Reactor Cladding MaterialP1-76CN245-87V. TsygvintsevRussianFederationX-ray diffraction structural analysis of structuraland fuel materials for BN-600 reactorP1-77CN245-120D. LorenzoFranceInsertion reliability studies for the RBC-typecontrol rods in ASTRIDP1-78CN245-124V. ShvetsovaRussianFederationSynergetic mechanism of high temperatureradiation embrittlement of austenitic steelsunder long term neutron irradiation at hightemperaturesP1-79CN245-126F. RouillardFranceEvaluation of cobalt free coatings as hard facingmaterial candidates in sodium fast reactorP1-80CN245-152N. StauffUSATrade-off Study of Advanced TransmutationFuels in Sodium cooled Fast ReactorsP1-81CN245-166V. ShurupovRussianFederationApplication of physicalmodelling whencalibratinghighrangeelectromagneticflowmetersP1-82CN245-169K.V.SureshKumarIndiaExtending the grid plate life - Incorporation oflower axial shield for FBTRP1-83CN245-171I. KonovalovRussianFederationThe behaviour features of fuel elements withnitride fuel - theory and experimentP1-84CN245-176B. YinChinaFabrication process of NpO2pelletsP1-85CN245-178E. KinevRussianFederationPost-reactorstateofthestandardandexperimental BN-600 fuel kindsP1-86CN245-207W. CarmackUSAOverview of the U.S. DOE fast reactor fueldevelopment program
236Track 5PostersIdPresenterCountryTitleP1-87CN245-214I. PeshkichevRussianFederationMathematical modelling of the mononitridenuclear fuel production processesP1-88CN245-227P. AgostiniItalyTowards a new approach for structural materialsof Lead Fast ReactorsP1-89CN245-234S. StarikovRussianFederationMultiscale computermodelling of nuclear fuelproperties at radiation and thermal impactsP1-90CN245-241Y. YamadaJapanA Conceptual design of engineering-scale plantappliedthesimplifiedMA-bearingfuelfabrication processP1-91CN245-244K. SuzukiJapanExperience on MOX fuel fabrication for fastreactor at PFPFP1-92CN245-245T. MatsumotoJapanThermal conductivity of non-stoichiometric(Pu0.928Am0.072)O2-xP1-93CN245-251K. MorimotoJapanTheinfluenceofporosityonthermalconductivity of low-density uranium oxide.P1-94CN245-253P. PillaiIndiaDevelopmentofUltraSub-sizeTensileSpecimen for Evaluation of Tensile Propertiesof Irradiated MaterialsP1-95CN245-254Y. SekioJapanEvaluation of irradiation-induced point defectsmigration during neutron irradiation in modified316 stainless steelP1-96CN245-256S. HirookaJapanMechanical and Thermal Properties of (U,Pu)O2-xP1-97CN245-264V. PastukhovRussianFederationStatistical investigation of radiation-inducedporosity in BN fuel claddings using scanningelectron microscopyP1-98CN245-265S. BarsanovaRussianFederationChange in Mechanical Properties of Spent FastReactor CladdingsP1-99CN245-272Y. de CarlanGIFUse of ion irradiations to help design ofadvanced austenitic steelsP1-100CN245-287A. FilanovichRussianFederationThermal and elastic properties of CexTh1-xO2mixed oxides: a self-consistent thermodynamicapproachP1-101CN245-291M. TarasovaRussianFederationThe way of nitride fuel producing by highvoltage electro-discharge compactionP1-102CN245-322B. HaryFranceOptimizationofthethermomechanicaltreatmenttoachieveahomogeneousmicrostructure in a 14Cr ODS steelP1-103CN245-338J. LeeKorea,Republic ofThe Effect of Proton Irradiation on theCorrosion Behaviours of Ferritic/MartensiticSteel
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