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【英文标准名称】:StandardPracticeforAnalysisandInterpretationofLight-WaterReactorSurveillanceResults,E706(IA)
【原文标准名称】:E706(IA)轻水堆监测结果的分析和说明标准方法
【标准号】:ASTME853-2001(2008)
【标准状态】:现行
【国别】:美国
【发布日期】:2001
【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】:E10.05
【标准类型】:(Practice)
【标准水平】:()
【中文主题词】:
【英文主题词】:damageexposureparameter;dpa;embrittlement;LWR;pressurevessel;reactorsurveillance;surveillancecapsule;Dosimetry;Fracturetesting--nuclearreactors;Neutronflux/fluence;Neutronradiation--nuclearmaterials/applications;Nuclearreactor
【摘要】:Theobjectivesofareactorvesselsurveillanceprogramaretwofold.Thefirstrequirementoftheprogramistomonitorchangesinthefracturetoughnesspropertiesofferriticmaterialsinthereactorvesselbeltlineregionresultingfromexposuretoneutronirradiationandthethermalenvironment.Thesecondrequirementistomakeuseofthedataobtainedfromthesurveillanceprogramtodeterminetheconditionsunderwhichthevesselcanbeoperatedthroughoutitsservicelife.Tosatisfythefirstrequirementof3.1,thetaskstobecarriedoutarestraightforward.Eachoftheirradiationcapsulesthatcomprisethesurveillanceprogrammaybetreatedasaseparateexperiment.Thegoalistodefineandcarrytocompletionadosimetryprogramthatwill,aposteriori,describetheneutronfieldtowhichthematerialstestspecimenswereexposed.Theresultantinformationwillthenbecomepartofadatabaseapplicableinastrictersensetothespecificplantfromwhichthecapsulewasremoved,butalsoinabroadersensetotheindustryasawhole.Tosatisfythesecondrequirementof3.1,thetaskstobecarriedoutaresomewhatcomplex.Theobjectiveistodescribeaccuratelytheneutronfieldtowhichthepressurevesselitselfwillbeexposedoveritsservicelife.Thisdescriptionoftheneutronfieldmustincludespatialgradientswithinthevesselwall.Therefore,heavyemphasismustbeplacedontheuseofneutrontransporttechniquesaswellasonthechoiceofadesignbasisforthecomputations.Sinceagivensurveillancecapsulemeasurement,particularlyoneobtainedearlyinplantlife,isnotnecessarilyrepresentativeoflong-termreactoroperation,asimplenormalizationofneutrontransportcalculationstodosimetrydatafromagivencapsulemaynotbeappropriate(1-67).Theobjectivesandrequirementsofareactorvessel''ssupportstructure''ssurveillanceprogramaremuchlessstringent,andatpresent,arelimitedtophysics-dosimetrymeasurementsthroughex-vesselcavitymonitoringcoupledwiththeuseofavailabletestreactormetallurgicaldatatodeterminetheconditionofanysupportstructuresteelsthatmightbesubjecttoneutroninducedpropertychanges(1,29,44-58,65-70).1.1Thispracticecoversthemethodology,summarizedinAnnexA1,tobeusedintheanalysisandinterpretationofneutronexposuredataobtainedfromLWRpressurevesselsurveillanceprograms;and,basedontheresultsofthatanalysis,establishesaformalismtobeusedtoevaluatepresentandfutureconditionofthepressurevesselanditssupportstructures(1-70).1.2Thispracticerelieson,andtiestogether,theapplicationofseveralsupportingASTMstandardpractices,guides,andmethods(seeMasterMatrixE706)(1,5,13,48,49).Inordertomakethispracticeatleastpartiallyself-contained,amoderateamountofdiscussionisprovidedinareasrelatingtoASTMandotherdocuments.Supportsubjectareasthatarediscussedincludereactorphysicscalculations,dosimeterselectionandanalysis,andexposureunits.Note18212;(Figure1isdeletedinthelatestupdate.TheuserisreferedtoMasterMatrixE706forthelatestfigureofthestandardsinterconnectivity).1.3Thispracticeisrestrictedtodirectapplicationsrelatedtosurveillanceprogramsthatareestablishedinsupportoftheoperation,licensing,andregulationofLWRnuclearpowerplants.Proceduresanddatarelatedtotheanalysis,interpretation,andapplicationoftestreactorresultsareaddressedinPracticeE560,PracticeE1006,GuideE900