ASTM E1006-2002 试验反应堆的物理放射量测定结果的分析和解释的标准实施规程,E706(II)
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【英文标准名称】:StandardPracticeforAnalysisandInterpretationofPhysicsDosimetryResultsforTestReactors,E706(II)
【原文标准名称】:试验反应堆的物理放射量测定结果的分析和解释的标准实施规程,E706(II)
【标准号】:ASTME1006-2002
【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】:反应堆;剂量测定;分析;核能
【英文主题词】:discreteordinates;dosimetry;MonteCarlo;neutronexposureparameters;radiationtransport;testreactor
【摘要】:Themechanicalpropertiesofsteelsandothermetalsarealteredbyexposuretoneutronradiation.Thesepropertychangesareassumedtobeafunctionofchemicalcomposition,metallurgicalcondition,temperature,fluence(perhapsalsofluencerate),andneutronspectrum.Theinfluenceofthesevariablesisnotcompletelyunderstood.Thefunctionaldependencybetweenpropertychangesandneutronradiationissummarizedintheformofdamageexposureparametersthatareweightedintegralsovertheneutronfluencespectrum.Theevaluationofneutronradiationeffectsonpressurevesselsteelsandthedeterminationofsafetylimitsrequiretheknowlegeofuncertaintiesinthepredictionofradiationexposureparameters(forexample,dpa(PracticeE693),neutronfluencegreaterthan1.0MeV,neutronfluencegreaterthan0.1MeV,thermalneutronfluence,etc.).Thispracticedescribesrecommendedproceduresanddatafordeterminingtheseexposureparameters(andtheassociateduncertainties)fortestreactorexperiments.Thenuclearindustrydrawsmuchofitsinformationfromdatabasesthatcomefromtestreactorexperiments.Therefore,itisessentialthatreliabledatabasesareobtainedfromtestreactorstoassesssafetyissuesinLightWaterReactor(LWR)nuclearpowerplants.1.1Thispracticecoversthemethodologysummarizedintobeusedintheanalysisandinterpretationofphysics-dosimetryresultsfromtestreactors.1.2Thispracticerelieson,andtiestogether,theapplicationofseveralsupportingASTMstandardpractices,guides,andmethods.1.3Supportsubjectareasthatarediscussedincludereactorphysicscalculations,dosimeterselectionandanalysis,exposureunits,andneutronspectrumadjustmentmethods.1.4Thispracticeisdirectedtowardsthedevelopmentandapplicationofphysics-dosimetry-metallurgicaldataobtainedfromtestreactorirradiationexperimentsthatareperformedinsupportoftheoperation,licensing,andregulationofLWRnuclearpowerplants.Itspecificallyaddressesthephysics-dosimetryaspectsoftheproblem.Proceduresrelatedtotheanalysis,interpretation,andapplicationofbothtestandpowerreactorphysics-dosimetry-metallurgyresultsareaddressedinPracticesE185,E560,E853,andE1035,GuidesE900,E2005E2006andTestMethodE646.1.5Thisstandardmayinvolvehazardousmaterials,operations,andequipment.Thisstandarddoesnotpurporttoaddressallofthesafetyconcerns,ifany,associatedwithitsuse.Itistheresponsibilityoftheuserofthisstandardtoestablishappropriatesafetyandhealthpracticesanddeterminetheapplicabilityofregulatorylimitationspriortouse.
【中国标准分类号】:F70
【国际标准分类号】:17_240
【页数】:6P.;A4
【正文语种】:
【原文标准名称】:试验反应堆的物理放射量测定结果的分析和解释的标准实施规程,E706(II)
【标准号】:ASTME1006-2002
【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】:反应堆;剂量测定;分析;核能
【英文主题词】:discreteordinates;dosimetry;MonteCarlo;neutronexposureparameters;radiationtransport;testreactor
【摘要】:Themechanicalpropertiesofsteelsandothermetalsarealteredbyexposuretoneutronradiation.Thesepropertychangesareassumedtobeafunctionofchemicalcomposition,metallurgicalcondition,temperature,fluence(perhapsalsofluencerate),andneutronspectrum.Theinfluenceofthesevariablesisnotcompletelyunderstood.Thefunctionaldependencybetweenpropertychangesandneutronradiationissummarizedintheformofdamageexposureparametersthatareweightedintegralsovertheneutronfluencespectrum.Theevaluationofneutronradiationeffectsonpressurevesselsteelsandthedeterminationofsafetylimitsrequiretheknowlegeofuncertaintiesinthepredictionofradiationexposureparameters(forexample,dpa(PracticeE693),neutronfluencegreaterthan1.0MeV,neutronfluencegreaterthan0.1MeV,thermalneutronfluence,etc.).Thispracticedescribesrecommendedproceduresanddatafordeterminingtheseexposureparameters(andtheassociateduncertainties)fortestreactorexperiments.Thenuclearindustrydrawsmuchofitsinformationfromdatabasesthatcomefromtestreactorexperiments.Therefore,itisessentialthatreliabledatabasesareobtainedfromtestreactorstoassesssafetyissuesinLightWaterReactor(LWR)nuclearpowerplants.1.1Thispracticecoversthemethodologysummarizedintobeusedintheanalysisandinterpretationofphysics-dosimetryresultsfromtestreactors.1.2Thispracticerelieson,andtiestogether,theapplicationofseveralsupportingASTMstandardpractices,guides,andmethods.1.3Supportsubjectareasthatarediscussedincludereactorphysicscalculations,dosimeterselectionandanalysis,exposureunits,andneutronspectrumadjustmentmethods.1.4Thispracticeisdirectedtowardsthedevelopmentandapplicationofphysics-dosimetry-metallurgicaldataobtainedfromtestreactorirradiationexperimentsthatareperformedinsupportoftheoperation,licensing,andregulationofLWRnuclearpowerplants.Itspecificallyaddressesthephysics-dosimetryaspectsoftheproblem.Proceduresrelatedtotheanalysis,interpretation,andapplicationofbothtestandpowerreactorphysics-dosimetry-metallurgyresultsareaddressedinPracticesE185,E560,E853,andE1035,GuidesE900,E2005E2006andTestMethodE646.1.5Thisstandardmayinvolvehazardousmaterials,operations,andequipment.Thisstandarddoesnotpurporttoaddressallofthesafetyconcerns,ifany,associatedwithitsuse.Itistheresponsibilityoftheuserofthisstandardtoestablishappropriatesafetyandhealthpracticesanddeterminetheapplicabilityofregulatorylimitationspriortouse.
【中国标准分类号】:F70
【国际标准分类号】:17_240
【页数】:6P.;A4
【正文语种】:
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