Neutron Radiation Field Measurements with TLD and TED Readings A comparison of the TED (base), TED (mean), and TLD readings normalized to the Y=12, Z=24 position compared to the normalized field measurements made by the neutron probe is provided in Table I-14. Table I-14: Comparison of Field Measurements with TLD and TED Readings. Relative Neutron probe cts/min Norm. 0.48 0.60 0.72 0.87 0.85 1.00 0.97 0.88 TED (mean) (mrem) norm 0.60 0.87 1.00 0.88 TED (base) (mrem) norm 0.44 TLD (mrem) norm 0.49 0.70 0.89 0.97 Z with Y=12 64 56 48 40 32 24 16 8 39.4 48.6 58.4 71.2 69.2 81.4 79 71.8 31 79 114 138 116 107 195 245 191 45 0.80 57 1.00 62 0.78 305 Thus, using normalized data, the field as determined by neutron probe matches closely with the field as determined by the dosimeters. This shows the validity of using dosimeter tally planes to provide the characteristics of the neutron radiation field. At the 1 ft plane, the radiation field varies by over a factor of 4 across the field. The field pattern in Fig. I-12 is primarily concentric circles except for that portion near the bottom of the glove box. This portion of the field shows the attenuation provided by Pb bricks that were in front of the source in the glove box. At 91.5 cm, the field is more uniform which should be expected since the distance has increased between the plane and the source. Comparison of TLD and TED Readings with Dosimeter Grids on Poly Slabs From Table I-3 and Table I-5, for the most part, the TLD readings are about half of the TED (mean) readings. A one-to-one comparison cannot be made because of the way the TLDs and TEDs were put onto the poly slabs they were next to each other and thus did not provide a measurement for the same location. Likewise, from Table I-4 and Table I-6, the TED (base) readings were greater than the TED (mean) readings by almost a factor of about 11/2. When compared with Table I-10, the estimated dose from the dosimeter grids more closely corresponded to the TED (base) readings than to the TED (mean) readings and was about a factor of two to three greater than the TLD readings in general. The TLD readings can be expected to be low because they are not designed to measure the dose received from a fast neutron spectrum whereas the TEDs are designed for fast neutrons. The chips in the TEDs formed a pyramid. Due to the way they were placed on the poly and due their specific location, the orientation of the faces of the pyramid to the source location varied. Thus, there is no specific 306 relationship between the TED readings and the dose from the dosimeter girds on the poly slabs except that the variation is in general agreement. This indicates that there may be a problem using the TLDs for determining dose when the neutron source is a fast spectrum than a thermal spectrum. Comparison of Dosimeter Grids on Poly Slabs with Phantom Dosimeter Lattice In comparing Tables I-10 and I-1, the values at the same location are similar except for the bottom three rows of the phantom dosimeter lattice. These values are larger than the corresponding values for the dosimeter grids at 30.5 cm. The predominant reason for this is that the dosimeter lattice is located about 17 cm in front of the centerline of the phantom, which is used as the location of the dosimeter grid. Thus, as shown in Figure I-19, the radiation field is more collimated than at the dosimeter grid as shown in Figure I-12. The collimation produces higher doses in the lower part of the lattice than in the upper half because of the location of the source relative to the grid and lattice. With the grid moved back, the radiation field broadens which results in higher doses in the upper half than in the bottom half of the grid. Comparison of Phantom Whole Body Dose with Other Estimates The phantom whole body dose at 30.5 cm was 92.4 mrem for a male without breasts. The TLD estimates were between 44 and 67 mrem with an average of 50 mrem, the TED (mean) estimates were between 70 and 169 with an average of 115 mrem, and the TED (base) estimates were between 107 and 300 mrem with an average of 192 mrem. At 91.5 cm, the phantom whole body was 19.5 mrem for a male without breasts. The TLD estimates were between 12 and 20 mrem with an average of 16 mrem, 307 the TED (mean) estimates were between 26 and 36 with an average of 30 mrem, and the TED (base) estimates were between 45 and 71 mrem with an average of 56 mrem. Thus, the TED (mean) readings came closer to the whole body estimate at a ft. while the TLD readings came closer to the whole body estimate at 91.5 cm. The computational estimates using dosimeter tally planes are closer to the TED (base) readings and thus are about a factor of 2 to 3 greater than the whole body dose estimates. Conclusions The whole body dose was better approximated by the TED (mean) readings than the TLD reading. This is to be expected since the mean energy of the neutron source was 4.85 MeV and TLDs were not designed for higher energy spectrums. Also, since there is a severe angular dependence based on the angle of incidence of the neutron on the TLD, the TLD readings may be low by a factor of four or more. The computational estimates using dosimeter tally planes or lattices were up to a factor of two to three higher than the whole body estimates. Since a dosimeter can be anywhere between waist and neck, this implies that the dose of record could easily be different depending on where the dosimeter is worn. Because of the way the experiment was setup, a direct comparison between many different estimates was not possible. Examples include TLDs and TEDs side by side, The dosimeter grid on the poly slabs was not filled with dosimeters in every position, and The dosimeter grid was setup offset from what the phantom tally lattice, 308 Bullet 3 is typical of the real world. It takes much thought to design an experiment that can be effectively modeled using MCNP. Most of the time, there are no experimental data that can be used to validate a given model. To model an existing operation and measure the radiation dose field to validate it is time consuming and something that no one is usually willing to pay for. 309 Appendix J: HSR-4 DOSIMETER DATA 310 APPENDIX J.1 Track Edge Dosimeter (Pn3 Or Ted) Data Good afternoon Art. Below are the results from the dosimeters you requested. Please bear in mind our LLD is 20 mRem. Also our Response Factor, tracks per square centimeter per mRem, is developed using foils exposed in the holder. When in the holder the foils are held at approximately a forty degree angle to the phantom. The base foil exposures included here have not been corrected for this. PN3 Data Date Read 7-May-03 Calc Date 7-May-03 If you have any questions please contact me. Rich McKeever Foil Foil Number 869316 869317 869296 869295 869264 869286 869307 869328 869232 869253 Wheel Position 4 5 6 7 8 9 10 11 12 13 Area Read 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 63 78 63 114 255 233 234 419 45 78 68 76 74 119 280 237 236 419 48 93 Zone 1 Zone 2 Pixelsum Foil Position 3219456 PL 3369557 PR 3384157 PB 3658399 Base 3932340 PL 3854497 PR 3729920 PB 4285039 Base 2911387 PL 3548035 PR Exposure (mRem) 33 41 35 71 186 161 161 300 18 48 BGRD Response Factor Dosimeter Mean Number Base Pyramidal Foil Exposure 36 Exposure 71 Tracks * cm^-2 Tr * cm^-2 * mRem ^-1 28 28 28 28 28 28 28 28 28 28 1.65 #1 1.65 1.65 1.65 1.65 #2 1.65 1.65 1.65 1.65 #3 1.65 169 300 31 57 311 Foil Foil Number 869274 869315 869222 869242 869243 869221 869252 869273 869294 869231 869241 869262 869283 869220 869293 869314 869251 869272 869292 869313 869230 869271 869240 869261 869282 Wheel Position 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 Area Read 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 62 93 74 67 70 103 59 53 61 106 203 255 143 260 293 140 142 253 17 15 10 15 270 129 247 57 103 66 75 61 98 55 50 63 100 169 214 124 269 248 129 98 296 13 17 13 12 234 108 242 Zone 1 Zone 2 Pixelsum Foil Position 3124783 PB 3432379 Base 3301020 PL 3188059 PR 3082452 PB 3172420 Base 3312930 PL 3110743 PR 3219699 PB 2970940 Base 3138027 PL 3568770 PR 3238521 PB 3541795 Base 3580025 PL 3121766 PR 3038811 PB 3805816 Base 3209615 PL 2988182 PR 2941882 PB 2872014 Base 3719170 PL 3329267 PR 3611236 PB Exposure (mRem) 28 57 36 37 33 59 26 22 30 61 124 161 84 183 188 85 74 191 -6 -5 -8 -7 174 73 168 BGRD Response Factor Dosimeter Mean Number Base Pyramidal Foil Exposure Exposure Tracks * cm^-2 Tr * cm^-2 * mRem ^-1 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 1.65 1.65 1.65 #4 1.65 1.65 1.65 1.65 #5 1.65 1.65 1.65 1.65 #6 1.65 1.65 1.65 1.65 #7 1.65 1.65 1.65 1.65 #8 1.65 1.65 1.65 1.65 #9 1.65 1.65 35 59 26 61 123 183 116 191 -6 -7 138 245 312 Foil Foil Number 869219 869216 869217 869218 869215 869312 869229 869250 869291 869237 869238 869239 869236 869228 869249 869270 869311 869247 869248 869269 869268 869289 869284 869263 869310 Wheel Position 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 21 22 23 24 25 26 27 28 Area Read 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 320 17 13 20 14 45 50 73 98 52 61 42 58 49 67 79 115 52 68 64 95 45 40 74 75 371 14 12 14 10 46 41 86 74 35 48 34 44 39 59 98 88 70 55 71 96 49 42 76 96 Zone 1 Zone 2 Pixelsum Foil Position 4032150 Base 2920809 PL 2944344 PR 3173403 PB 2924985 Base 2992532 PL 3157799 PR 3132155 PB 2946605 Base 3034040 PL 3268286 PR 3173680 PB 3080934 Base 2902643 PL 3185543 PR 3454198 PB 3297031 Base 3017569 PL 3041854 PR 3420175 PB 3192079 Base 3096132 PL 3217983 PR 3227690 PB 3131948 Base Exposure (mRem) 245 -5 -8 -4 -8 18 18 43 48 16 24 12 22 16 31 50 60 29 30 34 55 19 14 40 48 BGRD Response Factor Dosimeter Mean Number Base Pyramidal Foil Exposure Exposure Tracks * cm^-2 Tr * cm^-2 * mRem ^-1 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 1.65 1.65 #10 1.65 1.65 1.65 1.65 #11 1.65 1.65 1.65 1.65 #12 1.65 1.65 1.65 1.65 #13 1.65 1.65 1.65 1.65 #14 1.65 1.65 1.65 1.65 #15 1.65 1.65 1.65 -6 -8 26 48 17 22 32 60 31 55 24 48 313 Foil Foil Number 869303 869304 869305 869325 869259 869260 869265 869258 869279 869280 869281 869278 869285 869326 869306 869327 869300 869301 869302 869299 869322 869323 869324 869321 869244 Wheel Position 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 Area Read 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 81 63 207 179 168 100 260 280 128 72 251 216 113 65 221 154 56 68 72 77 178 150 329 362 239 75 46 207 145 159 78 275 279 104 41 211 208 116 50 195 173 36 60 72 87 194 140 302 361 235 Zone 1 Zone 2 Pixelsum Foil Position 3127587 PL 2900150 PR 3637125 PB 3355048 Base 3313327 PL 3159456 PR 3993458 PB 3965586 Base 3449046 PL 3212134 PR 3681560 PB 3558515 Base 3387793 PL 3133253 PR 3487215 PB 3396949 Base 3021095 PL 3035411 PR 3055297 PB 3055491 Base 3317090 PL 3240845 PR 3910636 PB 3784971 Base 3657592 PL Exposure (mRem) 42 24 140 106 107 50 186 195 71 26 158 144 70 27 141 107 18 32 38 45 124 93 222 257 163 BGRD Response Factor Dosimeter Mean Number Base Pyramidal Foil Exposure 69 Exposure 106 Tracks * cm^-2 Tr * cm^-2 * mRem ^-1 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 1.65 #16 1.65 1.65 1.65 1.65 #17 1.65 1.65 1.65 1.65 #18 1.65 1.65 1.65 1.65 #19 1.65 1.65 1.65 1.65 #20 1.65 1.65 1.65 1.65 #21 1.65 1.65 1.65 1.65 #22 114 195 85 144 79 107 29 45 146 257 119 181 314 Foil Foil Number 869266 869245 869223 Wheel Position 54 55 56 Area Read 1.6 1.6 1.6 94 195 246 104 210 277 Zone 1 Zone 2 Pixelsum Foil Position 3124036 PR 3431066 PB 3510288 Base Exposure (mRem) 58 136 181 BGRD Response Factor Dosimeter Mean Number Base Pyramidal Foil Exposure Exposure Tracks * cm^-2 Tr * cm^-2 * mRem ^-1 28 28 28 1.65 1.65 1.65 315 APPENDIX J.2 TLD Data U T AUSTIN EXPERIMENT TLD Data Read Date 5 May 2003 Calc Date 5 May 2003 Badge 36386 36413 36464 36607 36754 37283 37286 37310 37328 37336 37365 37372 37831 37833 37950 37954 37956 Shallow 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Deep 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Neutron 39.000 44.000 51.000 14.000 62.000 12.000 31.000 44.000 19.000 14.000 19.000 0.000 57.000 45.000 14.000 17.000 46.000 Lens 43.000 45.000 52.000 14.000 63.000 12.000 32.000 46.000 19.000 14.000 19.000 0.000 57.000 47.000 14.000 17.000 47.000 NCR1 1.905 -6.185 -3.731 -5.167 -0.216 -7.407 -4.996 -2.544 -8.160 -5.300 -7.036 -9.810 -2.138 -1.465 -7.351 -4.763 -2.416 NCR2 -1.567 2.575 -3.286 -6.566 -2.538 34.222 -4.795 -1.587 -6.675 -6.433 -3.078 -6.005 -1.805 -4.557 -3.811 -3.252 0.242 NCR3 1.334 -4.792 -6.421 -12.037 -7.374 -12.830 -5.675 -5.210 -13.099 -8.857 -9.718 -4.232 -7.039 -11.616 -11.401 -7.713 -4.613 NCR4 8.067 1.125 -0.617 -1.851 3.519 -1.137 0.067 1.907 -2.885 -1.317 -1.197 -3.663 0.678 1.638 -2.669 -3.925 -1.359 NCR5 41.121 23.983 30.125 13.365 31.578 20.078 29.074 26.534 18.740 17.364 22.626 1.100 31.428 35.332 24.529 25.689 35.360 NCR6 8.207 2.004 3.113 0.704 5.442 -0.739 3.232 4.733 0.781 0.349 13.608 0.784 1.842 3.376 0.177 0.374 3.124 NCR7 6.333 0.620 2.213 -0.211 1.198 -0.938 1.152 3.043 0.470 0.079 0.484 -0.171 0.692 2.074 -0.638 0.663 2.518 NCR8 83.432 72.995 87.948 27.906 96.431 29.439 62.359 74.639 39.327 31.321 31.116 0.691 95.181 86.528 35.297 41.204 88.132 316 Badge 37988 37998 38074 38091 38128 Shallow 0 0 0 0 0 Deep 0 0 0 0 0 Neutron 13.000 67.000 0.000 14.000 20.000 Lens 13.000 69.000 0.000 14.000 20.000 NCR1 -0.218 -5.055 -6.310 -0.362 -2.079 NCR2 5.481 -9.044 -5.800 0.144 -4.174 NCR3 -5.728 -5.343 -10.654 -11.814 -3.345 NCR4 -0.326 0.101 -3.379 -2.822 -0.080 NCR5 22.341 34.929 0.472 18.278 20.397 NCR6 -0.098 4.217 -1.616 -0.645 8.642 NCR7 -0.062 2.484 0.110 -1.764 -0.046 NCR8 32.503 108.889 1.733 32.564 34.426 317 Appendix K: SOURCES 4C and MCNP Input Files 318 APPENDIX K.1 SOURCES 4C Input File For Calculation of Neutron Spectrum of M-797 m-797 PuBe Source 1 2 1 3 0 004 0.92883861 094 0.07113660 095 0.00002470 -63 50.0 0.0 5.000E+01 4.500E+01 4.000E+01 3.500E+01 3.000E+01 2.750E+01 2.500E+01 2.250E+01 2.000E+01 1.750E+01 1.690E+01 1.490E+01 1.350E+01 1.160E+01 1.000E+01 8.610E+00 7.410E+00 6.070E+00 4.970E+00 3.680E+00 2.870E+00 2.230E+00 1.740E+00 1.350E+00 1.110E+00 8.210E-01 6.390E-01 4.980E-01 3.880E-01 3.020E-01 1.830E-01 1.110E-01 6.740E-02 4.090E-02 2.550E-02 1.990E-02 1.500E-02 9.120E-03 319 5.530E-03 3.350E-03 2.840E-03 2.400E-03 2.030E-03 1.230E-03 7.490E-04 4.540E-04 2.750E-04 1.670E-04 1.010E-04 6.140E-05 3.720E-05 2.260E-05 1.370E-05 8.310E-06 5.040E-06 3.060E-06 1.860E-06 1.130E-06 6.830E-07 4.140E-07 2.510E-07 1.520E-07 9.240E-08 5 0942380 0942390 0942400 0942410 0952410 1 4000 0040090 1.73E+18 5.24E+21 2.78E+20 2.20E+19 1.92E+18 0.9288 320 APPENDIX K.2 MCNP Input File: NETL Glove box with Dosimeter Mesh Tally UTGB c c Glove box at University of Texas c Model of experiment conducted during trip of 4/22/03 - 5/01/03 c Source PuBe source M-797 c Mesh tally for dosimeters located on poly block 1' in front of GB with c right edge of poly block on center line between right glove port pair c c ****************************************************************************** c CELL CARDS c ****************************************************************************** c c Inside Glove box c 1 1 -0.001 2 -5 32 -34 54 -59 #2 imp:n=1 $ Air inside GB 2 2 -11.35 2 -5 33 -34 54 -55 imp:n=1 $ Pb bricks inside GB c c Shell c 3 3 -8.00 1 -6 31- 35 53 -54 imp:n=1 $ Bottom 4 3 -8.00 1 -6 31- 35 59 -60 imp:n=1 $ Top 5 3 -8.00 5 -6 31- 35 54 -59 imp:n=1 $ Right 6 3 -8.00 1 -2 31- 35 54 -59 imp:n=1 $ Left 7 3 -8.00 (2 -5 34 -35 54 -59) (-3:4:-34:35:-56:57) imp:n=1 $ Front 8 3 -8.00 2 -5 31 -32 54 -59 imp:n=1 $ Back c c Window and Gloveports c 9 4 -3.76 3 -4 34- 35 56 -57 #10 #11 #12 #13 imp:n=1 $ Window 10 0 34 -35 -21 imp:n=1 $ Left Glovepport 11 0 34 -35 -22 imp:n=1 $ Middle Left Glovepport 12 0 34 -35 -23 imp:n=1 $ Middle Right Glovepport 13 0 34 -35 -24 imp:n=1 $ Right Glovepport c c c Poly Slabs c 14 5 -0.92 7 -8 36 -37 51 -58 imp:n=1 $PL - Poly on left side 15 5 -0.92 9 -10 38 -39 52 -58 imp:n=1 $PR - Poly on right side 16 5 -0.92 11 -12 40 -41 52 -58 imp:n=1 $PL - Poly on left side 17 5 -0.92 12 -13 42 -43 52 -58 imp:n=1 $PL - Poly on left side c c Universe c 98 1 -0.001 -99 (-1:6:-31:35:-53:60)#14 #15 #16 #17 imp:n=1 $ 321 99 0 99 imp:n=0 $ Outside world c c ****************************************************************************** c END OF CELL CARDS c ****************************************************************************** c ****************************************************************************** c SURFACE CARDS c ****************************************************************************** c cY c 1 py -91.44 2 py -91.1225 3 py -78.105 4 py 78.105 5 py 91.1225 6 py 91.44 7 py -98.7425 8 py -93.6625 9 py 93.6625 10 py 98.7425 11 py 8.89 12 py 35.56 13 py 62.23 c c Glove Ports - Front 21 c/x -54.61 -22.86 10.795 22 c/x -16.61 -22.86 10.795 23 c/x 16.61 -22.86 10.795 24 c/x 54.61 -22.86 10.795 c cX c 31 px -58.42 32 px -58.102 33 px 47.9425 34 px 58.1025 35 px 58.42 36 px 28.575 37 px 55.245 38 px 25.40 39 px 52.07 40 px 88.90 41 px 93.98 42 px 149.86 43 px 154.94 c cZ c 51 pz -133.35 52 pz -57.15 53 pz -43.18 322 54 pz -42.8625 55 pz -37.7825 56 pz -34.29 57 pz -11.43 58 pz 39.37 59 pz 42.8625 60 pz 43.18 c c Universe c 99 so 1000 c c ****************************************************************************** c END OF SURFACE CARDS c ****************************************************************************** c c c ****************************************************************************** c MATERIAL CARDS c ****************************************************************************** c c c Dry air (density = 0.00098 g/cc at Los Alamos) c Reference: CRC Handbook of Chemistry and Physics and c CRC Handbook of tables for Applied Engineering Science c Nuclide composition in ATOM FRACTION m1 7014 0.782315 $ Nitrogen N14 7015 0.002905 $ Nitrogen N15 8016 0.209966 $ Oxygen O16 8017 0.000080 $ Oxygen O17 18000.59c 0.004734 $ Argon Ar-nat nlib=60c plib=02p elib=03e cond=0 c c c c c Lead (density = 11.35 g/cc) c Nuclide composition in ATOM FRACTION c Reference: c m2 82000.42c 1.00 $lead Pb-nat nlib=60c plib=02p elib=01e cond=0 c c c Stainless Steel Type 304 Stainless Steel (density = 8.0 g/cc). c Nuclide composition in ATOM FRACTION c Reference: METALS HANDBOOK Tenth Edition pp. 843 & 871 m3 6000 0.003635 $ Carbon C-nat 14000 0.019431 $ Silicon Si-nat 15031 0.000793 $ Phosphorus P31 16000 0.000511 $ Sulfur S-nat 24050 0.008665 $ Chromium Cr50 323 24052 0.167091 $ Chromium Cr52 24053 0.018947 $ Chromium Cr53 24054 0.004716 $ Chromium Cr54 25055 0.019867 $ Manganese Mn55 26054 0.039181 $ Iron Fe54 26056 0.615060 $ Iron Fe56 26057 0.014204 $ Iron Fe57 26058 0.001890 $ Iron Fe58 28058 0.058551 $ Nickel Ni58 28060 0.022554 $ Nickel Ni60 28061 0.000980 $ Nickel Ni61 28062 0.003126 $ Nickel Ni62 28064 0.000796 $ Nickel Ni64 nlib=60c plib=02p elib=03e cond=1 c c c c c c c c c m4 Leaded Glass (density = 3.76 g/cc) Nuclide composition in ATOM FRACTION Reference: Askeland, Donald R., The Science and Engineering of Materials, 3rd ed., Table 14-2, p. 449 (1994) composition data Dean, John A., Lange's Handbook of Chemistry, 14th ed., Table 3.2, pp. 3.12-3.63, McGraw-Hill Inc.(1992) density data Approximate Thickness of glass (mm) per mm lead equivalent = 1.9 8016 0.610814 $ oxygen O16 8017 0.000244 $ oxygen O17 11023 0.047148 $ sodium Na23 14000 0.271543 $ silicon Si-nat 19000 0.051704 $ potassium K-nat 82000.42c 0.018547 $lead Pb-nat nlib=60c plib=02p elib=01e cond=0 c c c Polyethylene (density = 0.92 g/cc). c Nuclide composition in ATOM FRACTION c Reference:Harmon II, Charles D., et al., "Criticality Calculations with c MCNP: A Primer", Appendix C, LANL, LA-12827-M, August 1994. m5 1001 0.666584 $ Hydrogen H1 1002 0.000100 $ Hydrogen H2 6000 0.333316 $ Carbon C-nat nlib=60c plib=02p elib=03e cond=-1 c c c c ****************************************************************************** c END OF MATERIAL CARDS c ****************************************************************************** c c c ****************************************************************************** c SOURCE CARDS c ****************************************************************************** c c 324 mode n phys:n 20 cut:n j 0 phys:p 100 cut:p j 0.01 c c Neutron energy spectra for M-797 PuBe neutron source c Be - 7.86 g c Pu - 15.97 g c Dimensions of container: 1.02" o.d. x 1.46" high c Container material: Ta and SS c Thickness: Ta c Calibrated 07 Nov 1961 c Total neutron emission = 1.75E+06 neutrons/s c sdef par=1 pos= 43.1025 35.56 -39.1541 erg=d8 # si8 sp8 h d 1.00E-11 0. 1.00E-02 1.47E+00 2.00E-02 4.25E+00 5.00E-02 2.53E+01 1.00E-01 7.62E+01 2.00E-01 2.29E+02 4.00E-01 3.81E+03 6.00E-01 1.57E+04 8.00E-01 2.39E+04 1.00E+00 2.59E+04 1.30E+00 3.83E+04 1.70E+00 3.87E+04 2.10E+00 4.67E+04 2.40E+00 4.65E+04 2.70E+00 5.67E+04 3.00E+00 9.16E+04 3.30E+00 1.17E+05 3.60E+00 1.10E+05 4.00E+00 1.35E+05 4.40E+00 1.23E+05 5.00E+00 1.65E+05 6.00E+00 1.65E+05 7.00E+00 1.53E+05 8.00E+00 1.73E+05 9.00E+00 1.30E+05 1.00E+01 7.86E+04 1.20E+01 1.08E+04 1.50E+01 7.41E-02 2.00E+01 4.22E-03 c Total 1.75E+06 c c c ****************************************************************************** c END OF SOURCE CARDS c ****************************************************************************** 325 c c c c ****************************************************************************** c TALLY CARDS c ****************************************************************************** c c c Multiplier for dose-rate conversion = c [(1.75E+06 src_neutrons/s)/(kg Pu)] x [X tally_neutrons/(src_neutron*cm^2)] x c [(Y*E-12 Sv cm^2)/(tally neutron)]x(100 rem/Sv)x(3600 s/h)x(1000 mrem/rem) x c 24 h = 1.512E+4*XY mrem c c *************************************************************************** c c AP - Neutron Fluence-to Effective-Dose-Equivalent Conversion factors vs c Energy from ANSI/ANS-6.1.1-1977 for AP exposure geomertry. Energy units c in MeV and conversion-factors units are 1.0e-12Sv-cm^2. c de0 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 c df0 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c tmesh rmesh1:n cora1 87.4 88.4 corb1 -100 24i 100 corc1 -140 34i 140 endmd fm1 1.512E+4 c c c c ****************************************************************************** c END OF TALLY CARDS c ****************************************************************************** c dbcn 12j 137753 prdmp j 5e7 j 1 ctme 9999 nps 1e8 print 10 40 50 60 110 140 160 161 162 170 326 APPENDIX K.3 MCNP Input File: NETL Glove box with Phantom and Dosimeter Tally Plane UTP1 c c Glove box at University of Texas c Model of experiment conducted during trip of 4/22/03 - 5/01/03 c Source PuBe source M-797 c Phantom at 1 ft in front of glove box on centerline of source c c ************************************************************************ ****** c CELL CARDS c ************************************************************************ ****** c c Inside Glove box c 1001 1 -0.001 1002 -1005 1032 -1034 1054 -1059 #1002 $ Air inside GB 1002 2 -11.35 1002 -1005 1033 -1034 1054 -1055 $ Pb bricks inside GB c c Shell c 1003 3 -8.00 1001 -1006 1031 -1035 1053 -1054 $ Bottom 1004 3 -8.00 1001 -1006 1031 -1035 1059 -1060 $ Top 1005 3 -8.00 1005 -1006 1031 -1035 1054 -1059 $ Right 1006 3 -8.00 1001 -1002 1031 -1035 1054 -1059 $ Left 1007 3 -8.00 (1002 -1005 1034 -1035 1054 -1059) (-1003:1004:-1034:1035:-1056:1057) $ Front 1008 3 -8.00 1002 -1005 1031 -1032 1054 -1059 $ Back c c Window and Gloveports c 1009 4 -3.76 1003 -1004 1034 -1035 1056 -1057 #1010 #1011 #1012 #1013 $ Window 1010 0 1034 -1035 -1021 $ Left Glovepport 1011 0 1034 -1035 -1022 $ Middle Left Glovepport 1012 0 1034 -1035 -1023 $ Middle Right Glovepport 1013 0 1034 -1035 -1024 $ Right Glovepport 327 c c c Poly Slabs c c 1014 5 -0.92 1007 -1008 1036 -1037 1051 -1058 $PL - Poly on left side c 1015 5 -0.92 1009 -1010 1038 -1039 1052 -1058 $PR - Poly on right side c 1016 5 -0.92 1011 -1012 1040 -1041 1052 -1058 $PL - Poly on left side c 1017 5 -0.92 1012 -1013 1042 -1043 1052 -1058 $PL - Poly on left side c c Universe c 1098 1 -0.001 -1099 (-1001:1006:-1031:1035:-1053:1060) #900 $ c c c ************************************************************************ ****** c Male Phanton cells Body Builder c Height: 179 cm , Weight 73.54 kg, 0 cm extra torso fat c ************************************************************************ ****** c SkeletonVolume = 7218.700000, skel_vol = 7142.857143 c c LEG BONES 50 11 -1.40 -4 53 (-51 : -52 ) u=2 vol=2800.00 c c ARM BONES 70 11 -1.40 4 -73 (-71 : -72 ) u=2 vol=956.00 c c PELVIS 90 11 -1.40 91 -92 93 4 -101 ( 95 : -94 ) u=2 vol=606.00 c c SPINE ( Total Spine vol=983.00 ) 100 11 -1.40 -100 -103 101 u=2 vol=206.14 101 11 -1.40 -100 -8 103 u=2 vol=554.90 102 11 -1.40 -105 -102 8 u=2 vol=221.96 c c SKULL & FACE 110 11 -1.40 (111 -110):(121 -120 122 -1 -123 110) u=2 vol=923.00 c c RIBS 130 11 -1.40 132 -131 ((134 -133):(136 -135):(138 -137):(74 -139): (76 -75):(78 -77):(80 -79):(82 -81):(332 -83): 328 (86 -85):(88 -87):(98 -89)) u=2 vol=694.00 c c CLAVICLES 140 11 -1.40 -140 ((141 -143):(-142 144)) u=2 vol=54.70 c c SCAPULAE 150 11 -1.40 131 -156 154 -155 ((150 -152):(-151 153)) u=2 vol=202.00 c c ******************************************************************** c ADRENALS 160 10 -1.04 162 (-160:-161) u=2 vol=15.70 c c BRAIN 180 10 -1.04 -111 u=2 vol=1370.00 c c BREAST 190 10 -1.04 11(-192:-193) u=2 vol =337.00 c c GALL BLADDER 200 10 -1.04 (-202 -200):(202 -201 -203) u=2 vol=63.70 c c ESOPHAGUS 212 10 -1.04 213 -212 322 -8 100 : -216 217 -218 210 350 100 u=2 vol=44.70 c Air in Upper Esophagus 213 10 -1.04 -213 322 -8 u=2 c c STOMACH 210 10 -1.04 -210 u=2 vol=402.00 c c SMALL INTESTINE (exclude Ascending Colon, Transverse Colon, c and Descending Colon) 220 10 -1.04 -91 221 -222 223 -7 (232:230:-223)(240 :241 :-242 ) (232:250:-223) u=2 vol=1060.00 c c ASCENDING COLON 230 10 -1.04 -230 231 -232 u=2 vol=187.50 c c TRANSVERSE COLON 240 10 -1.04 -240 -241 242 u=2 vol=248.00 c c DESCENDING COLON 250 10 -1.04 -250 251 -232 u=2 vol=191.90 c SIGMOID COLON (Vol=106.0 cm^3) 280 1 -1.04 (-280 282 -251):(-281 -282 4) u=2 vol=106.0 329 c c HEART c 290 1 -1.04 (290((-291 -292):(291 -293))): (-290((-291 -295):(291 -294))) u=2 vol=740.0 c c KIDNEYS 310 10 -1.04 (-310 282 -162):(-311 -313 -162) u=2 vol=288.00 c c LIVER 320 10 -1.04 -320 -321 7 -322 -132 u=2 vol=1830.00 c c LUNGS 330 3 -0.296 332 ((-331 (-335:336:334:-333)): (-330 ( 339:338:337))) u=2 vol=3380.00 c c Ovaries 340 10 -1.04 -340:-341 u=2 vol=8.38 c c PANCREAS 350 10 -1.04 -350 351 (352:-282) u=2 vol=90.70 c c SPLEEN 360 10 -1.04 -360 u=2 vol=176.00 c c TESTICLES 370 10 -1.04 -370:-371 u=2 vol=37.60 c c THYMUS 380 10 -1.04 -380 u=2 vol=20.10 c c THYROID 390 10 -1.04 -390 391 -392 -393 8 u=2 vol=19.90 c c URINARY BLADDER 410 10 -1.04 -410 u=2 vol=248.70 c c UTERUS 420 10 -1.04 -420 421 u=2 vol=76.00 c c PENIS & SCROTUM 40 10 -1.04 -1 -4 47 -45 49 -48 37 38 370 371 u=2 vol=158.40 $ exclude Testicles c 330 c ************************************************************************ ****** c c SKIN c c Head & Neck Skin 22 10 -1.04 ((-21 22 9):(-20 23 -9 12)) u=2 vol = 259.26 28 10 -1.04 28 -27 8 -12 u=2 vol=58.74 c c Trunk Skin (exclude breast) 17 10 -1.04 (-8 18 20 -10):(4 -18 -10 11 192 193) u=2 vol=1440.00 c c Breast Skin 192 10 -1.04 10 ((-190 192):(-191 193)) u=2 vol 51.00 c c Penis & Scrotum Skin 41 10 -1.04 -1 -4 41 -42 43 -44 31 32 #40 370 371 u=2 vol=23.40 $ exclude Testicles c c Legs Skin 34 10 -1.04 (-4 34 -31 36):(-31 33 -36) u=2 vol=605.00 35 10 -1.04 (-4 35 -32 36):(-32 33 -36) u=2 vol=605.00 c c ************************************************************************ ****** c c HEAD (exclude Skull & Brain, Face Bones, Spine & Thyroid) 20 10 -1.04 ((-22 9):(-23 -9 12)) 110 (-121:120:-122:1:123:-110)(105:-8:102) (390:-391:392:393:-8) u=2 c c NECK (exclude Spine & Thyroid) 27 10 -1.04 -28 8 -12 105 (390:-391:392:393:-8) u=2 c c OUTER TRUNK-ARMS & SCAPULAE (excluded Scapulae and Arm Bones) 10 10 -1.04 4 131 -18 -11 (-131:156:-150:152:-154:155) (-131:156:151:-153:-154:155)(-4:71:73) (-4:72:73) u=2 c c UPPER TRUNK-ABOVE RIBS (exclude Spine, Clavicles, Upper Lungs, c Thymus and Esophagus 11 10 -1.04 ((-18 -131 133):(-8 18 -20 -10)) (105:102:-8)(100:8:-133) (140:-141:143) (140:142:-144) (-133:330) (-133:331) 380 #212 #213 u=2 c 331 c UPPER RIB CAGE (exclude ribs 1-9 12 10 -1.04 -131 132 79 -133 (131:-132:133:-134) (131:-132:135:-136) (131:-132:137:-138) (131:-132:139:-74) (131:-132:75:-76) (131:-132:77:-78) u=2 c c LOWER RIB CAGE (exclude ribs 10-12) 13 10 -1.04 -131 132 -79 98 (131:-132:85:-86) (131:-132:87:-88) (131:-132:89:-98) (131:-132:79:-80) (131:-132:81:-82) (131:-132:83:-332) u=2 c c HIGH CHEST ORGANS (exclude Spine, Heart, Lungs, Thymus and Esophagus) 14 10 -1.04 -132 -133 332 (100:133:-332) #290 (330:133:-332: (-339 -338 -337)) (331:133:-332:(335 -336 -334 333)) 380 #212 #213 u=2 c c CHEST---LIVER LEVEL (exclude spine, Adrenals, Gall Bladder, Kidneys, c Liver, Pancreas, Spleen, Esophagus & Stomach) 15 10 -1.04 (-132 -332 103 : -131 -103 7 ) ( 100 : 332 : -7 ) ( 160 : -162 ) ( 161 : -162 ) ( 202 : 200 ) (-202 : 201 : 203 ) ( 310 : -282 ) ( 311 : 313 ) ( 320 : 321 : -7 : 322 : 132 ) ( 350 : -351 : -352 282 ) 360 (-213 : 212 : -322 : 8 : -100 ) ( 216 : -217 : 218 : -210 : -350 : -100 ) ( 213 : -322 : 8 ) 210 u=2 c c LOWER TRUNK (exclude Spine, Pelvis, Small Intestine, Ascending Colon c Descending Colon, Sigmoid Colon,Urinary Bladder, uterus c & ovaries) 16 10 -1.04 -131 4 -7 (100:-101:7) #90 (91:-221:222:-223:7) (232:230:-231) (232:250:-251)(280:-282:251) (281:282:-4) (420:-421) 340 341 410 u=2 c c LEGS (exclude leg bones) 30 10 -1.04 -4 (-34:-35) 36 (4:51:-53) (4:52:-53) u=2 vol= 16790.00 c c SURROUNDING AIR exclude Head, Neck, Trunk and legs) 600 1 -0.001 -600 c Exclude Head and Neck (21:-9) (20:9:-8) c Exclude Trunk (-4:10:8) c Exclude Breasts (-10:(190 191)) c Exclude Legs 332 c (4:-33:(31 32)) Exclude Genitalia (1:4:-41:42:-43:44:-31:-32) #700 u=2 c c Air OUTSIDE of NECK 601 1 -0.001 -20 27 8 -12 u=2 c c Anterior Phantom Dosimetry Cell 700 1 -0.001 486 -485 -1 478 -470 u=2 c c Cylindrical cell for phantom universe 900 0 -500 1051 -502 fill=2 c 1099 0 1099 $ Outside world c c ************************************************************************ ****** c END OF CELL CARDS c ************************************************************************ ****** c ************************************************************************ ****** c SURFACE CARDS c ************************************************************************ ****** c cY c 1001 py -91.44 1002 py -91.1225 1003 py -78.105 1004 py 78.105 1005 py 91.1225 1006 py 91.44 1007 py -98.7425 1008 py -93.6625 1009 py 93.6625 1010 py 98.7425 1011 py 8.89 333 1012 py 35.56 1013 py 62.23 c c Glove Ports - Front 1021 c/x -54.61 110.49 10.795 1022 c/x -16.61 110.49 10.795 1023 c/x 16.61 110.49 10.795 1024 c/x 54.61 110.49 10.795 c cX c 1031 px -58.42 1032 px -58.102 1033 px 47.9425 1034 px 58.1025 1035 px 58.42 1036 px 28.575 1037 px 55.245 1038 px 25.40 1039 px 52.07 1040 px 88.90 1041 px 93.98 1042 px 149.86 1043 px 154.94 c cZ c 1051 pz 0 1052 pz 76.2 1053 pz 90.17 1054 pz 90.4875 1055 pz 95.5675 1056 pz 99.06 1057 pz 121.92 1058 pz 172.72 1059 pz 176.2125 1060 pz 176.53 c c Universe c 1099 so 1000 c c 334 c ************************************************************************ ****** c Male Phanton Surfaces (Body Builder) c ************************************************************************ ****** c Planes used in several places c 1 69 py 0 4 69 pz 0 332 69 pz 43.5000 7 69 pz 27.0000 8 69 pz 70.0000 9 69 pz 91.4500 12 69 pz 78.4000 c c ******************************************* c BODY SURFACE c c HEAD 21 69 sq 1.54729 1 1.92586 0. 0. 0. -104.04 0 0 91.45 22 69 sq 1.5625 1 1.95609 0. 0. 0. -100 0 0 91.45 20 69 sq 1.54729 1 0 0. 0. 0. -104.04 0 0 0 23 69 sq 1.5625 1 0 0. 0. 0. -100 0 0 0 c c NECK 27 69 cz 5.6000 28 69 cz 5.4000 c c TORSO 10 69 sq 1 3.92195 0 0. 0. 0. -408.04 0 0 0 11 69 sq 1 4 0 0. 0. 0. -400 0 0 0 18 69 pz 69.8000 c c LEGS 31 69 gq 1 1 0 0 0 -0.2000 -20.2000 0 0 0 32 69 gq 1 1 0 0 0 0.2000 20.2000 0 0 0 33 69 pz -80.200 34 69 gq 1 1 0 0 0 -0.2000 -20.0000 0 0 0 35 69 gq 1 1 0 0 0 0.2000 20.0000 0 0 0 36 69 pz -80.000 37 69 gq 1 1 0 0 0 -0.2000 -20.4000 0 0 0 38 69 gq 1 1 0 0 0 0.2000 20.4000 0 0 0 335 c c PENIS & SCROTUM 41 69 pz -4.8 42 69 p 0 -10 -1 100 43 69 p -10 0 1 -100 44 69 p -10 0 -1 100 47 69 pz -4.6 45 69 p 0 -10.1 -1 100 49 69 p -10.1 0 1 -100 48 69 p -10.1 0 -1 100 c c ************************************************************************ ****** c SKELETON c LEG BONES 51 69 gq 1 1 0.009069 0 0 -0.200501 -20.000000 0 1.785714 87.7500 52 69 gq 1 1 0.009069 0 0 0.200501 20.000000 0 1.785714 87.7500 53 69 pz -79.8000 c c ARM BONES ( left/right) ) 71 69 gq 0.510204 0.137174 0 0 0 0.010352 -19.489796 0 -0.204969 185.877551 72 69 gq 0.510204 0.137174 0 0 0 -0.010352 19.489796 0 -0.204969 185.877551 73 69 pz 69.0000 c c PELVIS 91 69 sq 1 1 0 0. 0. 0. -127.69 0 -3.8 0 92 69 sq 1 1 0 0. 0. 0. -144 0 -3 0 93 69 py -3.0000 94 69 py 5.0000 95 69 pz 14.0000 c c SPINE 100 69 sq 1.5625 1 0 0. 0. 0 -6.25 0 5.5 0 105 69 sq 1.5625 1 0 0. 0. 0. -6.25 0 1.45 0 101 69 pz 22.0000 102 69 pz 84.8000 103 69 pz 35.1000 c c SKELETON c SKULL (head) c CRANIUM 336 110 111 c c 120 121 122 123 c c 131 132 133 134 135 136 137 138 139 74 75 76 77 78 79 80 81 82 83 85 86 87 88 89 98 c c 140 141 142 143 144 c c 69 sq 1.60444 1 2.04082 0. 0. 0. -90.25 0 0 91.45 69 sq 1.69789 1 2.23698 0. 0. 0. -73.96 0 0 91.45 FACIAL 69 sq 1.65306 1 0 0. 0. 0. -81 0 0 0 69 sq 1.84184 1 0 0. 0. 0. -57.76 0 0 0 69 pz 82.4000 69 pz 93.1300 RIBS 69 sq 1 3.00916 0 0. 0. 0. -289 0 0 0 69 sq 1 3.14776 0 0. 0. 0. -272.25 0 0 0 69 pz 67.3000 69 pz 65.9000 69 pz 64.5000 69 pz 63.1000 69 pz 61.7000 69 pz 60.3000 69 pz 58.9000 69 pz 57.5000 69 pz 56.1000 69 pz 54.7000 69 pz 53.3000 69 pz 51.9000 69 pz 50.5000 69 pz 49.1000 69 pz 47.7000 69 pz 46.3000 69 pz 44.9000 69 pz 42.1000 69 pz 40.7000 69 pz 39.3000 69 pz 37.9000 69 pz 36.5000 69 pz 35.1000 CLAVICLES 69 tz 0 11.1000 68.2500 20.0000 0.788300 0.788300 69 p 7.034200 1 0 11.100 69 p 7.034200 -1 0 -11.100 69 p 0.894150 1 0 11.100 69 p 0.894150 -1 0 -11.100 SCAPULAE 337 156 150 151 152 153 154 155 c c 160 69 69 69 69 69 69 69 sq p p p p pz pz 1 3.75885 0 0. 0. 0. -361 0 0 0 0.2500 1 0 0 0.2500 -1 0 0 0.8000 1 0 0 0.8000 -1 0 0 50.9000 67.3010 ADRENALS 69 gq 37.298 25.202 0.5625 -48.5148 0 0 -18.512 -82.2181 -42.75 1036.13 161 69 gq 37.298 25.202 0.5625 48.5148 0 0 18.512 -82.2181 -42.75 1036.13 162 69 pz 38 c c c BREASTS c left 190 69 sq 1 1.29489 1.4227 0. 0. 0. -24.5025 10 -8.6603 52 c right 191 69 sq 1 1.29489 1.4227 0. 0. 0. -24.5025 -10 -8.6603 52 c 192 69 sq 1 1.31006 1.44608 0. 0. 0. -22.5625 10 -8.6603 52 193 69 sq 1 1.31006 1.44608 0. 0. 0. -22.5625 -10 -8.6603 52 c c GALL BLADDER 200 69 s -4.5 -3.2 30 2.12 201 69 gq 0.924065 0.954066 0.0701124 -0.118118 -0.413343 -0.531454 24.1414 18.1764 -7.01399 171.417 202 69 p 0.268697 0.208982 0.940281 26.3306 203 69 p 0.268697 0.208982 0.940281 34.3306 c c c ESOPAHGUS 212 69 sq 1 7.7602 0 0. 0. 0. -1.36905 0 2.575 0 213 69 sq 1 52.5625 0 0. 0. 0. -0.756944 0 2.575 0 216 69 gq 0.458169 0.633991 0.90784 0.890651 -0.367322 0.446924 -21.1983 12.2727 -75.8574 1588.09 217 69 p 0.736092 -0.604987 -0.303579 -14.2992 218 69 p 0.736092 -0.604987 -0.303579 -6.59922 338 c c 210 c c 221 222 223 c c 230 231 232 c c 240 241 242 c c c 251 250 STOMACH 69 sq 4 7.11111 1 0. 0. 0. -64 8 -4 35 SMALL INTESTINE 69 py -4.8600 69 py 2.2000 69 pz 17.0000 ASCENDING COLON 69 sq 6.2500 6.2500 0 0 0 0 -39.0625 -8.5000 -2.3600 0 69 pz 14.4500 69 pz 24.0000 TRANSVERSE COLON 69 sq 0 1 2.77778 0. 0. 0. -6.25 0 -2.36 25.5 69 px 10.5000 69 px -10.5000 DESCENDING COLON 69 pz 8.7200 69 gq 4.5369 3.5344 0.106435 0 1.15654 -0.463191 -72.8161 -10.0851 2.06701 283.329 c c SIGMOID COLON 282 69 px 3 280 69 ty 3 0 8.72 5.72 1.57 1.57 281 69 ty 3 0 0 3 1.57 1.57 c c HEART 290 69 p 0.675066 -0.4727 -0.566428 -26.7954 291 69 p 0.573592 0.819141 7.18977e-006 -0.900503 c Left Ventricle 292 69 gq 1946.76 1896.95 2854.33 -136.928 -1284.71 1834.66 -95872.8 71201.4 -289580 7.26092e+006 c Right Ventricle 293 69 gq 870.831 1369.38 559.799 1369.9 -251.943 359.829 -17267.3 16157 -56793.2 1.42524e+006 339 c Left Atrium 294 69 gq 409.659 572.418 267.401 447.228 -21.4028 30.5767 -1543.14 2683.61 -26809.2 666412 c Right Atrium 295 69 gq 1105.69 913.706 1363.44 -527.551 -109.165 155.881 -10955 9275.13 -136696 3.39551e+006 c c KIDNEYS 310 69 sq 1.49383 13.4444 1 0. 0. 0. -30.25 6 6 32.5 311 69 sq 1.49383 13.4444 1 0. 0. 0. -30.25 -6 6 32.5 312 69 px 3.0000 313 69 px -3.0000 c c LIVER 320 69 sq 1 4.25391 0 0. 0. 0. -272.25 0 0 0 321 69 p 1935 1505 -1575 -67725 322 69 pz 43 c c Lungs 330 69 sq 23.0408 10.2404 1 0. 0. 0. -576.02 8.5 0 43.5 331 69 sq 23.0408 10.2404 1 0. 0. 0. -576.02 -8.5 0 43.5 333 69 px -5.4000 334 69 py 1.5000 335 69 pz 46.0000 336 69 pz 54.0000 337 69 px 8.0000 338 69 py 1.0000 339 69 pz 55.0000 c c Ovaries 340 69 sq 4 16 1 0. 0. 0. -4 6 0 15 341 69 sq 4 16 1 0. 0. 0. -4 -6 0 15 c c PANCREAS 350 69 sq 1 177.778 23.5078 0. 0. 0. -256 -1 0 37 351 69 px -1.0000 352 69 pz 37.0000 340 c c SPLEEN 360 69 sq 2.93878 9 1 0. 0. 0. -36 11 3 37 c c TESTICLES 370 69 sq 3.13018 2.35111 1 0. 0. 0. -5.29 1.3 -8 -2.3 371 69 sq 3.13018 2.35111 1 0. 0. 0. -5.29 -1.3 -8 -2.3 c c THYMUS 380 69 sq 7.11111 25 1 0. 0. 0. -16 0 -7.3 57 c c THYROID 390 69 c/z 0 -3.1500 2.2000 391 69 c/z 0 -3.1500 1.0000 392 69 py -3.1500 393 69 pz 75.0000 c c URINARY BLADDER 410 69 sq 1 2.05572 2.05572 0. 0. 0. -24.5818 0 -4.5 8 c c UTERUS 420 69 sq 3.96952 1 11.0546 0. 0. 0. -27.2484 0 -2 14 421 69 py -4.6200 c c c Tally Dosimetry Lattice c "x" surface tally lattice coordinate 459 69 px 28 460 69 px 20 461 69 px 12 462 69 px 4 463 69 px -4 464 69 px -12 465 69 px -20 466 69 px -28 c c "z" surface tally lattice coordinate 470 69 pz 78 c 8 69 pz 70 471 69 pz 62 472 69 pz 54 473 69 pz 46 474 69 pz 38 475 69 pz 30 341 476 69 pz 22 477 69 pz 14 478 69 pz 6 c c Dosimeter Cylinder Tally Cell 485 69 c/z 0 5.0 21.80 $ Outer surface 486 69 c/z 0 5.0 21.70 $ inner surface 487 69 pz 80 c c c Phantom Cylinder 500 c/z 88.90 35.56 22.0 $ Cylinder for initial phantom 501 pz 0.01 502 pz 180 c c 600 69 so 301 c c ************************************************************************ ****** c END OF SURFACE CARDS c ************************************************************************ ****** c c c ************************************************************************ ****** c MATERIAL CARDS c ************************************************************************ ****** c c c Dry air (density = 0.00098 g/cc at Los Alamos) c Reference: CRC Handbook of Chemistry and Physics and c CRC Handbook of tables for Applied Engineering Science c Nuclide composition in ATOM FRACTION m1 7014 0.782315 $ Nitrogen N14 7015 0.002905 $ Nitrogen N15 8016 0.209966 $ Oxygen O16 342 8017 0.000080 $ Oxygen O17 18000.59c 0.004734 $ Argon Ar-nat nlib=60c plib=02p elib=03e cond=0 c c c c c Lead (density = 11.35 g/cc) c Nuclide composition in ATOM FRACTION c Reference: c m2 82000.42c 1.00 $lead Pb-nat nlib=60c plib=02p elib=01e cond=0 c c c Stainless Steel Type 304 Stainless Steel (density = 8.0 g/cc). c Nuclide composition in ATOM FRACTION c Reference: METALS HANDBOOK Tenth Edition pp. 843 & 871 m3 6000 0.003635 $ Carbon C-nat 14000 0.019431 $ Silicon Si-nat 15031 0.000793 $ Phosphorus P31 16000 0.000511 $ Sulfur S-nat 24050 0.008665 $ Chromium Cr50 24052 0.167091 $ Chromium Cr52 24053 0.018947 $ Chromium Cr53 24054 0.004716 $ Chromium Cr54 25055 0.019867 $ Manganese Mn55 26054 0.039181 $ Iron Fe54 26056 0.615060 $ Iron Fe56 26057 0.014204 $ Iron Fe57 26058 0.001890 $ Iron Fe58 28058 0.058551 $ Nickel Ni58 28060 0.022554 $ Nickel Ni60 28061 0.000980 $ Nickel Ni61 28062 0.003126 $ Nickel Ni62 28064 0.000796 $ Nickel Ni64 nlib=60c plib=02p elib=03e cond=1 c c c Leaded Glass (density = 3.76 g/cc) c Nuclide composition in ATOM FRACTION c Reference: Askeland, Donald R., The Science and Engineering of Materials, c 3rd ed., Table 14-2, p. 449 (1994) composition data c Dean, John A., Lange's Handbook of Chemistry, 14th ed., 343 c Table 3.2, pp. 3.12-3.63, McGraw-Hill Inc.(1992) density data c Approximate Thickness of glass (mm) per mm lead equivalent = 1.9 m4 8016 0.610814 $ oxygen O16 8017 0.000244 $ oxygen O17 11023 0.047148 $ sodium Na23 14000 0.271543 $ silicon Si-nat 19000 0.051704 $ potassium K-nat 82000.42c 0.018547 $lead Pb-nat nlib=60c plib=02p elib=01e cond=0 c c c Polyethylene (density = 0.92 g/cc). c Nuclide composition in ATOM FRACTION c Reference:Harmon II, Charles D., et al., "Criticality Calculations with c MCNP: A Primer", Appendix C, LANL, LA-12827-M, August 1994. m5 1001 0.666584 $ Hydrogen H1 1002 0.000100 $ Hydrogen H2 6000 0.333316 $ Carbon C-nat nlib=60c plib=02p elib=03e cond=-1 c c c c BodyBuilder Adult Tissue (density = 1.04 g/cc). c Nuclide composition in ATOM FRACTION c Reference:BodyBuilder Software, White Rock Science m10 1001 0.63103424 $ Hydrogen H1 1002 0.00009467 $ Hydrogen H2 6000 0.11481305 $ Carbon C-nat 7014 0.01077719 $ Nitrogen N-14 7015 0.00004002 $ Nitrogen N-15 8016 0.24150173 $ Oxygen O16 8017 0.00009664 $ Oxygen O17 11023 0.00029644 $ Sodium N23 12000 0.00003255 $ Magnesium Mg-nat 14000 0.00006500 $ Silicon Si-nat 15031 0.00026325 $ Phosphorus P-31 16000 0.00038719 $ Sulfur S-nat 17000 0.00022827 $ Chlorine Cl-nat 19000 0.00032371 $ Potassium K-nat 20000 0.00003644 $ Calcium Ca-nat 26054 0.00000032 $ Iron Fe-54 26056 0.00000500 $ Iron Fe-56 26057 0.00000012 $ Iron Fe-57 26058 0.00000002 $ Iron Fe-58 344 30000.42c 0.00000279 $ Zinc Zn-nat 37085.55c 0.00000051 $ Rubidium Rb-85 37087.55c 0.00000020 $ Rubidium Rb-87 40000 0.00000067 $ Zirconium Zr-nat nlib=60c plib=02p elib=03e cond=-1 c c BodyBuilder Skelton (density = 1.40 g/cc). c Nuclide composition in ATOM FRACTION c Reference:BodyBuilder Software, White Rock Science m11 1001 0.55710523 $ Hydrogen H1 1002 0.00008358 $ Hydrogen H2 6000 0.16234404 $ Carbon C-nat 7014 0.01664370 $ Nitrogen N-14 7015 0.00006181 $ Nitrogen N-15 8016 0.22903186 $ Oxygen O16 8017 0.00009165 $ Oxygen O17 9019 0.00010072 $ Fluorine F-19 11023 0.00108539 $ Sodium N23 12000 0.00035271 $ Magnesium Mg-nat 14000 0.00000545 $ Silicon Si-nat 15031 0.01259075 $ Phosphorus P-31 16000 0.00041303 $ Sulfur S-nat 17000 0.00030874 $ Chlorine Cl-nat 19000 0.00029953 $ Potassium K-nat 20000 0.01946022 $ Calcium Ca-nat 26054 0.00000064 $ Iron Fe-54 26056 0.00001006 $ Iron Fe-56 26057 0.00000023 $ Iron Fe-57 26058 0.00000003 $ Iron Fe-58 30000.42c 0.00000585 $ Zinc Zn-nat 37085.55c 0.00000129 $ Rubidium Rb-85 37087.55c 0.00000050 $ Rubidium Rb-87 38000 0.00000262 $ Strontium Sr 82000.42c 0.00000037 $ Lead Pb-nat nlib=60c plib=02p elib=03e cond=-1 c c BodyBuilder Lung (density = 0.296 g/cc). c Nuclide composition in ATOM FRACTION c Reference:BodyBuilder Software, White Rock Science m12 1001 0.6331547 $ Hydrogen H1 1002 0.0000950 $ Hydrogen H2 6000 0.0536843 $ Carbon C-nat 7014 0.0128393 $ Nitrogen N-14 7015 0.0000477 $ Nitrogen N-15 345 8016 0.2980768 $ Oxygen O16 8017 0.0001193 $ Oxygen O17 11023 0.0005041 $ Sodium N23 12000 0.0000181 $ Magnesium Mg-nat 14000 0.0000135 $ Silicon Si-nat 15031 0.0001627 $ Phosphorus P-31 16000 0.0004420 $ Sulfur S-nat 17000 0.0004725 $ Chlorine Cl-nat 19000 0.0003125 $ Potassium K-nat 20000 0.0000141 $ Calcium Ca-nat 26054 0.0000024 $ Iron Fe-54 26056 0.0000383 $ Iron Fe-56 26057 0.0000009 $ Iron Fe-57 26058 0.0000001 $ Iron Fe-58 30000.42c 0.0000010 $ Zinc Zn-nat 37085.55c 0.0000005 $ Rubidium Rb-85 37087.55c 0.0000002 $ Rubidium Rb-87 nlib=60c plib=02p elib=03e cond=-1 c c c ************************************************************************ ****** c END OF MATERIAL CARDS c ************************************************************************ ****** c c c ************************************************************************ ****** c SOURCE CARDS c ************************************************************************ ****** c c mode n phys:n 20 cut:n j 0 phys:p 100 cut:p j 0.01 c 346 c Neutron energy spectra for M-797 PuBe neutron source c Be - 7.86 g c Pu - 15.97 g c Dimensions of container: 1.02" o.d. x 1.46" high c Container material: Ta and SS c Thickness: Ta c Calibrated 07 Nov 1961 c Total neutron emission = 1.75E+06 neutrons/s c sdef par=1 pos= 43.1025 35.56 94.1959 erg=d8 # si8 sp8 h d 1.00E-11 0. 1.00E-02 1.47E+00 2.00E-02 4.25E+00 5.00E-02 2.53E+01 1.00E-01 7.62E+01 2.00E-01 2.29E+02 4.00E-01 3.81E+03 6.00E-01 1.57E+04 8.00E-01 2.39E+04 1.00E+00 2.59E+04 1.30E+00 3.83E+04 1.70E+00 3.87E+04 2.10E+00 4.67E+04 2.40E+00 4.65E+04 2.70E+00 5.67E+04 3.00E+00 9.16E+04 3.30E+00 1.17E+05 3.60E+00 1.10E+05 4.00E+00 1.35E+05 4.40E+00 1.23E+05 5.00E+00 1.65E+05 6.00E+00 1.65E+05 7.00E+00 1.53E+05 8.00E+00 1.73E+05 9.00E+00 1.30E+05 1.00E+01 7.86E+04 1.20E+01 1.08E+04 1.50E+01 7.41E-02 2.00E+01 4.22E-03 c Total 1.75E+06 c c 347 c ************************************************************************ ****** c END OF SOURCE CARDS c ************************************************************************ ****** c c c ************************************************************************ ****** c TALLY CARDS c ************************************************************************ ****** c c ************************************************************************ ****** c NEUTRON c ************************************************************************ ****** c c ************************************************************************ ****** c Simulated Dosimeter Lattice Tally c ************************************************************************ ****** c c Multiplier for dose-rate conversion = c [(1.75E+06 src_neuts/s)/(kg Pu)] x [X tally_neuts/(src_neutron*cm^2)] x c [(Y*E-12 Sv cm^2)/(tally neut)]x(100 rem/Sv)x(3600 s/h)x(1000 mrem/rem) x c 24 h = 1.512E+4*XY mrem c c AP - Neutron Fluence-to Effective-Dose-Equivalent Conversion factors vs c Energy from ANSI/ANS-6.1.1-1977 for AP exposure geomertry. Energy units c in MeV and conversion-factors units are 1.0e-12Sv-cm^2. c c c de0 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 c 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 348 c df0 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 c 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c c c c ************************************************************************ ****** c fc2 mrem/source-particle-cm^2 averaged over tally surface area f2:n 485 fs2 -464 -8 463 470 sd2 1 1 1 1 64 fm2 1.512E+4 fq2 e f cf2 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e2 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de2 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df2 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc12 mrem/source-particle-cm^2 averaged over tally surface area f12:n 485 fs12 -463 -8 462 470 sd12 1 1 1 1 64 fm12 1.512E+4 fq12 e f cf12 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e12 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de12 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df12 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c 349 fc22 mrem/source-particle-cm^2 averaged over tally surface area f22:n 485 fs22 -462 -8 461 470 sd22 1 1 1 1 64 fm22 1.512E+4 fq22 e f cf22 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e22 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de22 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df22 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc32 mrem/source-particle-cm^2 averaged over tally surface area f32:n 485 fs32 -465 -471 464 8 sd32 1 1 1 1 64 fm32 1.512E+4 fq32 e f cf32 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e32 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de32 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df32 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc42 mrem/source-particle-cm^2 averaged over tally surface area f42:n 485 fs42 -464 -471 463 8 sd42 1 1 1 1 64 fm42 1.512E+4 fq42 e f cf42 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 350 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e42 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de42 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df42 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc52 mrem/source-particle-cm^2 averaged over tally surface area f52:n 485 fs52 -463 -471 462 8 sd52 1 1 1 1 64 fm52 1.512E+4 fq52 e f cf52 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e52 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de52 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df52 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc62 mrem/source-particle-cm^2 averaged over tally surface area f62:n 485 fs62 -462 -471 461 8 sd62 1 1 1 1 64 fm62 1.512E+4 fq62 e f cf62 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e62 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de62 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df62 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 351 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc72 mrem/source-particle-cm^2 averaged over tally surface area f72:n 485 fs72 -461 -471 460 8 sd72 1 1 1 1 64 fm72 1.512E+4 fq72 e f cf72 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e72 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de72 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df72 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc82 mrem/source-particle-cm^2 averaged over tally surface area f82:n 485 fs82 -465 -472 464 471 sd82 1 1 1 1 64 fm82 1.512E+4 fq82 e f cf82 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e82 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de82 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df82 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc92 mrem/source-particle-cm^2 averaged over tally surface area f92:n 485 fs92 -464 -472 463 471 sd92 1 1 1 1 64 fm92 1.512E+4 fq92 e f 352 cf92 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e92 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de92 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df92 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc102 mrem/source-particle-cm^2 averaged over tally surface area f102:n 485 fs102 -463 -472 462 471 sd102 1 1 1 1 64 fm102 1.512E+4 fq102 e f cf102 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e102 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de102 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df102 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc112 mrem/source-particle-cm^2 averaged over tally surface area f112:n 485 fs112 -462 -472 461 471 sd112 1 1 1 1 64 fm112 1.512E+4 fq112 e f cf112 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e112 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de112 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 353 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df112 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc122 mrem/source-particle-cm^2 averaged over tally surface area f122:n 485 fs122 -461 -472 460 471 sd122 1 1 1 1 64 fm122 1.512E+4 fq122 e f cf122 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e122 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de122 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df122 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc132 mrem/source-particle-cm^2 averaged over tally surface area f132:n 485 fs132 -465 -473 464 472 sd132 1 1 1 1 64 fm132 1.512E+4 fq132 e f cf132 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e132 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de132 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df132 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc142 mrem/source-particle-cm^2 averaged over tally surface area f142:n 485 fs142 -464 -473 463 472 sd142 1 1 1 1 64 354 fm142 1.512E+4 fq142 e f cf142 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e142 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de142 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df142 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc152 mrem/source-particle-cm^2 averaged over tally surface area f152:n 485 fs152 -463 -473 462 472 sd152 1 1 1 1 64 fm152 1.512E+4 fq152 e f cf152 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e152 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de152 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df152 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc162 mrem/source-particle-cm^2 averaged over tally surface area f162:n 485 fs162 -462 -473 461 472 sd162 1 1 1 1 64 fm162 1.512E+4 fq162 e f cf162 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e162 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 355 4.0 4.4 5 6 7 8 9 10 12 15 20 de162 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df162 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc172 mrem/source-particle-cm^2 averaged over tally surface area f172:n 485 fs172 -461 -473 460 472 sd172 1 1 1 1 64 fm172 1.512E+4 fq172 e f cf172 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e172 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de172 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df172 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc182 mrem/source-particle-cm^2 averaged over tally surface area f182:n 485 fs182 -465 -474 464 473 sd182 1 1 1 1 64 fm182 1.512E+4 fq182 e f cf182 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e182 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de182 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df182 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc192 mrem/source-particle-cm^2 averaged over tally surface area f192:n 485 356 fs192 -464 -474 463 473 sd192 1 1 1 1 64 fm192 1.512E+4 fq192 e f cf192 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e192 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de192 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df192 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc202 mrem/source-particle-cm^2 averaged over tally surface area f202:n 485 fs202 -463 -474 462 473 sd202 1 1 1 1 64 fm202 1.512E+4 fq202 e f cf202 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e202 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de202 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df202 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc212 mrem/source-particle-cm^2 averaged over tally surface area f212:n 485 fs212 -462 -474 461 473 sd212 1 1 1 1 64 fm212 1.512E+4 fq212 e f cf212 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 357 e212 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de212 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df212 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc222 mrem/source-particle-cm^2 averaged over tally surface area f222:n 485 fs222 -461 -474 460 473 sd222 1 1 1 1 64 fm222 1.512E+4 fq222 e f cf222 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e222 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de222 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df222 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc232 mrem/source-particle-cm^2 averaged over tally surface area f232:n 485 fs232 -465 -475 464 474 sd232 1 1 1 1 64 fm232 1.512E+4 fq232 e f cf232 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e232 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de232 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df232 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c 358 fc242 mrem/source-particle-cm^2 averaged over tally surface area f242:n 485 fs242 -464 -475 463 474 sd242 1 1 1 1 64 fm242 1.512E+4 fq242 e f cf242 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e242 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de242 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df242 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc252 mrem/source-particle-cm^2 averaged over tally surface area f252:n 485 fs252 -463 -475 462 474 sd252 1 1 1 1 64 fm252 1.512E+4 fq252 e f cf252 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e252 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de252 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df252 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc262 mrem/source-particle-cm^2 averaged over tally surface area f262:n 485 fs262 -462 -475 461 474 sd262 1 1 1 1 64 fm262 1.512E+4 fq262 e f cf262 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 359 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e262 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de262 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df262 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc272 mrem/source-particle-cm^2 averaged over tally surface area f272:n 485 fs272 -461 -475 460 474 sd272 1 1 1 1 64 fm272 1.512E+4 fq272 e f cf272 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e272 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de272 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df272 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc282 mrem/source-particle-cm^2 averaged over tally surface area f282:n 485 fs282 -465 -476 464 475 sd282 1 1 1 1 64 fm282 1.512E+4 fq282 e f cf282 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e282 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de282 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df282 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 360 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc292 mrem/source-particle-cm^2 averaged over tally surface area f292:n 485 fs292 -464 -476 463 475 sd292 1 1 1 1 64 fm292 1.512E+4 fq292 e f cf292 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e292 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de292 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df292 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc302 mrem/source-particle-cm^2 averaged over tally surface area f302:n 485 fs302 -463 -476 462 475 sd302 1 1 1 1 64 fm302 1.512E+4 fq302 e f cf302 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e302 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de302 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df302 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc312 mrem/source-particle-cm^2 averaged over tally surface area f312:n 485 fs312 -462 -476 461 475 sd312 1 1 1 1 64 fm312 1.512E+4 fq312 e f 361 cf312 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e312 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de312 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df312 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c fc322 mrem/source-particle-cm^2 averaged over tally surface area f322:n 485 fs322 -461 -476 460 475 sd322 1 1 1 1 64 fm322 1.512E+4 fq322 e f cf322 10 11 12 13 14 15 16 17 20 22 27 28 30 35 40 41 50 70 90 100 101 102 110 130 140 150 160 180 190 192 200 210 212 213 220 230 240 250 280 290 310 320 330 340 350 360 370 380 390 410 420 e322 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de322 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df322 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c c ************************************************************************ ****** c End of Simulated Dosimeter Lattice Tally c ************************************************************************ ****** c c ************************************************************************ ****** c Phantom Organ/Tissue Tally Cells (rad to rem based on ANSI 1977) 362 c ************************************************************************ ****** c c Rad to rem conversion using ANSI/ANS-6.1.1-1977 Mean Quality Factors c c Multiplier for rad-to-rem conversion = c [X MeV/g/basis] x [Y rem/rad] x [1 rad/6.242E+7 Mev/g] x [1000 mrem/rem] c = 1.602E-5 * XY mrem/h-basis c c ANSI 1977 Mean Quality Factors c c c de0 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 c 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 c df0 2 2 2 2 2 2 2.5 7.5 c 11 11 9 8 7 6.5 7.5 8 c c ************************************************************************ ****** c fc306 Brain f306:n 180 fm306 1.602e-5 e306 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de306 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df306 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc316 Thyroid f316:n 390 fm316 1.602e-5 e316 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de316 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df316 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc326 Thymus f326:n 380 363 fm326 1.602e-5 e326 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de326 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df326 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc336 Lungs f336:n 330 T fm336 1.602e-5 e336 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de336 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df336 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc346 Heart f346:n 290 fm346 1.602e-5 e346 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de346 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df346 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc356 Adrenals f356:n 160 fm356 1.602e-5 e356 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de356 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df356 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc366 Kidneys f366:n 310 364 fm366 1.602e-5 e366 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de366 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df366 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc376 Liver f376:n 320 fm376 1.602e-5 e376 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de376 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df376 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc386 Gall Bladder f386:n 290 fm386 1.602e-5 e386 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de386 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df386 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc396 Pancreas f396:n 350 fm396 1.602e-5 e396 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de396 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df396 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc406 Spleen f406:n 360 365 fm406 1.602e-5 e406 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de406 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df406 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc416 Eosphagus f416:n 212 fm416 1.602e-5 e416 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de416 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df416 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc426 Stomach f426:n 210 fm426 1.602e-5 e426 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de426 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df426 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc436 Small Intestine f436:n 220 fm436 1.602e-5 e436 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de436 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df436 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc446 Ascending Colon f446:n 230 366 fm446 1.602e-5 e446 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de446 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df446 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc456 Transverse Colon f456:n 240 fm456 1.602e-5 e456 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de456 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df456 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc466 Descending Colon f466:n 250 fm466 1.602e-5 e466 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de466 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df466 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc476 Sigmoid Colon f476:n 280 T fm476 1.602e-5 e476 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de476 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df476 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc486 Bladder f486:n 410 367 fm486 1.602e-5 e486 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de486 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df486 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc496 Testes f496:n 370 fm496 1.602e-5 e496 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de496 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df496 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc506 Genitalia f506:n 40 fm506 1.602e-5 e506 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de506 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df506 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc516 Skin f516:n 22 28 17 41 34 35 192 T fm516 1.602e-5 e516 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de516 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df516 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc526 Bone f526:n 50 70 90 100 101 102 110 130 140 150 T 368 fm526 1.602e-5 e526 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de526 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df526 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc536 Breast f536:n 190 fm536 1.602e-5 e536 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de536 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df536 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc546 Ovaries f546:n 340 fm546 1.602e-5 e546 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de546 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df546 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c fc556 Uterus f556:n 420 fm556 1.602e-5 e556 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 0.01 0.02 0.05 0.1 0.2 0.4 0.6 0.8 1.0 1.3 1.7 2.1 2.4 2.7 3.0 3.3 3.6 4.0 4.4 5 6 7 8 9 10 12 15 20 de556 2.5e-8 1.0e-7 1.0e-6 1.0e-5 1.0e-4 1.0e-3 1.0e-2 1.0e-1 5.0e-1 1.0 2.5 5.0 7.0 10.0 14.0 20.0 df556 2 2 2 2 2 2 2.5 7.5 11 11 9 8 7 6.5 7.5 8 c 369 c ************************************************************************ ****** c End of Phantom Organ/Tissue Tally Cells c ************************************************************************ ****** c c c ************************************************************************ ****** c Mesh Tally - ANSI 1977 c ************************************************************************ ****** c c If mesh tally is used to correspond to the dosimeter tally plane of a c phantom, then the distance from the GB to the mesh tally is 13.68 and c has a width of 0.1 cm or is 16.8 cm toward GB from center line of c phantom (i.e. 149.86 - 16.8 = 133.06) c c If the center line is at y' then set up the mesh tally in y direction to c be y'-m*8-4 (m+n)i y'+n*8+4 c (i.e., to cover the front of the glove box need |y|> 91.44, which can c accomplish by n=8 and m=16 in this case.) c c Should cover the z region as where the dosimeter can be normally worn. c With Z=0 is the ground floor that walk on, need zmin <= 82 and zmax>=162, c i.e., zmin=82-p*8 and zmax=162+q*8. If want to cover the z direction from c about the floor level to about the glove box height, then p=10 and q=2 c in this case. (zmin (p+q+9)i zmax) c c de1 2.50e-8 1.00e-7 1.00e-6 1.00e-5 1.00e-4 1.00e-3 1.00e-2 1.00e-1 5.00e-1 1.00e+0 2.50e+0 5.00e+0 7.00e+0 1.00e+1 1.40e+1 2.00e+1 df1 1.02e+1 1.02e+1 1.24e+1 1.26e+1 1.16e+1 1.04e+1 9.89e+0 6.03e+1 2.57e+2 3.67e+2 3.47e+2 4.33e+2 4.08e+2 4.08e+2 5.78e+2 6.31e+2 c tmesh rmesh1:n cora1 72.10 72.20 corb1 -96.44 24i 103.56 corc1 2 21i 178 370 endmd fm1 1.512E+4 c c c ************************************************************************ ****** c End of Mesh Tally - ANSI 1977 c ************************************************************************ ****** c c c ************************************************************************ ****** c END OF TALLY CARDS c ************************************************************************ ****** c c c ************************************************************************ ****** c Other Data Cards c ************************************************************************ ****** c c Phantom Transformation tr69 88.90 35.56 80 0 1 0 1 0 0 0 0 1 1 c dbcn 12j 137753 prdmp j 5e7 j 1 ctme 9999 nps 3e7 print 10 40 50 60 110 140 160 161 162 170 imp:n 1 69r 0 371 Appendix L: Phantom Dose Estimates For NETL Glove Box Experiment 372 Table L-1: Phantom Dose Estimates at 1 ft using ICRP 26. Male with breasts Tissue mrem/b fraction mrem/b Testes 1.67E+02 0.25 Breast 0.15 RBM 0.12 Lungs 0.12 Thyroid 0.03 NBS 0.03 Stomach Transverse Colon Gentalia Thymus Liver 1.47E+02 1.31E+02 1.29E+02 1.29E+02 0.06 0.06 0.06 0.06 0.06 EDE 1.64E+02 3.90E+01 1.57E+00 7.14E+01 3.71E+01 1.71E+02 4.18E+01 2.47E+01 4.68E+00 1.88E-01 2.14E+00 1.11E+00 1.03E+01 8.80E+00 7.84E+00 7.76E+00 7.74E+00 1.17E+02 Male without breasts Tissue mrem/b fraction mrem/b Female Tissue mrem/b fraction mrem/b Ovaries 3.95E+01 0.25 Breast 0.15 RBM 0.12 Lungs 0.12 Thyroid 0.03 NBS 0.03 Stomach Transverse Colon Gentalia Thymus Liver 1.47E+02 1.31E+02 1.29E+02 1.29E+02 0.06 0.06 0.06 0.06 0.06 EDE Testes 1.67E+02 0.25 Breast 0 RBM 0.12 Lungs 0.12 Thyroid 0.03 NBS 0.03 Stomach Transverse Colon Gentalia Thymus Liver 1.47E+02 1.31E+02 1.29E+02 1.29E+02 0.06 0.06 0.06 0.06 0.06 EDE 1.64E+02 3.90E+01 1.57E+00 7.14E+01 3.71E+01 1.71E+02 1.88E-01 2.14E+00 1.11E+00 1.03E+01 4.18E+01 0.00E+00 4.68E+00 8.80E+00 7.84E+00 7.76E+00 7.74E+00 9.24E+01 1.64E+02 3.90E+01 1.57E+00 7.14E+01 3.71E+01 1.71E+02 9.87E+00 2.47E+01 4.68E+00 1.88E-01 2.14E+00 1.11E+00 1.03E+01 8.80E+00 7.84E+00 7.76E+00 7.74E+00 8.51E+01 373 Table L-2: Phantom Dose Estimates at 1 ft using ICRP 60. Male with breasts Tissue mrem/b fraction mrem/b Testes 0.2 RBM 0.12 Colon 0.12 Lungs 0.12 Stomach Bladder 0.12 0.05 Breast 0.05 Liver 0.05 Esophagus Thyroid Skin 0.05 0.05 0.01 NBS 0.01 Remainder ED 5.54E+01 0.05 2.77E+00 9.79E+01 1.67E+02 3.90E+01 8.82E+01 1.57E+00 1.71E+02 7.03E+01 1.64E+02 1.29E+02 5.65E+01 7.14E+01 6.50E+01 3.71E+01 3.35E+01 4.68E+00 1.06E+01 1.88E-01 2.06E+01 3.52E+00 8.22E+00 6.45E+00 2.83E+00 3.57E+00 6.50E-01 3.71E-01 Male without breasts Tissue fraction mrem/b Female Tissue fraction Ovaries 0.2 RBM 0.12 Colon 0.12 Lungs 0.12 Stomach Bladder 0.12 0.05 Breast 0.05 Liver 0.05 Esophagus Thyroid Skin 0.05 0.05 0.01 NBS 0.01 Remainder ED 5.63E+01 0.05 2.82E+00 7.23E+01 Testes 0.2 RBM 0.12 Colon 0.12 Lungs 0.12 Stomach Bladder 0.12 0.05 Breast 0 Liver 0.05 Esophagus Thyroid Skin 0.05 0.05 0.01 NBS 0.01 Remainder ED 5.54E+01 0.05 2.77E+00 8.96E+01 mrem/hr-b 1.67E+02 3.90E+01 8.82E+01 1.57E+00 1.71E+02 7.03E+01 1.64E+02 1.29E+02 3.35E+01 4.68E+00 1.06E+01 1.88E-01 2.06E+01 3.52E+00 0.00E+00 6.45E+00 5.65E+01 7.14E+01 6.50E+01 3.71E+01 2.83E+00 3.57E+00 6.50E-01 3.71E-01 mrem/hr-b 3.95E+01 3.90E+01 8.82E+01 1.57E+00 1.71E+02 7.03E+01 1.64E+02 1.29E+02 mrem/hr-b 7.89E+00 4.68E+00 1.06E+01 1.88E-01 2.06E+01 3.52E+00 8.22E+00 6.45E+00 5.65E+01 7.14E+01 6.50E+01 3.71E+01 2.83E+00 3.57E+00 6.50E-01 3.71E-01 374 Table L-3: Phantom Dose Estimates at 3 ft using ICRP 26. Male with breasts Tissue mrem/b fraction mrem/b Testes 1.67E+01 0.25 4.18E+00 Breast 4.58E+01 0.15 6.87E+00 RBM 1.13E+01 0.12 1.35E+00 Lungs 0.12 Thyroid 0.03 NBS 0.03 Thymus Stomach Liver 0.06 0.06 0.06 Pancreas Esophagus EDE 1.82E+01 0.06 1.09E+00 2.21E+01 0.06 5.27E-01 4.87E+01 1.07E+01 4.34E+01 2.71E+01 2.40E+01 1.85E+01 6.33E-02 1.46E+00 3.22E-01 2.60E+00 1.62E+00 1.44E+00 1.11E+00 Male without breasts Tissue mrem/b fraction mrem/b Female Tissue mrem/b fraction mrem/b Ovaries 6.07E+00 0.25 1.52E+00 Breast 4.58E+01 0.15 6.87E+00 RBM 1.13E+01 0.12 1.35E+00 Lungs 0.12 Thyroid 0.03 NBS 0.03 Thymus Stomach Liver 0.06 0.06 0.06 Pancreas Esophagus EDE 1.82E+01 0.06 1.09E+00 1.95E+01 0.06 Testes 1.67E+01 0.25 4.18E+00 Breast 4.58E+01 0 0.00E+00 RBM 1.13E+01 0.12 1.35E+00 Lungs 0.12 Thyroid 0.03 NBS 0.03 Thymus Stomach Liver 0.06 0.06 0.06 Pancreas Esophagus EDE 1.82E+01 0.06 1.09E+00 1.52E+01 0.06 5.27E-01 4.87E+01 1.07E+01 4.34E+01 2.71E+01 2.40E+01 1.85E+01 6.33E-02 1.46E+00 3.22E-01 2.60E+00 1.62E+00 1.44E+00 1.11E+00 5.27E-01 4.87E+01 1.07E+01 4.34E+01 2.71E+01 2.40E+01 1.85E+01 6.33E-02 1.46E+00 3.22E-01 2.60E+00 1.62E+00 1.44E+00 1.11E+00 375 Table L-4: Phantom Dose Estimates at 3 ft using ICRP 60. Male with breasts Tissue mrem/b fraction mrem/b Testes 0.2 RBM 0.12 Colon 0.12 Lungs 0.12 Stomach Bladder Breast 0.12 0.05 0.05 Liver 0.05 Esophagus Thyroid Skin 0.05 0.05 0.01 NBS 0.01 Remainder ED 1.03E+01 0.05 5.16E-01 1.72E+01 1.67E+01 1.13E+01 8.64E+00 5.27E-01 2.71E+01 1.07E+01 4.58E+01 2.40E+01 1.82E+01 4.87E+01 1.48E+01 1.07E+01 3.35E+00 1.35E+00 1.04E+00 6.33E-02 3.25E+00 5.36E-01 2.29E+00 1.20E+00 9.09E-01 2.43E+00 1.48E-01 1.07E-01 Male without breasts Tissue mrem/hr-b fraction mrem/b Female Tissue mrem/hr-b fraction Ovaries 0.2 RBM 0.12 Colon 0.12 Lungs 0.12 Stomach Bladder Breast 0.12 0.05 0.05 Liver 0.05 Esophagus Thyroid Skin 0.05 0.05 0.01 NBS 0.01 Remainder ED 1.05E+01 0.05 5.24E-01 1.51E+01 Testes 0.2 RBM 0.12 Colon Lungs 0.12 Stomach Bladder Breast 0.12 0.05 0 Liver 0.05 Esophagus Thyroid Skin 0.05 0.05 0.01 NBS 0.01 Remainder ED 1.03E+01 0.05 5.16E-01 1.49E+01 1.67E+01 1.13E+01 8.64E+00 5.27E-01 2.71E+01 1.07E+01 4.58E+01 2.40E+01 0.12 1.82E+01 4.87E+01 1.48E+01 1.07E+01 3.35E+00 1.35E+00 1.04E+00 6.33E-02 3.25E+00 5.36E-01 0.00E+00 1.20E+00 9.09E-01 2.43E+00 1.48E-01 1.07E-01 6.07E+00 1.13E+01 8.64E+00 5.27E-01 2.71E+01 1.07E+01 4.58E+01 2.40E+01 1.82E+01 4.87E+01 1.48E+01 1.07E+01 mrem/hr-b 1.21E+00 1.35E+00 1.04E+00 6.33E-02 3.25E+00 5.36E-01 2.29E+00 1.20E+00 9.09E-01 2.43E+00 1.48E-01 1.07E-01 376 References AGS. 1998. 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Morstin, K., Kopec, M., and Schmitz, T. 1992. Equivalent Dose Versus Dose Equivalent for Neutrons Based on New ICRP Recommendations, Radiation Protection Dosimetry 44(1/4):159-164. NRC. 1991. Title 10 Code Federal Regulations Part 20, Standards for Protection Against Radiation, U.S. Government Printing Office. O'Kelly, S, 2003. Personal communication. April 30. Portal, G, and Dietze, G. 1992. Implications of New ICRP and ICRU Recommendations for Neutron Dosimetry, Radiation Protection Dosimetry 44(1/4):165-170. Poston Sr., J.W. 2000. Dosimetry: Where We've Been, Where We Are, Where We're Going, American Nuclear Society Proceedings on the Topical Meeting on "Radiation Protection for our National Priorities: Medicine, the Environment, and the Legacy":630-636. Prael, R.E. and Lichtenstein, H. 1989. User Guide to LCS: The LAHET Code System, LANL Report LA-UR-89-3014. Profio, A.E. 1976. Experimental Reactor Physics, New York: Wiley. Profio, A.E. 1979. Radiation Shielding and Dosimetry, New York: Wiley. Reece, W.D., Poston Sr., J.W., and Xu, X.G. 1994. Determining the Effective Dose Equivalent for External Photon Radiation: Calculational Results for Beam and Point Source Geometries, Radiation Protection Dosimetry 55(1):5-21. Reece, W.D., and Xu, X.G. 1997. Determining Effective Dose Equivalent for External Photon Radiation: Assessing Effective Dose Equivalent from Personal Dosimeter Readings, Radiation Protection Dosimetry 69(3):167-178. Richards, J.R. 2003. Information concerning RSN-105S-M9: a proportional counter manufactured by Reuter-Stokes, Inc. A GE Power Systems Company, email message to author, May 14. 380 Shores, E.F. 1999. Calculated Dose Equivalent Rates from PuBe Source Neutrons, LANL report LA-UR-99-3595. Siebert, R.L. and Thomas, R.H. 1997. Computational Dosimetry, Radiation Protection Dosimetry 70(1-4):371-378.Taylor, L.S. 1979. Organization for Radiation Protection The Operations of the ICRP and NCRP, 1928-1974, Report, DOE/TIC-10124, National Technical Information Services, Springfield, VA 22161. Sinclair, W.K. 1990. Quality Factor, Concepts and Issues, Radiation Protection Dosimetry 31(1/4):355-359. Shultis, J.K., and Faw, R.E. 2000. Radiation Shielding, American Nuclear Society (ANS). Tanner, J.E., Piper, R.K., Leonowich, J.A., and Faust, L.G. 1992., Verification of an Effective Dose Equivalent Model for Neutrons, Radiation Protection Dosimetry 44(1/4):171-174. Taylor, L.S. 1981. The Development of Radiation Protection Standards (1925-1940), Health Physics 41:227-232. Thomas, R.H. 1997. We Have Met the Enemy and He is Us", (Editorial) Radiation Protection Dosimetry 71(2):83-84. Thomas, R.H. 1998. The Seven Deadly Sins of Dosimetry in Radiation Protection, (Editorial) Radiation Protection Dosimetry 78(2):87-90. Van Dam, J., Beauduin, M., Gregoire, V., Gueulette, J., Laublin, G., and Wambersie, A. 1992. Variation of Neutron RBE as a Function of Energy for Different Biological Systems: A Review, Radiation Protection Dosimetry 44(1/4):41-44. Van Riper, K.A. 2002. Body Builder User's Guide, White Rock Science. Van Riper, K.A. 2002. MORITZ Geometry Tool, White Rock Science. Wilson, W.B., Perry, R.T., Shores, E.F., Charlton, W.S., Parish, T.A., Estes, G.P., Brown, T.H., Arthur, E.D., Bozoian, M., England, T.R., Madland, D.G., and Stewart, J.E. 2002. SOURCES 4C: A Code for Calculating ( ,n), Spontaneous Fission, and Delayed Neutron Sources and Spectra, LANL Report LA-UR-021617. 381 X-5 Monte Carlo Team. 2003. MCNP A General Monte Carlo N-Particle Transport Code, Version 5, Volume 1: Overview and Theory, LANL report LA-UR-031987. Zankl, M. and Drexler, G. 1995, An Analysis of the Equivalent Dose Calculation for the Remainder Tissues, Health Physics 69(3):346-355. Zankl, M., Petoussi, N., and Drexler, G. 1992. Effective Dose and Effective Dose Equivalent The Impact of the New ICRP Definition for External Photon Irradiation, Health Physics 62(5):395-399. Zankl, M. 1999. Personal Dose Equivalent for Photons and its Variation with Dosimeter Position, Health Phys. 76(2): 162-170. 382 Vita Arthur Bryan Crawford was born in Santa Fe, New Mexico on 17 March 1950, son of Harvey Elihu Crawford and Johnnie Lee Young of Holland, Georgia and Wichita Falls, Texas respectively. He was raised in Albuquerque, New Mexico and attended Bel Air Elementary, McKinley Jr. High, and Del Norte High School in Albuquerque, graduating in May 1968. He completed his Bachelor of Science in Physics and Mathematics at the University of New Mexico, Albuquerque in May 1972. He was accepted for graduate studies at the University of Illinois, Champaign-Urbana where he received Master of Science degrees in Physics and Nuclear Engineering in May 1974 and May 1979 respectively.. In June, 1979, he began work at Oak Ridge National laboratory in the Consolidated Fuel Reprocessing Program and then changed to the safety analysis arena when fuel reprocessing fell out of favor. In October 1983, he went to Los Alamos, where he has worked as a nuclear safety analyst for several different companies and for the University of California who operates Los Alamos National Laboratory. He currently works in the Radiation Protection Services group at Los Alamos doing radiological engineering design and analyses for different activities at Los Alamos and in the DOE complex.. He is a registered professional engineer in the State of New Mexico. He has an interest in teaching. While at the University of Illinois, he taught different engineering physics classes for first and second year students He also has a teaching certificate and has taught mathematics and science at the secondary level in Santa Fe as circumstances allowed. In the Washington DC Temple of the Church of Jesus Christ of Latter Day Saints, he married Pamela Elaine Stafford of Olney, Illinois on 19 December 1975 for time and 383 all eternity. They are blessed with 3 daughters: Charity Annalee Crawford and Roshana Shalene Crawford, of Urbana, Illinois, Amber Adrielle Crawford, of Oak Ridge, Tennessee, and a son, Caleb Bryan Eli Crawford, Los Alamos, New Mexico. Publications and presentations include: A. Crawford, Chaired Session 11.D "Natural Phenomena Impacts to Doe Facilities", Eleventh Annual SAWG Workshop American Nuclear Society Embedded Topical Meeting, Milwaukee, WI, June 14-21, 2001. A. Crawford, "Authorization Basis Dose Assessment Calculations for a Hot Cell", Paper + presentation to Eleventh Annual SAWG Workshop American Nuclear Society Embedded Topical Meeting, Milwaukee, WI, June 14-21, 2001. Presented paper for T. Rudell, "The Cerro Grande Fire From Wildfire Modeling through the Fire Aftermath", Eleventh Annual SAWG Workshop American Nuclear Society Embedded Topical Meeting, Milwaukee, WI, June 14-21, 2001. A. Crawford, Presentation and chair of session on "Design/QA Controls for SSCs", Authorization Basis Workshop, Las Vegas, NV, January 25, 2000. G. Medford, et al, "Chemistry and Metallurgy Research (CMR) Facility Final Safety Analysis Report", LANL report CMR-FAC-95-291, October 1995. J. L. LaChance, A. Kowaczkowski, A. Crawford, J. Holderness, and G. Medford, "A Risk Assessment and Management Tool for the Chemistry and Metallurgy Research Building," Proceedings of PSAM - II (March 20-25, 1994). R. J. Romero et al, "The Chemistry and Metallurgy Research (CMR) Building Final Safety Analysis Report (FSAR)," Los Alamos National Laboratory draft report (February 1994). J. H. Holderness, G. T. Medford, and A. B. Crawford, "Multidimensional Uncertainty Propagation for Process Event Trees," Proceedings of the International Topical Meeting on Probabilistic Safety Assessment (January 26-29, 1993). R. J. Romero, et al, "The Chemistry and Metallurgy Research (CMR) Building Interim Safety Analysis Report (ISAR)," LANL report (March 23, 1992). A. Kowaczkowski, et al, "DP Safety Survey Report, HB Line, Savannah River Site," U.S. DOE Office of Defense Programs draft report (January 1, 1992). A. Kowaczkowski, et al, "DP Safety Survey Report, FB Line, Savannah River Site," 384 U.S. DOE Office of Defense Programs draft report (January 1, 1992). A. Kowaczkowski, et al, "DP Safety Survey Report, Building 12-42, South Vault, Pantex Plant," U.S. DOE Office of Defense Programs draft report (January 1, 1992). G. T. Medford, et al, "DP Safety Survey Report, Weapon Subsystem Laboratory TA-41-4 and Underground Vault TA-41-1, Los Alamos National Laboratory," U.S. DOE Office of Defense Programs draft report (September 1991). A. B. Crawford, "Comparison of `Requirements for the NMSF' and the Approved Environmental Assessment (EA) with FONSI," letter report to Dave Post, et al (July 1, 1991). C. L. Faust, and A. B. Crawford, "Draft PSAR SNML Project," LANL report SNML-89021, Rev. B. (May 1990). D. W. Stack, et al, "A Level One Probabilistic Risk Assessment of the N Reactor," Vols. 1 and 2, LANL draft letter report (October 1987). F. A. Guevara, L. G. Hoffman, W. A. Scoggins, C. M. Seabourn, C. C. Thomas, Jr., and A. B. Crawford, "Independent Safety Review of the E. I. du Pont de Nemours and Company Savannah River Plant Building 221 HB-Line Phase II Enhanced Neptunium Oxide Facility," LANL letter report (July 1987). C. A. Anderson, L. M. Carruthers, A. B. Crawford, G. F. Jones, and J. E. Hyder, "Independent Safety Review of the Teledyne Energy Systems Radioisotope Thermoelectric Generator Shipping Package," LANL letter report (October 6, 1986). A. B. Crawford and J. E. Hyder, "Independent Safety Review of the Foster Wheeler Energy Applications, Inc. Transportable Cesium Irradiator (TPCI)," LANL letter report (September 24, 1986). A. B. Crawford, J. C. Elder, F. A. Guevara, W. A. Scoggins, C. M. Seabourn, and C. C. Thomas, "Independent Safety Review of the Martin Marietta Energy Systems, Inc. Thorium-Uranium Recycle Facility Californium Facility," LANL letter report (February 20, 1986). T. P. Suchocki, et al, "Savannah River Reactor Probabilistic Safety Assessment," LANL classified draft letter report (January 1986). A. B. Crawford, J. C. Elder, C. A. Linder, and C. C. Thomas, "Technical Evaluation Report Concerning the Proposed Renewal of the Operating License for the University of Lowell Research Reactor, Docket 50-223," LANL letter report (October 16, 1985). 385 R. W. Andrae, A. B. Crawford, and J. E. Hyder, "Independent Safety Review of the Nuclear Packaging, Inc. Transportable Cesium Irradiator (TPCI) Shipping Cask," LANL letter report (September 1985). A. B. Crawford and J. E. Hyder, "Independent Safety Review of Rockwell International Rockwell Hanford Operation Proposed Plutonium Nitrate Transfer Between the PUREX Facility and the Plutonium Finishing Plant," LANL letter report (August 8, 1985). C. A. Linder, A. B. Crawford, and J. C. Elder, "Technical Evaluation Report Concerning the Proposed Construction Permit/Operating License for the University of Texas Triga Reactor, Docket 50-602," LANL letter report (May 1985). C. A. Linder and A. B. Crawford, "Technical Evaluation Report Concerning the Proposed Renewal of the Operating License for the Manhattan College Zero Power Reactor, Docket 50-199," LANL letter report (January 1985). C. C. Thomas, A. B. Crawford, J. E. Hyder, and C. A. Linder, "Technical Evaluation Report Concerning the Proposed Renewal of the Operating License for the University of Missouri-Rolla Research Reactor, Docket 50-123," LANL letter report (January 1985). A. B. Crawford, "Threat Assessment Book for the Vermont Yankee Nuclear Power Station," LANL letter report (August 1984). A. B. Crawford, J. E. Hyder, C. A. Linder, and C. C. Thomas, "Technical Evaluation Report Concerning the Proposed Renewal of the Operating License for the General Electric Nuclear Test Reactor, Docket No. 50-073," LANL letter report (June 19, 1984). A. B. Crawford, J. E. Hyder, and A. E. Sanchez-Pope, "Technical Evaluation Report Concerning the Proposed Renewal of the Operating License for the Westinghouse Nuclear Training Reactor, Docket No. 50-087," LANL letter report (March 14, 1984). A. B. Crawford, R. B. Gallagher, R. H. Guymon, K. H. Harrington, M. P. Johnson, G. T. Mays, and W. P. Poore, "Sequence Coding and Search System Coders Manual for the Licensee Event Reports, Vols. 1 and 2," Oak Ridge National Laboratory (ORNL) report ORNL/NSIC-189 (March 1983). M. L. Casada, A. B. Crawford, K. H. Harrington, and G. T. Mays, "Review of Operating Experience History of Yankee Rowe through 1980," ORNL report ORNL/NSIC-204 (August 1982). M. L. Casada, A. B. Crawford, K. H. Harrington, and G. T. Mays, "Review of Operating History of San Onofre-1 through 1980," ORNL report ORNL/NSIC-201 (May 1982). 386 R. D. Hurt, S. J. Hurrel, J. W. Wachter, T. L. Hebble, and A. B. Crawford, "Experimental Demonstration of Microscopic Process Monitoring," ORNL report ORNL/TM-7848 (January 1982). A. B. Crawford, C. A. Kukielka, G. N. Lagerberg, and G. T. Mays, "Review of Operating Experience History of Dresden-2 through 1980," ORNL report ORNL/NSIC-199 (September 1981). R. D. Hurt, J. W. Wachter, T. L. Hebble, A. B. Crawford, and S. J. Hurrel, "Microscopic Process Monitoring," Nuclear Materials Management Journal 9(1), 53-55 (Spring 1980). Permanent address: 5 Juego Place, Santa Fe, NM 87508 This dissertation was typed by the author. 387

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