ML17059A578

Non-proprietary Version of Final Rept Plant-Specific Charpy Shift Model for Nine Mile Point Unit 1.

ML17059A578
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Issue date:	12/31/1994
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MPM-59401-NP, NUDOCS 9412290180
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Attachment2NIAGAI4L.MOHAWKPOWERCORPORATIONLICENSENO.DPR-63DOCKETNO.50-220PLANTSPECIFICCHARPYSHIFTMODELFORNIjMEMILEPOINTUNIT1MPM-59401-NPDECEMBER1994(NON-PROPRIETARYVERSION)94l2290l8094i220PDRADOCK05000220PPDR

Plant-Specific,CharpyShiftModelfoi'ineMilePointVnitICCopyright1994M.P.Manahan,Sr.AllnghtsreservedCopyright1994NiagaraMohawkPowerCorporationAllrightsreservedDecember,1994ReportNo.MPM-59401-NP,...SERVINGCLIENTNEEDSTHROUGHADVANCEDTECHNOLOGY l

ReportNumberMPM-59401-NPFinalReportentitled7Plant-SpecificCharpyShiftModelforNineMilePointUnit1preparedforNiagaraMohawkPowerCorporationResearch&Development300ErieBoulevardWestSyracuse,NY13202byDr.M.P.ManahanMPMResearch&Consulting915PikeStreet,P.O.Box840Lemont,PA16851-0840December,1994NOTE:Thisreportisthenon-proprietaryversionofMPMResearch&Consulting'sReportNo.MPM-59401.Copyright1994M.P.Manahan,Sr.AllrightsreservedCopyright1994NiagaraMohawkPowerCorporationAllrightsreserved

TABLEOFCONTENTSAbstractExecutiveSummary~~~~~~~~~~~~~1.0Introduction2.0Plant-SpecificDatabaseDevelopment32.1DatabaseScrub3.0AnalyticalModel.....................3.1DefectProduction................3.2Chemical/MicrostructuralVanables...3.3HardeningMechanisms......5~~~~~~~~~~~~~5~~~~~~~~~~63.4Summuy~~~~~~~~~~~~~114.0CharpyShiftModelling144.2DatabaseSub-Division4.3RegressionAnalysis14155.0SummaryandConclusions...............~~~~~~~~~~~356.0References................~~~~~~~~~367.0Nomenclature39~AendiceeAppendixAProceduresforEvaluationofthePowerReactorEmbrittlementDataBase..~~~~~~~~~~40AppendixBImportantChemicalandMicrostructuralFeaturesinRPVNeutronDamageModellingforA302BandA302BModifiedSteel47

AbstractThisreportdocumentsthedevelopmentofaplant-specificCharpyshiftmodelforNineMilePointUnit1(NMP-1)..Theplant-specificmodelisphysicallybasedandincorporatestheimportantmicrostructuraldamagemechanismswhicharenowknownandwellunderstood.Atfluencesbelow-2x10"n/cm'typicalboilingwaterreactor(BWR)end-of-license(EOL)fluence),itisshownthatthereisnocorrelationofyieldstrengthelevationorCharpyshiftwithbulkCucontentfortheNMP-1beltlinematerials.TheanalysesanddatatrendsdemonstratethatmostBWRsoperatebelowthefluencethresholdforsignificantCuprecipitation.ThisresultsinadifferentfunctionalformfortheCharpyshift(AT3Q)modelthancurrentlyusedinRegulatoryGuide1.99(Revision2)(RG1.99(2)).TheNuclearRegulatoryCommission(NRC)modelwasbasedprimarilyonhighfluencepressurizedwaterreactor(PWR)dataandtherewereveryfewsurveillancedataavailableintheBWRfluencerangewhentheNRCmodelwasdeveloped.Depletedzone(cascadecores)damageisexpectedtobetheprimarydamagecomponentforBWRs.Sincedepletedzonesareshearabledefects,theCharpyshifthasbeenshowntobeproportionaltothesquarerootoffluence.Theinsignificantchangeinworkhardeningbehaviorexhibitedbythetensiledataconfirmthatshearabledefects(mainlydepletedzones)arethepredominantmicrostructuralfeatureresultingfromneutronirradiation.BasedonknowledgeoftheimportantradiationdamagemechanismsoperatingintheNMP-1reactorpressurevessel(RPV)steel,criteriawereestablishedfordefiningtheNMP-1plant-specificdatasetfromthelargerNRCPowerReactor-EmbrittlementDataBase(PR-EDB).ApplicationofthesecriteriatothePR-EDBresultedinadatasetcontaining37powerreactorsurveillancedatapointsinadditiontothe3fromNMP-1.Regressionanalysesyieldedanaccuratelinearmodelofh.T>>asafunctionofthesquarerootoffluence.Applicationoftheplant-specificmodeltoNMP-1willreducetheleakage/hydrostatictesttemperatureby-41'F.Thiswillreducethein-serviceleaktestdurationbyapproximatelyeighthoursforeachfuturestartup.Inaddition,outageschedulingflexibilitywillbeincreasedasaresultofthein-serviceleaktestsbeingconductedbelow212'F.

ExecutiveSummaryReactorpressurevessel(RPV)materialsundergoatransitioninfracturebehaviorfrombrittletoductileasthetesttemperatureofthematerialisincreased.CharpyV-notchtestsareconductedinthenuclearindustrytomonitorchangesinthefracturebehaviorduringirradiation.Neutronirradiationtofluencesabove-5x10"n/cm'ausesanupwardshiftintheCharpycurveandintheductile-to-brittletransitiontemperature(DBTT).TheNuclearRegulatoryCommission(NRC)hasdevelopedatrendcurvemodelandacalculativeprocedureformodellingtheDBTTshiftandthisinformationisdescribedinRegulatoryGuide1.99(Revision2)(RG1.99(2)).ThenuclearindustrytracksthisshiftthroughCharpy30ft-lbtransitiontemperaturemeasurements.AtthetimetheRG1.99(2)modelwasdeveloped,therewerefewsurveillancecapsuletestresultsavailableforfluencesintheboilingwaterreactor(BWR)operatingrange.Useofadatabasewhichconsistspredominantlyofpressurizedwaterreactor(PWR)datahasresultedinanoverlyconservativematerialbehaviormodellingfortheNineMilePointUnit1(NMP-1)beltlineplates.Thisreportshowsthatwiththelargeamountofdataavailabletoday,amuchmoreaccurateplant-specificmodelcanbedevelopedforuseintheBWRfluencerange.ThedevelopmentofaCharpyshift(b,T3Q)modelforaparticularplantisanticipatedinRG1.99(2),"TousethesurveillancedatafromaspecificplantinsteadofRegulatoryPosition1,onemustdeveloparelationshipofERTM,rtofluenceforthatplant.".Therefore,theworkdocumentedinthisreportwasundertakentodevelopaplant-specificCharpy30ft-lbtransitiontemperatureshift(h.T>>)modelwhichcanbeappliedtotheNMP-1beltlineplates.

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1.0IntroductionFerriticpressurevesselmaterialsundergoatransitioninfracturebehaviorasaresultoftheirbody-centered-cubic(BCC)latticestructure.TheCharpyV-notchtestisusedextensivelyinreactorpressurevessel(RPV)surveillanceprogramstocharacterizetheeffectsofneutronfluenceontheCharpycurve.TwokeyparameterswhicharemonitoredaretheCharpycurveshiftindexedatthe30ft-lblevel(b,T,~)andthedropintheuppershelfenergy(hUSE).CurrentregulationsusetheET3QtodeterminetheshiftintheAmericanSocietyofMechanicalEngineers(ASME)referencestressintensityfactor(Kgcurve.Therefore,pressure-temperature(P-T)operatingcurvesareshiftedtohighertemperatures(reducedoperatingwindow)preciselyinaccordancewiththeCharpycurveshiA.Itisessentialthataccuratetrendcurvemodels(b,T3pvs.fluence)beusedtoensurethattheP-Tcurvesareappropriatelycalculated.InthecaseofNineMilePointUnit1(NMP-1),accuraterepresentationoftheactualmaterialbehaviorisessentialtodeterminewhetherin-serviceleaktestingabove212'Fisnecessary.Ifitcanbeshownthatin-serviceleaktestingbelow212'Fisjustifiedwithadequatemarginsofsafety,thensubstantialsavingsinoutagetimecanberealizedinthefuture.TheNuclearRegulatoryCommission(NRC)updatedRegulatoryGuide1.99andissuedRevision2inMay,1988(RG1.99(2))[RG199].Revision3,whichisexpectedtoparalleltheRevision2workintermsoftechnicalapproachandcontent,iscurrentlybeingdeveloped.TheRevision2workinvolvedseveralchangesincluding:theseparatetreatmentofweldsandplates;theadditionofNiasamodelvariable;theremovalofPfromtheRevision1model;andtheinclusionofguidanceforcalculatingneutronattenuationthroughthevesselwallbasedonadisplacementperatom(dpa)basis.ThefinalmodeladoptedwasbasedheavilyontheworkoftwoNRCcontractors(OdetteandGutherie)[Ra84].TheRevision2modelisbasedexclusivelyontheassumptionthatonlyhardeningmechanisms(particularlyCuprecipitation)contributetotheembrittlementtrend[Od83](hencetheremovalofthePtermsincePisasurfaceactiveelement).Researchconductedoverthepastdecade(andparticularlyoverthepast5years)hasbroughtthephysicalbasisfortheNRCmodelintoquestion[IGRDM4,IGRDM5,Ig92].Itiscurrentlybelievedthatsphericalmicrovoidsrarelyforminvesselmaterials[ESER94,Au94,Ba92](Odette'shardeningtheorypostulatessignificantmicrovoidnumberdensities[Ep84]).Anenergyminimizationmodel[ESER94]showsthatinironitismorelikelythatvacancyclusterswillcollapsetoloopsorexistasalooselyconnectedcollectionofindividualvacancies.RecentAtomProbeFieldIonMicroscopy(APFIM)studieshaveshowntheprocessofCuprecipitationtobemuchmorecomplexthanoriginallyenvisioned[Mi88a,Mi88b,Au94].SeveralAPFIMworkershavereported"clouds"ofsoluteatomswhichincludeNi,Mn,andSi,andthesecloudsoccasionallyareassociatedwithCu.Miller[Mi88a]hasalsoreportedP-richregionsandtheprecipitationofsmallrod-shapedsphericalMo,Ccarbidesintheferritematrix.TheirradiationinducedcarbidesareexpectedsincethereisasignificantMoconcentrationandMo,CismorestablethantheFe,Cproducedduringfinalheattreatment.However,littleisknownatpresentabouttheextenttowhichMo,Ccontributestothetotalhardening.

Withregardtonon-hardeningembrittlement,theBritishhaverecentlydemonstratedlargeCharpyshiAsfortemperedhighPlaboratoryheatsandverifiedthemechanismtobenon-hardeningembrittlementwhichresultsfromtransportofPtoprioraustenitegrainsPvic94].McElroy[Mc94]hasalsodiscussedgrainboundaryembrittlementinhigherPRussiansteelsandMAGNOXwelds.However,itisimportanttobearinmindthatintergranular(IG)fracturehasnotbeenreportedintheU.S.steels.Thisismostlikelybecausetheconcentrationofsurfaceactiveelementsatboundarieshasnotreachedacriticallevelforfluencesinthelow10"n/cm'ange.TheU.S.lightwaterreactor(LWR)surveillanceprogramsshouldcontinuetoexamineCharpyfracturesurfacestoensurethatIGfractureisnotaproblem.Finally,theadditionofalargeamountofdatatotheNRC'sPowerReactor-EmbrittlementDatabase(PR-EDB)hasshownthatfurthersub-divisionofthedatabeyondthatofplateandweldcategoriesisneeded.Thispointismorefullydiscussedlaterin,thisreport.FurtherdiscussionconcerningthephysicalmechanismsofneutrondamageinRPVsteelsisalsoprovidedinthereportsectionswhichfollow.Inlightoftheseconsiderations,andthefactthattheRG1.99(2)wasdevelopedusingadatasetwithfewboilingwaterreactor(BWR)fluencerangedata,aprudentapproachistodevelopaplant-specifictrendcurvefortheNMP-1beltlineplates.Therefore,thefocusofthisreportisstrictlyonthemodifiedA302B(A302M)material.Themodelisreferredtoas"plant-specific"becausethedatabasewassubdividedtoalevelwhichyieldsadatasetwhichisrepresentativeoftheA302MmaterialintheNMP-1beltlineregion.

2.0Plant-SecificDatabaseDevelomentTheNRC'sPR-EDB[PREDB94]wasusedastheprimarysourceofdataformodeldevelopment.ThePR-EDBisacollectionofdatafromsurveillanceprogramsofcommercialnuclearreactors(primarilyU.S.reactors).ThePR-EDBisonedatabasecontainedwithintheNRC'sEmbrittlementDataBase(EDB)whichal'soincludesdatafromtestreactorirradiations.Whilemanyusefulinsightscanbegainedfromanalysisoftestreactordata,thecurrentmodellingeFortfocusedsolelyoncommercialreactordatasincethegoalisto'produceamodelwhichcanbeapplieddirectlytoNMP-1.Theuseoftestreactordatawouldnot,ingeneral,beappropriatesincetherearewidelyvaryingflux,temperature,andneutronspectraintestreactorirradiations.data:TheversionofthePR-EDB(Version2)usedinthisstudycontainsthefollowingCharpy252capsulesfrom96reactors207heataffectedzone(HAZ)Charpycurves(98diFerentHAZs)227weldCharpycurves(105differentwelds)524basematerialCharpycurves(136differentbasematerials)2.1DatabaseScrubSincethegoalofthepresentworkistodevelopaCharpyshiftplatemodelforNMP-1,thefirststepwastodeleteweldandHAZdatafromthePR-EDBfiles.TheNMP-1datawerethencorrected(theNMP-1datainthecurrentPR-EDBdoesnotreflectthematerialmix-upresolution)anddataforseveralplants(ex.,OysterCreek)wereverifiedforaccuracyincaseswheresurveillancereportswerereadilyavailableatMPMResearch&Consulting.Inconsistencies,suchastemperatureandenergyunits,werethencorrectedinthePR-EDBfilescontainingtheplatedata.

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3.0AnalticalModelThissectionofthereportreviewsneutrondamagemechanismsandprovidesthebasisforthephysicallybasedmodel.ThediscussionislimitedtodamagemechanismswhicharerelevanttotheA302Mmaterial.Theobjectiveistodeveloptheproperfunctionalformforleast-squaresregressionusingtheU.S.LWRPR-EDB.3.1DefectProduction3.2Chemical/MicrostructuralVariablesSteelsforRPVplates,suchasA302MandA533B,are0.23Csteelswithabout1.35Mn,0.5Niand0.5Mo(weightpercents).Inaddition,theirlevelsofimpuritiesortrampelementsaregenerally0.01-0.02P,0.01-0.02Sand0.1-0.3Cu[Kh80].Theseimpuritiescanhavedramaticeffectsonmechanicalbehaviordependinginpartontheprocessingofthesteels.'oproducetheheavyplateneededforRPVs,thesteelsaregenerallycastintolargeingotswhich,aftercooling,arehotrolledorforgedintothickplateswhicharethenre-austenitized,quenched,andtempered.Theplatesarethenweldedintothevesselandthefinalstructureisstress-reliefannealedandfurnacecooled.

3.3HardeninMechanismsExtensiveLWR,LiquidMetalFastBreederReactor,andfusionreactordatabaseshaveestablishedthatexposureofallmetalstofastneutronfluxesresultsinanincreaseintheyieldstrengthofthematerial.Inthecaseofferriticsteelsirradiatedtohighfluences,theyieldstrengthisobservedtoincrease,theultimatetensilestrength(UTS)increasesthesameastheyieldstrength,orforsomesteelsmodestly,andtheductility(measuredastotaloruniformelongationinatensiletestorreductionofarea)isreduced.Neutronirradiationincreasesthestrengthofametalintwoways:SourceHardenin-itincreasesthestressrequiredtostartadislocationmovingwithintheslipsystem.FrictionHardenin-oncethedislocationismoving,itwillbeimpededbyobstaclesclosetoorlyingintheslipplane.InBCCmetals,thepre-existingmatrixCatmospheresareveryeffectiveinpinningdislocationspriortotheapplicationofstress,andthedepletedzonesformedatLWRfluencelevelswouldnotbeexpectedtosignificantlyaffectthesourcehardening.Therefore,wefocusattentiononfrictionhardeninginthediscussionwhichfollows.

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3.4Summa

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4.0CharShiftModellinExaminationoftheET,Oandh,USEtrendswithfluenceandcompositionindicatethattheA508forgingsshouldbemodelledasaseparatesub-divisionofthedatabase.Accordingly,inthereportsectionswhichfollow,theA302B,A302M,andA533BmaterialsaregroupedtogetherfordevelopmentoftheNMP-1material-specificmodel.13

4.3ReressionAnalsis

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5.0SummarandConclusions34

6.0References[ASM]MetalsHandbook,NinthEdition,Volume1,PropertiesandSelection:IronsandSteels.[AU94]P.Auger,P.Pareige,M.Akamatsu,J-C.VanDuysen,"MicrostructuralCharacterizationofAtomClustersinIrradiatedPressureVesselSteelsandModelAlloys",tobepublishedintheJournalofNuclearMaterials.[Ba92]A.Barbu,T.N.Le,N.Lorenzelli,F.MauryandC.H.deNovion,"ElectronIrradiationEffectsonCuPrecipitationinIron-BasedDiluteAlloys",MaterialsScienceForumVols.97-99,1992,pp.351-358.[Do71]C.C.Dollins,Radiat.Eff.,11:33,1971.[Ep84]Perrin,J.F.,Wullaert,R.A.,Odette,G.R.,andLombrozo,P.M.,"PhysicallyBasedRegressionCorrelationsofEmbrittlementDataFromReactorPressureVesselSurveillancePrograms",FinalReporttoEPRI,January,1984.[ESER94]Manahan,M.P.,Cuddy,L.J.,"ThePhysicalBasisforUpperShelfEnergyDropinIrradiatedReactorPressureVesselSteels",FinalReporttoESEERCO,March,1994.[Fa89]Fabry,etal,"ImprovementofLWRPressureVesselSteelEmbrittlementSurveillance:1984-1986ProgressReportonBelgianActivitiesinCooperationwithUSNRCandOtherREEDPrograms",ReactorDosimeMethodsAlicationsandStandardizationASTMSTP1001,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1989,pp.17-37.[G171]Gladman,T.,Holmes,B.,andMcIvor,L.D.,"EffectofSecondPhaseParticlesontheMechanicalPropertiesofSteel",p.78,IronandSteelInstitute,London,1971.Pg92]Igata,N.andKayano,H.,"DuctilityandHardeningofNeutron-IrradiatedFe-CrandFe-Cr-NiSteels",EffectsofRadiationonMaterials:15thInternationalSymposium,ASTMSTP1125,R.E.Stoller,A.S.Kumar,andD.S.Gelles,Eds.,AmericanSocietyforTestingandMaterials,Philadelphia,1992,pp.1243-1255.PGRDM4]"InternationalGrouponRadiationDamageMechanismsinPressureVesselSteels",IGRDM-IV,November16-20,1992,Fontainbleau,France.PGRDM5]"InternationalGrouponRadiationDamageMechanismsinPressureVesselSteels",IGRDM-IV,May2-6,1994,SantaBarbara,CA.35

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[Kh80]J.N.Khass,A.J.Giannuzzi,D.A.Hughes,"RadiationEffectsinBoilingWaterReactorPressureVesselSteels",JournalofEngineeringMaterialsandTechnology,Vol.102,April1980,pp.177-185.[Li94]E.P.Lippincott,"WestinghouseSurveillanceCapsuleNeutronFluenceReevaluation",WestinghouseElectricCorporation,ReportNo.WCAP-14044,April,1994.[Lu85]G.E.Lucas,G.R.Odette,P.M.Lombrozo,andJ.W.Sheckherd,"EffectsofComposition,Microstructure,andTemperatureonIrradiationHardeningofPressureVesselSteels",EffectsofRadiationonMaterials:TwelAhInternationalSymposium,ASTMSTP870,F.A.GarnerandJ.S.Perrin,Eds.,AmericanSocietyforTestingandMaterials,Philadelphia,1985,pp.900-930.[Ma60][Ma62]M.J.MakinandF.J.Minter,ActaMet.,8:691(1960).M.J.MakinandT.H.Blewitt,ActaMet.,10:241(1962).[Ma92]Manahan,M.P.,"UpperShelfEnergyDropTrendCurveModelling",NiagaraMohawkPowerCorporation,NMPCProjectNo.03-9425,ReportNo.MPM-1292315,November30,1992.[Mi88a]McElroy,R.,"PresentationonTemperEmbrittlement",presentedattheJanuary,1994ASTME10meeting,SanFrancisco,CA.M.K.MillerandM.G.Burke,"MicrostructuralCharacterizationofIrradiatedPWRSteelsUsingtheAtomProbeField-IonMicroscope",EnvironmentalDegradationofMaterialsinNuclearPowerSystems-WaterReactors,G.J.TheusandJ.R.Weeks,Eds.,TheMetallurgicalSociety,1988.[Mi88b]M.K.Miller,D.T.Hoelzer,F.Ebrahimi,J.R.HawthorneandM.G.Burke,"MicrostructuralCharacterizationofIrradiatedFe-Cu-Ni-PModelSteels",EnvironmentalDegradationofMaterialsinNuclearPowerSystems-WaterReactors,G.J.TheusandJ.R.Weeks,Eds.,TheMetallurgicalSociety,1988.[0d83]G.R.Odette,"OntheDominantMechanismofIrradiationEmbrittlementofReactorPressureVesselSteels",PergamonPressLtd.,1983.[Od85]Odette,G.R.,Lombrozo,P.M.,andWallaert,R.A.,"RelationshipBetweenIrradiationHardeningandEmbrittlementofPressureVesselSteels",EffectsofRadiationonMaterials:TwelAhInternationalSymposium,ASTMSTP870,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1985,pp.840-860.36

[0176]Olander,D.,"FundamentalAspectsofNuclearReactorFuelElements",U.S.DepartmentofCommerce,NationalTechnicalInformationService,1976.[PREDB94]PR-EDB:PowerReactorEmbrittlementDataBase,Version2,NUREG/CR-4816.[Ra84]P.N.Randall,"BasisforRevision2ofU.S.NRCRegulatoryGuide1.99",U.S.NuclearRegulatoryCommission,1984.[Rg199]U.S.NuclearRegulatoryCommissionRegulatoryGuide,Revision2,May1988.[Ri51]Rineholt,J.A.,andHarris,Jr.,W.J.,"EffectofAlloyingElementsonNotchToughnessofPearliticSteels",TransactionsoftheAmericanSocietyforMetals,Vol.43,1951,p.1175-1214.[Se58]A.Seeger,inProceedingsoftheSecondUnitedNationsInternationalConferenceonthePeacefulUsesofAtomicEnergy,Geneva,1958,vol.6,p.250,UnitedNations,NewYork,1958.[St85]Steel,L.E.,Davies,L.M.,Ingham,T.,andBrumovsky,M.,"ResultsoftheInternationalAtomicEnergyAgencygAEA)CoordinatedResearchProgramsonIrradiationEffectsonAdvancedPressureVesselSteels",EffectsofRadiationonMaterials:TwelAhInternationalSymposium,ASTMSTP870,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1985,pp.863-899.[Ta89]Taboada,A.,Randall,P.N.,andSerpan,C.Z.Jr.,"OverviewofU.S.ResearchandRegulatoryActivitiesonNeutronIrradiationEmbrittlementofPressureVesselSteel",RadiationEmbrittlementofNuclearReactorPressureVesselSteels:AnInternationalReviewhirdVolumeASTMSTP1011,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1989,pp.27-38.37

7.0NomenclatureAAAAPFIMASMEBCCBWR6an~DBTTDPAEDBEOLHAZICPSIGKa,LWRNMP-1NMPCNRCP-TPR-EDBPWRb,RTNDrRBRG1.99(2)RPVRTET)0b,USEUSEUTSXRFangstromatomicabsorptionAtomProbeFieldIonMicroscopyAmericanSocietyofMechanicalEngineersbody-centeredcubicboilingwaterreactorchangeinflowstressductilebrittletransitiontemperaturedisplacementsperatomEmbrittlementDataBaseEnd-of-LicenseheataffectedzoneinductivelycoupledplasmaspectrometryIntergranularASMEreferencestressintensityfactorcurveLightWaterReactorNineMilePointUnit1NiagaraMohawkPowerCorporationNuclearRegulatoryCommissionPressure-TemperaturePowerReactor-EmbrittlementDatabasepressurizedwaterreactorneutroninducedshiftinASMEnil-ductilityreferencetemperatureRusselM3rownRegulatoryGuide1.99(Revision2)reactorpressurevesselroomtemperatureCharpycurveshiftindexedatthe30ft-ibdropintheuppershelfenergyuppershelfenergyultimatetensilestrengthx-rayfluorescence38 I'

Appendices39 cg,g.

AppendixAProceduresForEvaluationofThePowerReactorEmbrittlementDataBasePartIDataBaseEvaluation40

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PartHDataAnalsisforPR-EDBersion244

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AppendixBImortantChemicalandMicrostructuralVariablesinRPVNeutronDamaeModellinforA533BA302BandA302BModifiedSteel47 l>~++%awgpqw,~t~i Pages4Sand49intentionallyleftblank

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