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当前位置:首页 > 行业资料 > 国内外标准规范 > RG1.099 反应堆压力容器材料的放射性脆化 1988
Revlalon2May1988U.S.NUCLEARREGULATORYCOMMISSIONiREGULATORYGUIDEOFFICEOFNUCLEARREGULATORYRESEARCHREGULATORYGUIDE1.99(TaskME3054)RADIATIONEMBRITrLEMENTOFREACTORVESSELMATERIALSA.INTRODUCTIONGeneralDesignCriterion31,FracturePreventionofReactorCoolantPressureBoundary,ofAppendixA,'GeneralDesignCriteriaforNuclearPowerPlants,to10CFRPart50,DomesticLicensingofProductionandUtilizationFacilities,requires,inpart,thatthereactorcoolantpressureboundarybedesignedwithsufficientmargintoensurethat,whenstressedunderoperating,maintenance,testing,andpostulatedaccidentconditions,(l)theboundarybehavesinanonbrittlemannerand(2)theprobabilityofrapidlypropagatingfractureisminimized.GeneralDesignCriterion31alsorequiresthatthedesignreflecttheuncertaintiesindeterminingtheeffectsofirradiationonmaterialproperties.Appendix0,FractureToughnessRequirements,andAppendixH,ReactorVesselMaterialSurveillanceProgramRequirements,whichimplement,inpart,Criterion31,necessitatethecalculationofchangesinfracturetoughnessofreactorvesselmaterialscausedbyneutronradiationthroughouttheServicelife.ThisguidedescribesgeneralproceduresacceptabletotheNRCstaffforcalculatingtheeffectsofneutronradiationembrittlementofthelow-alloysteelscurrentlyusedforlight-water-cooledreactorvessels.ThecalculativeproceduresgiveninRegulatoryPosition1.1ofthisguidearenotthesameasthosegiveninthePressurizodThermalShockrule(§50.61,FractureToughnessRequirementsforProtectionAgainstPressurizedThermalShockEvents,of10CFRPart50)forcalculatingRTPTS,thereferencetemperaturethatistobecomparedtothescreeningcriteriongivenintherule.TheinformationonwhichthisRevision2isbasedmayalsoaffectthebasisforthePTSrule.Thestaffispresentlyconsideringwhethertoproposeachangeto§50.61.TheAdvisoryCommitteeonReactorSafeguardshasbeenconsultedconcerningthisguideandhasconcurredintheregulatoryposition.Anyinformationcollectionactivitiesmentionedinthisregulatoryguidearecontainedasrequirementsin10CFRPart50,whichprovidestheregulatorybasisforthisguide.Theinformationcollec-tienrequirementsin10CFRPart50havebeenclearedunderOMBClearanceNo.3150-0011.B.DISCUSSIONSomeNRCrequirementsthatnecessitatecalculationofradiationembrittlementare:1.ParagraphV.AofAppendix0requirestheeffewsofneutronradiationtobepredictedfromtheresultsofperdnentradiationeffctsstudies.ThisguideprovidessuchresultsintheformofcalculativeproceduresthatareacceptabletotheNRC.2.ParagraphV.BofAppendix0describesthebasisforsettingtheupperlimitforpressureasafunctionoftemperatureduringheatupandcooldownforagivenserviceperiodintermsofthepredictedvalueoftheadjustedreferencetemperatureattheendoftheserviceperiod.3.ThedefinitionofreactorvesselbetlinegiveninParagraph11.FofAppendixGrequiresidentificationofregionsofthereactorvesselthatarepredictedtoexperiencesufficientneutronradiationembrittlementtobeconsideredintheselectionofthemostlimitingmaterial.ParagraphsM.AandIV.A.1specifytheadditionaltestrequirementsforbeitliematerialsthasupplementtherequirementsforreactorvesselmaterialsgenerally.4.Paragraphn.BofAppendixHincorporatesASTME185byreference.Paragraph5.1ofASTME18542,StandardPracticeforConductingSurveillanceTestsforLight-WaterCooledNuclearPowerReactorVessels(Ref.1),requiresthatthematerialstobeplacedinsurveillancebethosethatmaylimitoperationofthereactorduringitslifetime,ie.,thoseexpectedtohavethehighestadjustedreferencetemperatureorthelowestCharpyupper-shelfenergyatendoflife.Bothmeasuresofradiationembrittlementmustbeconsidered.InParagraph7.6ofASIME185-32,therequirementsforthenumberofcapsulesandthewithdrawalschedulearebasedonthecalculatedamountofradiktonembrittlementatendoflife.USNRCREGULATORYGUIDESTheguidesareIssuedInthefollowingtenbroaddivisions:RegulatoryGuidesareissuedtodescribeandmakeavailabletothepublicmethodsacceptabletotheNRCstaffofimpieenting1.PowerReactors6.ProductsspecificpartsoftheCommission'sregulations,todelineatetech.2.ResearchandTestReactors7.TransportationniquesusedbythestaffInevaluatingspecificproblemsorpostu-3.FuelsandMaterialsFacilities8.OccupationalHealthlatedaccidentsortoprovideguidancetoapplicants.Regulatory4.EnvironmentalandSiting9.AntitrustandFinancialReviewGuidesarenotsubstitutesforregulations,andcompliancewith5.MaterlalsandPlantProtection10.Generalthemisnotrequired.MethodsandsolutionsdifferentfromthosesetoutIntheguideswillbeacceptableiftheyprovideabasisforthefindingsrequisitetotheissuanceorcontinuanceofapermitorbepurchasedfromtheGovernmentlicenseIntingOfficeatthecurrentGPOprice.informationoncurrentGPOpricesmaybeobtainedbycontactingtheSuperintendent-ofThisguidewasissuedafterconsiderationofcommentsreceivedfromDocuments,U.S.GovernmentPrintingOffice,PostOfficeBoxthepublic.Commentsandsuggestionsforimprovementsinthese37082,Washington,DC20013-7082,telephone(202)275-2060orguidesareencouragedatalltimes,andguideswillberevised,as(202)275-2171.arpropriate,toaccommodatecommentsandtoreflectnewinformationorexperience.issuedguidesmayalsobepurchasedfromtheNationalTechnicalWrittencommentsmaybesubmittedtotheRulesandProceduresInformationServiceonastandingorderbasis.DetailsonthisBranch,ORRA
本文标题:RG1.099 反应堆压力容器材料的放射性脆化 1988
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