Fissile-Materials-Summary-irsn_sect03_146

Fissile-Materials-Summary-irsn_sect03_146 - RPUBLIQUE...

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RÉPUBLIQUE FRANÇAISE INSTITUT DE RADIOPROTECTION ET DE SÛRETÉ NUCLÉAIRE DÉPARTEMENT DE PRÉVENTION ET D'ÉTUDE DES ACCIDENTS S ervice d' É tudes de C riticité Courrier : BP 17, 92262 FONTENAY-AUX-ROSES CEDEX, France - Téléphone : (33) 01.58.35.74.21 - Télécopie : (33) 01.46.57.29.98 Siège social : 77-83, avenue du Général de Gaulle - 92140 CLAMART - Standard : (33) 01 58 35 88 88 - RCS Nanterre B 440 546 018 Demandeur DG TREN Mme Van den Berghe Référence de la demande Contract N° 4.1020/D/01-001 Numéro de la fiche d'action Référence de la note SEC/T/03.146 TITRE : Final report Evaluation of nuclear criticality safety data and limits for actinides in transport C4/TMR2001/200-1 RESUME : This final report gives the results of the project including the data of the interim report and the work achieved in the last phases of the project. First, the report gives a preliminary list of actinide nuclides that should be introduced in the regulations of the transport of radioactive materials, considering their potential effect on reactivity. Secondly, as many of those actinide nuclides are supposed to be transported in very small quantities, a rule to except them from the fissile requirements was set. This rule is based on calculations for Normal and Accidental Conditions of Transport and takes into account: different parameters that may have an influence on reactivity (like reflectors or moderators) and some safety factors to include the discrepancies between the results obtained by the participants (IRSN, EMS and SERCO). A IND. DATE OBJET R éservé à l'unité A utorisation de diffusion A uteur(s) V érificateur * C hef d' U nité C hef du DPEA D irecteur G énéral de l' IRSN Noms C. LAVARENNE / D. MENNERDAHL / C. DEAN V. ROUYER P. COUSINOU p.i. M. POURPRIX J. REPUSSARD Dates Signatures * rapport sous assurance de la qualité
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REFERENCE : SEC/T/03.146 INDICE : A PAGE : 2 / 40 SUMMARY 1. Introduction. ........................................................................................ 2 2. The nuclides properties . .................................................................... 5 2.1 Theoretical densities of single nuclides, elements and mixtures . ......................................... 5 2.2 Actinide nuclides ways of formation and radioactive half-lives . ............................................ 5 2.3 Radioprotection safety restrictions - Types of packages . ..................................................... 7 2.4 Nuclear properties Cross sections . ................................................................................... 8 2.4.1 Different types of nuclides regarding fissions. ............................................................. 8 2.4.2 Nuclear cross sections capability to sustains a chain reaction . ................................ 9 2.4.2.1 Cross section evaluations. ................................................................................... 9 2.4.2.2 Capability to sustain a chain reaction. ................................................................ 11 2.5 Criticality properties . .......................................................................................................... 14 3. Calculations in normal and accidental conditions. ........................ 18 3.1 Criticality risk in normal conditions of transport . ................................................................. 18 3.1.1 Calculations with thermal spectrum fissile actinide nuclides. ..................................... 20 3.1.1.1 Calculations without a steel wrapper. ................................................................. 20 3.1.1.2 Calculations with a steel wrapper. ...................................................................... 21 3.1.1.3 Calculations with others moderators . ................................................................. 21 3.1.2 Calculations with fast spectrum fissile actinide nuclides. ........................................... 23 3.1.2.1 Calculations with APOLLO 2 MORET 4 . ......................................................... 23 3.1.2.2 Calculations with TRIPOLI 4 . ............................................................................. 23 3.1.3 Conclusions on Normal Conditions of Transport. ...................................................... 24 3.2 Criticality risk in accidental conditions of transport . ............................................................ 24 3.3 Comparison between the normal and the accidental conditions. ........................................ 25 4. Method for the definition of exception criteria. .............................. 27 4.1 Additional parameters leading to an increase of reactivity.
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Fissile-Materials-Summary-irsn_sect03_146 - RPUBLIQUE...

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