RG1.065 反应堆容器封口螺栓的材料与检查 1973

October1973U.S.ATOMICENERGYCOMMISSIONREGULATORYGUllDIRECTORATEOFREGULATORYSTANDARDS:REGULATORYGUIDE1.65MATERIALSANDINSPECTIONSFORREACTORVESSELCLOSURESTUDSA.INTRODUCTIONGeneralDeignCriterion1,QualityStandardsandRecords,,ofAppendixA,GeneralDesignCriteriaforNuclearPowerPlants,to10CFRPart50,LicensingofProductionandUtili(.tionFacilities,requires,inpart,thatstructures,systems,andcomponentiimportanttosafetybedesigned,fabricated,erected,andtestedtoqualitystandardscommensuratewiththeimportanceofthesafetyunctionstobeperformed.Criterion30,Qualityof.ReactorCoolantPressureBoundary,ofthesameappendixrequires,inpart,thatcomponentswhicharepartofthereactorcoolantpressureboundarybedesigned,fabricated,erected,andtestedtothehighestqualitystandardspractical.Inaddition,Criterion31,FracturePreventionofReactorCoolantPressureBoundary,requires,inpart,thatthereactorcoolantpressureboundarybedesignedwithsufficientmargintoassurethatwhenstressedunderoperating,maintenance,testing,andpostulatedaccidentconditions(1)theboundarybehavesinanonbrittlemannerand(2)theprobabilityofrapidlypropagatingfractureisminimized.AppendixB,QualityAssuranceCriteriaforNuclearPowerPlantsandFuelReprocessingPlants,to10CFRPart50requires,inpart,thatmeasuresbeestablishedforthecontrolofspecialprocessingsuchasheattreatingandthatpropertestingbeperformed.Section5O.S5a,CodesandStandards,of10CFRPart50requires,inpart,thatpressurevesselswhicharepartofthereactorcoolantpressureboundarymeettherequirementsforClassAorClass1vesselssetforthinSectionHIoftheAmericanSocietyofMechanicalEngineers(ASME)BoilerandPressureVesselCode.ThisguidedefinesmaterialsandtestingproceduresacceptabletotheAEC.RegulatorystaffforImplementingthesecriteriawithregardtoreactorvesselUSAECREGULATORYGUIDESRegulatoryGuiduweIssuedtodescribeandmukssdtabletothePublicmethodsecmptab.totheAECReulutorystaffIrn;planwntlngepvelfIcPertOfeCommisskn
.inguistlomn.todeineateactdquesmudbythestaffInu/aimtlnhspedfcproblemaorpotulatedaccidents,ortoprovideultdntoapplicants.ReputatoryGuidesrenotubstitutesforregulationandcosvslancewithehumknotquired.Methodsandeolutiomdiffwentfthosert'OutWiSuldwlbIaeoptleItheyjrvidebasisfortilfindingsMquWtaIDtheIuenmOrcontinuenceofaeritatosnebytheComnmssion.Publishedguideswtllberv~sedPeriodically.aipproplate.toeccomniodgomanensenidtoreflect:newInformationorexperbince.closurestudboltingeforlight-water-cooieclreactors.TheAdvisoryCommittee-onReactorSafeguardshasbeenconsultedconcerningthisguideandhasconcurredintheregulatoryposition.B.DISCUSSIONTheASMEBoilerandPressureVesselCode,Section11,NuclearPowerPlantComponents,2andSectionXI,RulesforInserviceInspectionofNuclearReactorCoolantSystems.2specifycertainrequirementsassociatedwithreactorvesselclosurestudbolting.TMlregulatoryguidesuflplementstherequirementsoftheASMEcode.'High-stiengthlowalloyreactorstudboltingmaybeobtained-throughcloselycontrolledquenchingtadtemperingproceduresongradesof'steelsuchas.AmericanIronanxd'SteelInstitute(AISI)4140and4340(Ref.1).ThesesteelsaireappriovedbytheASMEasboltingmaterialsandarelisted'uiiderSectionH,MaterialSpecifications.2oftheASMECodeasSA-540GradeB-23andB-24bar,SA-193GradeB-7bar,SA-320GiadeL-43bar,andSA-194Grade7(nutsforbolting).Additionalrequirementssupplementingthesebasicmaterials-specificationsarefoundInSA-614entitledSpecification-ForSpecialRequirementsforBoltingMaterialsFor'NuclearandOtherSpecialApplications.'PropercontrolofthetemperingprocedureisnecessarytoObtain:the-desiredbalanceof'Closurestudboltingisdefinedtoincludeallstuds(studbolts),nuts,andwashersusedtofastenthepressurevesselheadtothepressurevessel.SCpiesmaybeobtainedfromthe'AmericanSocietyofMechanicalEngineers,UnitedEngineeringCenter,345East47thStreet,NewYork,NewYork10017.copweatpubmwdeukidesmybeobtainedbvrequestlaidlmlinGtil1004owdesiredtotheUS.AmncEnerWCormrublon.Wasngton.D.C.20546.,Attention:DirectorOfRegulatoryStdards.ComtsSnduguestksforlnl~onentsWe=ie.eleuencouraepdenidshouldbegenttothusecretary.ofthwCcnmollof.US.Atomic.EnegCommibsson.Wasngtono.0.0.205,Attention:Chief.PublicPrceding.Staff..TjwquidesameIssudinthlefoflomrictVanbroadslvilelone:1.PowwReactors2.Resarehd4TatReactors3.Fuels;endMaltriallFecilities4.EnvironmentalendlitingL.IaterlatendlantProtectionI.Products7.TranportatlonI.Occ0lt=loeHeatth9.AntitrustReview10.GeneralDEmechanicalproperties;Theabove-mentioned,studmaterialsivhenteniperedtoamaximumtensilestrengthof.170'ksi!(Ref.2)arerelativelyimmunetostresscorrosioncracking(SCC).AbovethisstrengthlevelthealloybecomesincreasinglysusceptibletoSCC.Therefore,.designconservatismshouldbeexercisedindeterminingthesizingofthestudssothattheminimumspecifiedstrengthlevelofthematerialselectedwillnotresultinameasuredultimatetensilestrengthexceeding170ksl.Useofmartensitic'stainlesssteelssuchasthe11-13%chromiumgradesshouldbeavoidedforreactorstudboltingapplications.Thesesteels(Ref.3)requiremorecloselycontrolledconditioningparametersthandocarbonandlow-alloysteels.Smallvariationsinheattreatmentcancauselargeincreasesinhardnessandtensilestrengthwithacorrespondingdecreaseinco