Title of article
Block-typeHTGRspentfuelprocessing:CEAinvestigationprogramandinitialresultsOriginalResearchArticle
Author/Authors
MichelMasson، نويسنده , , StéphaneGrandjean، نويسنده , , JerômeLacquement، نويسنده , , StéphaneBourg، نويسنده , , JeanMarieDelauzun، نويسنده , , JacquesLacombe، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2006
Pages
10
From page
516
To page
525
Abstract
ConsideringthecriteriaputforwardbytheGenerationIVForumtoselectfuturenuclearsystems(preservationofresources,minimizationoffinalwasteimpact,economics,etc.),theimpetusfortheveryhigh-temperatureHe-cooledreactorraisestheissueofprocessingthefuelinthecontextofaclosedcyclewithactiniderecycling.Duetotheuniquestructureoftheparticlefuelusedforthisclassofreactors,thedifficultiesessentiallyinvolveaccessibilitytotheuraniumkernelscoatedbycarbonandSiClayersanddispersedinalargevolumeofgraphite.Startingfrompastexperienceinthisfield,aresearchprogramhasbeenrecentlyundertakenbytheCEAtoproposeattractivesolutions.Themechanicalextractionofcompactsfromthespentfuelblocksappearstobeapromisingapproach,aswellasremovingthegraphitefromthecompactsbypulsedcurrentstofreetheparticles.Subsequentremovalofthecarbonandsiliconcarbidelayersbyhightemperatureoxidationorbycarbochlorinationtoaccessthekernelsisassessed.Foractiniderecycling,gelationappearstobeasuitableprocessforfabricatingthekernels.ThispaperprovidesabriefoverviewsofthedevelopmentscurrentlyinprogressattheCEA.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2006
Journal title
Nuclear Engineering and Design Eslah
Record number
896013
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