ASTM E1035-2002 核反应堆容器支承结构的中子辐照量测定标准实施规程
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【英文标准名称】:StandardPracticeforDeterminingNeutronExposuresforNuclearReactorVesselSupportStructures
【原文标准名称】:核反应堆容器支承结构的中子辐照量测定标准实施规程
【标准号】:ASTME1035-2002
【标准状态】:现行
【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(ASTM)
【起草单位】:E10.05
【标准类型】:(Practice)
【标准水平】:()
【中文主题词】:核能;辐射;压力容器
【英文主题词】:neutron;radiation;ferritic;vessel;dosimetric;reactor;pressurized
【摘要】:Predictionofneutronradiationeffectstopressurevesselsteelshaslongbeenapartofthedesignandoperationoflightwaterreactorpowerplants.Boththefederalregulatoryagencies(see2.2)andnationalstandardsgroups(see2.1)havepromulgatedregulationsandstandardstoensuresafeoperationofthesevessels.Recently,ithasbecomeapparentthatthesupportstructuresforpressurizedwaterreactorvesselsmayalsobesubjecttosimilarneutronradiationeffects(1,2,3,4,5).7Theobjectiveofthispracticeistoprovideguidelinesfordeterminingtheneutronradiationexposuresexperiencedbyindividualvesselsupports.Itisknownthathighenergyphotonscanalsoproducedisplacementdamageeffectsthatmaybesimilartothoseproducedbyneutrons.Theseeffectsareknowntobemuchlessatthebeltlineofalightwaterreactorpressurevesselthanthoseinducedbyneutrons.Thesamehasnotbeenprovenforalllocationswithinvesselsupportstructures.Therefore,itmaybeprudenttoapplycoupledneutron-photontransportmethodsandphotoninduceddisplacementcrosssectionstodeterminewhethergamma-induceddpaexceedsthescreeninglevelof3.0x00D7;10-4,usedinthispracticeforneutronexposures.See1.2.1.1Thispracticecoversproceduresformonitoringtheneutronradiationexposuresexperiencedbyferriticmaterialsinnuclearreactorvesselsupportstructureslocatedinthevicinityoftheactivecore.Thispracticeincludesguidelinesfor:1.1.1Selectingappropriatedosimetricsensorsetsandtheirproperinstallationinreactorcavities.1.1.2Makingappropriateneutronicscalculationstopredictneutronradiationexposures.1.2Thispracticeisapplicabletoallpressurizedwaterreactorswhosevesselsupportswillexperiencealifetimeneutronfluence(E>1MeV)thatexceeds1x1017neutrons/cm2or3.0x10-4dpa.(SeeTerminologyE170.)1.3Exposureofvesselsupportstructuresbygammaradiationisnotincludedinthescopeofthispractice,butseethebriefdiscussionofthisissuein3.2.1.4Thisstandarddoesnotpurporttoaddressallofthesafetyconcerns,ifany,associatedwithitsuse.Itistheresponsibilityoftheuserofthisstandardtoestablishappropriatesafetyandhealthpracticesanddeterminetheapplicabilityofregulatorylimitationspriortouse.
【中国标准分类号】:F74
【国际标准分类号】:27_120_20
【页数】:3P.;A4
【正文语种】:
【原文标准名称】:核反应堆容器支承结构的中子辐照量测定标准实施规程
【标准号】:ASTME1035-2002
【标准状态】:现行
【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(ASTM)
【起草单位】:E10.05
【标准类型】:(Practice)
【标准水平】:()
【中文主题词】:核能;辐射;压力容器
【英文主题词】:neutron;radiation;ferritic;vessel;dosimetric;reactor;pressurized
【摘要】:Predictionofneutronradiationeffectstopressurevesselsteelshaslongbeenapartofthedesignandoperationoflightwaterreactorpowerplants.Boththefederalregulatoryagencies(see2.2)andnationalstandardsgroups(see2.1)havepromulgatedregulationsandstandardstoensuresafeoperationofthesevessels.Recently,ithasbecomeapparentthatthesupportstructuresforpressurizedwaterreactorvesselsmayalsobesubjecttosimilarneutronradiationeffects(1,2,3,4,5).7Theobjectiveofthispracticeistoprovideguidelinesfordeterminingtheneutronradiationexposuresexperiencedbyindividualvesselsupports.Itisknownthathighenergyphotonscanalsoproducedisplacementdamageeffectsthatmaybesimilartothoseproducedbyneutrons.Theseeffectsareknowntobemuchlessatthebeltlineofalightwaterreactorpressurevesselthanthoseinducedbyneutrons.Thesamehasnotbeenprovenforalllocationswithinvesselsupportstructures.Therefore,itmaybeprudenttoapplycoupledneutron-photontransportmethodsandphotoninduceddisplacementcrosssectionstodeterminewhethergamma-induceddpaexceedsthescreeninglevelof3.0x00D7;10-4,usedinthispracticeforneutronexposures.See1.2.1.1Thispracticecoversproceduresformonitoringtheneutronradiationexposuresexperiencedbyferriticmaterialsinnuclearreactorvesselsupportstructureslocatedinthevicinityoftheactivecore.Thispracticeincludesguidelinesfor:1.1.1Selectingappropriatedosimetricsensorsetsandtheirproperinstallationinreactorcavities.1.1.2Makingappropriateneutronicscalculationstopredictneutronradiationexposures.1.2Thispracticeisapplicabletoallpressurizedwaterreactorswhosevesselsupportswillexperiencealifetimeneutronfluence(E>1MeV)thatexceeds1x1017neutrons/cm2or3.0x10-4dpa.(SeeTerminologyE170.)1.3Exposureofvesselsupportstructuresbygammaradiationisnotincludedinthescopeofthispractice,butseethebriefdiscussionofthisissuein3.2.1.4Thisstandarddoesnotpurporttoaddressallofthesafetyconcerns,ifany,associatedwithitsuse.Itistheresponsibilityoftheuserofthisstandardtoestablishappropriatesafetyandhealthpracticesanddeterminetheapplicabilityofregulatorylimitationspriortouse.
【中国标准分类号】:F74
【国际标准分类号】:27_120_20
【页数】:3P.;A4
【正文语种】:
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