ASTM E706-2002 E706(0)轻水反应堆压力容器监视标准的标准主模型
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【英文标准名称】:StandardMasterMatrixforLight-WaterReactorPressureVesselSurveillanceStandards,E706(0)
【原文标准名称】:E706(0)轻水反应堆压力容器监视标准的标准主模型
【标准号】:ASTME706-2002
【标准状态】:作废
【国别】:
【发布日期】:2002
【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】:(Guide)
【标准水平】:()
【中文主题词】:核技术;反应釜;核能;模型;轻水反应堆;压力容器;监督(认可)
【英文主题词】:dosimetry;matrixdata/programs;nuclearreactorvessels-light-watercooled;nuclearreactorvessels-surveillance;light-waterreactorpressurevesselsurveillancestandards,master
【摘要】:1.1Thismastermatrixstandarddescribesaseriesofstandardpractices,guides,andmethodsforthepredictionofneutron-inducedchangesinlight-waterreactor(LWR)pressurevessel(PV)andsupportstructuresteelsthroughoutapressurevessel''sservicelife(Fig.1).SomeoftheseareexistingASTMstandards,someareASTMstandardsthathavebeenmodified,andsomeareproposedASTMstandards.GeneralrequirementsofcontentandconsistencyarediscussedinSection6.Moredetailedwriters''andusers''information,justification,andspecificrequirementsfortheninepractices,tenguides,andthreemethodsareprovidedinSections3-5.ReferenceddocumentsarediscussedinSection2.Thesummary-typeinformationthatisprovidedinSections3and4isessentialforestablishingproperunderstandingandcommunicationsbetweenthewritersandusersofthissetofmatrixstandards.Itwasextractedfromthereferenceddocuments,Section2andreferences(1-106)forusebyindividualwritersandusers.1.2Thismastermatrixisintendedasareferenceandguidetothepreparation,revision,anduseofstandardsintheseriesandforplanningandschedulingpurposes.Thisindexistoensuretheaccomplishmentofanobjectiveirrespectiveofthetimerequired,thenumberofASTMcommitteesconcerned,orthecomplexityoftheissuesinvolved.1.3ThismastermatrixstandardprovidesaguidetoASTMstandardsrelatedtotheenergy-criticalareasthataretobedevelopedunderthecategoryofFissionReactorDevelopment,Section10,ofGuideE584-77andasdiscussedinPracticeE583-97.1.4Toaccountforneutronradiationdamageinsettingpressure-temperaturelimitsandmakingfractureanalyses(seeRefs2-7,9-14,21-57,63,69-71,77,78,83-104andRecommendedGuideE509),neutron-inducedchangesinreactorpressurevesselsteelfracturetoughnessmustbepredicted,thencheckedbyextrapolationofsurveillanceprogramdataduringavessel''sservicelife.Uncertaintiesinthepredictingmethodologycanbesignificant.Techniques,variables,anduncertaintiesassociatedwiththephysicalmeasurementsofPVandsupportstructuresteelpropertychangesarenotconsideredinthismastermatrix,butelsewhere(1,3,4,10-13,17,21,22-27,32-39,42,43,45,49-57,71,77,78,83,91-104,andRecommendedGuideE509).Thetechniques,variablesanduncertaintiesrelatedto(1)neutronandgammadosimetry,(2)physics(neutronicsandgammaeffects),and(3)metallurgicaldamagecorrelationproceduresanddataareaddressedinthismastermatrix(2,34).Themainvariablesofconcernto(1),(2),and(3)areasfollows:1.4.1Steelchemicalcompositionandmicrostructure,1.4.2Steelirradiationtemperature,1.4.3Powerplantconfigurationsanddimensions,fromthecoreedgetosurveillancepositionsandintothevesselandcavitywalls,1.4.4Corepowerdistribution,1.4.5Reactoroperatinghistory,1.4.6Reactorphysicscomputations,1.4.7Selectionofneutronexposureunits,1.4.8Dosimetrymeasurements,1.4.9Neutronspectraleffects,and1.4.10Neutrondoserateeffects.1.5Anumberofpotentialmethodsandstandardsexistforensuringtheadequacyoffracturecontrolofreactorpressurevesselbeltlinesundernormalandaccidentloads(1-4,6,7,13,14,21-28,29-34,52-57,71,77,78,91,93,RecommendedGuideE509,and2.3ASMEStandards).AsolderLWRpressurevesselsbecomemorehighlyirradiated,thepredictivecapabilityforchangesintoughnessmustimprove.Sinceduringavessel''sservicelifeanincreasingamountofinformationwillbeavailablefromtestreactorandpowerreactorsurveillanceprograms,betterprocedurestoevaluateandusethisinformationcanandmustbedeveloped(1-4,6,7,9-15,17,21-34,52-57,69,......
【中国标准分类号】:F69
【国际标准分类号】:27_120_10
【页数】:17P.;A4
【正文语种】:
【原文标准名称】:E706(0)轻水反应堆压力容器监视标准的标准主模型
【标准号】:ASTME706-2002
【标准状态】:作废
【国别】:
【发布日期】:2002
【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】:(Guide)
【标准水平】:()
【中文主题词】:核技术;反应釜;核能;模型;轻水反应堆;压力容器;监督(认可)
【英文主题词】:dosimetry;matrixdata/programs;nuclearreactorvessels-light-watercooled;nuclearreactorvessels-surveillance;light-waterreactorpressurevesselsurveillancestandards,master
【摘要】:1.1Thismastermatrixstandarddescribesaseriesofstandardpractices,guides,andmethodsforthepredictionofneutron-inducedchangesinlight-waterreactor(LWR)pressurevessel(PV)andsupportstructuresteelsthroughoutapressurevessel''sservicelife(Fig.1).SomeoftheseareexistingASTMstandards,someareASTMstandardsthathavebeenmodified,andsomeareproposedASTMstandards.GeneralrequirementsofcontentandconsistencyarediscussedinSection6.Moredetailedwriters''andusers''information,justification,andspecificrequirementsfortheninepractices,tenguides,andthreemethodsareprovidedinSections3-5.ReferenceddocumentsarediscussedinSection2.Thesummary-typeinformationthatisprovidedinSections3and4isessentialforestablishingproperunderstandingandcommunicationsbetweenthewritersandusersofthissetofmatrixstandards.Itwasextractedfromthereferenceddocuments,Section2andreferences(1-106)forusebyindividualwritersandusers.1.2Thismastermatrixisintendedasareferenceandguidetothepreparation,revision,anduseofstandardsintheseriesandforplanningandschedulingpurposes.Thisindexistoensuretheaccomplishmentofanobjectiveirrespectiveofthetimerequired,thenumberofASTMcommitteesconcerned,orthecomplexityoftheissuesinvolved.1.3ThismastermatrixstandardprovidesaguidetoASTMstandardsrelatedtotheenergy-criticalareasthataretobedevelopedunderthecategoryofFissionReactorDevelopment,Section10,ofGuideE584-77andasdiscussedinPracticeE583-97.1.4Toaccountforneutronradiationdamageinsettingpressure-temperaturelimitsandmakingfractureanalyses(seeRefs2-7,9-14,21-57,63,69-71,77,78,83-104andRecommendedGuideE509),neutron-inducedchangesinreactorpressurevesselsteelfracturetoughnessmustbepredicted,thencheckedbyextrapolationofsurveillanceprogramdataduringavessel''sservicelife.Uncertaintiesinthepredictingmethodologycanbesignificant.Techniques,variables,anduncertaintiesassociatedwiththephysicalmeasurementsofPVandsupportstructuresteelpropertychangesarenotconsideredinthismastermatrix,butelsewhere(1,3,4,10-13,17,21,22-27,32-39,42,43,45,49-57,71,77,78,83,91-104,andRecommendedGuideE509).Thetechniques,variablesanduncertaintiesrelatedto(1)neutronandgammadosimetry,(2)physics(neutronicsandgammaeffects),and(3)metallurgicaldamagecorrelationproceduresanddataareaddressedinthismastermatrix(2,34).Themainvariablesofconcernto(1),(2),and(3)areasfollows:1.4.1Steelchemicalcompositionandmicrostructure,1.4.2Steelirradiationtemperature,1.4.3Powerplantconfigurationsanddimensions,fromthecoreedgetosurveillancepositionsandintothevesselandcavitywalls,1.4.4Corepowerdistribution,1.4.5Reactoroperatinghistory,1.4.6Reactorphysicscomputations,1.4.7Selectionofneutronexposureunits,1.4.8Dosimetrymeasurements,1.4.9Neutronspectraleffects,and1.4.10Neutrondoserateeffects.1.5Anumberofpotentialmethodsandstandardsexistforensuringtheadequacyoffracturecontrolofreactorpressurevesselbeltlinesundernormalandaccidentloads(1-4,6,7,13,14,21-28,29-34,52-57,71,77,78,91,93,RecommendedGuideE509,and2.3ASMEStandards).AsolderLWRpressurevesselsbecomemorehighlyirradiated,thepredictivecapabilityforchangesintoughnessmustimprove.Sinceduringavessel''sservicelifeanincreasingamountofinformationwillbeavailablefromtestreactorandpowerreactorsurveillanceprograms,betterprocedurestoevaluateandusethisinformationcanandmustbedeveloped(1-4,6,7,9-15,17,21-34,52-57,69,......
【中国标准分类号】:F69
【国际标准分类号】:27_120_10
【页数】:17P.;A4
【正文语种】:
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