ASTM C1682-2009 核废料支援地学处置贮藏库的特性描述标准指南

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【英文标准名称】:StandardGuideforCharacterizationofSpentNuclearFuelinSupportofGeologicRepositoryDisposal
【原文标准名称】:核废料支援地学处置贮藏库的特性描述标准指南
【标准号】:ASTMC1682-2009
【标准状态】:现行
【国别】:
【发布日期】:2009
【实施或试行日期】:
【发布单位】:美国材料与试验协会(US-ASTM)
【起草单位】:C26.13
【标准类型】:(Guide)
【标准水平】:()
【中文主题词】:涂覆;腐蚀;受损燃料;被降解的涂层;工程屏障系统(EBS);不合格燃料;地学处置贮藏室;过渡时期干藏;核废料运输;核废料(SNF);废物包装实施;废物形态降解;氢化锆
【英文主题词】:cladding;corrosion;damagedfuel;degradedcladding;engineeredbarriersystem(EBS);failedfuel;geologicrepository;interimdrystorage;SNFtransport;spentnuclearfuel(SNF);wastepackageperformance;wasteformdegradation;zirconiumhydride
【摘要】:Inordertodemonstrateconformancetoregulatoryrequirementsandsupportthepostclosurerepositoryperformanceassessmentinformationisrequiredabouttheattributes,characteristics,andbehavioroftheSNFneedtobedetermined.ThesepropertiesoftheSNFinturnsupportthetransport,interimstorage,andrepositorypreclosuresafetyanalyses,andrepositorypostclosureperformanceassessment.TheinterimdrystorageofcommercialLWRSNFisregulatedperCodeofFederalRegulations,Title10,Part72,whichrequiresthatthecladdingmustnotsustainduringtheinterimstorageperiodanyx201C;grossx201D;damagesufficienttoreleasefuelfromthecladdingintothecontainerenvironment.However,claddingdamageinsufficienttoallowthereleaseoffuelduringtheinterimstorageperiodmaystilloccurintheformofsmallcracksorpinholes.Thesecracks/pinholescouldbesufficienttoclassifythefuelasx201C;failedfuelx201D;orx201C;breachedfuelx201D;perthedefinitionsgiveninSection3forrepositorydisposalpurposes,becausetheycouldallowcontactofwatervapororliquidwiththespentfuelmatrixandthusprovideapathwayforradionuclidereleasefromthewasteform.Also,pinholes/cracksinfuelrodsindryorwetinterimstoragecanalsodevelopintomuchlargerdefects(forexample,thephenomenonofcladdingx201C;unzippingx201D;)underlong-termrepositoryconditions.ThereforeSNFcharacterizationshouldbeadequatetodeterminetheamountofx201C;failedfuelx201D;foreitherusageasrequired.Thiscouldinvolvetheexaminationofreactoroperatingrecords,ultrasonictesting,sipping,andanalysisoftheresidualwateranddryingkineticsofthespentfuelassembliesorcanisters.IntheU.S.thedisposalofspentnuclearfuel(SNF)andhighlevelwaste(HLW)inageologicrepositoryisregulatedundertheCodeofFederalRegulations,Title10,Part60(whichpertainstoanygeologicrepositorybuiltintheU.S.),CodeofFederalRegulations,Title10,Part63(whichpertainstotherepositorylocatedatYuccaMountain,Nevada),andCodeofFederalRegulations,Title40,Part191(whichestablishedtheradiationprotectionlevelstherepositorymustmeet).Eachoftheseregulationscontainsconstraintsandlimitationsonthechemicalorphysical(orboth)propertiesandlong-termdegradationbehaviorofthespentfuelandHLWintherepository.EvaluatingthedesignandperformanceoftheWF,WP,andtherestoftheengineeredbarriersystem(EBS)withrespecttotheseregulatoryconstraintsrequiresknowledgeofthechemical/physicalcharacteristicsanddegradationbehavioroftheSNFthatcouldbeprovidedbythetestinganddataevaluationmethodsprovidedbythisguide,asfollows:CodeofFederalRegulations,Title10,Part60Sections135and113requirethatthewasteformbeamaterialthatissolid,non-particulate,non-pyrophoric,andnon-chemicallyreactive,thatthewastepackagecontainnoliquid,particulates,orcombustiblematerialsandthatthematerials/componentsoftheEBSbedesignedtoprovidex2014;assuminganticipatedprocessesandeventsx2014;substantiallycompletecontainmentoftheHLWfortheNRC-designatedregulatoryperiod.CodeofFederalRegulations,Title10,Part63Section113requiresthattheEBSbedesignedsuchthat,workingincombinationwiththenaturalbarriers,theperformanceassessmentoftheEBSdemonstratesconformancetotheannualreasonabl......