ASTM E636-2010 对核动力反应堆容器进行补充监控试验的标准指南E706(IH)
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【英文标准名称】:StandardGuideforConductingSupplementalSurveillanceTestsforNuclearPowerReactorVessels,E706(IH)
【原文标准名称】:对核动力反应堆容器进行补充监控试验的标准指南E706(IH)
【标准号】:ASTME636-2010
【标准状态】:现行
【国别】:美国
【发布日期】:2010
【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】:E10.02
【标准类型】:(Guide)
【标准水平】:()
【中文主题词】:
【英文主题词】:fracturetoughness;irradiation;notchductility;nuclearreactorvessels;surveillance(ofnuclearreactorvessels);Irradiance/irradiation;Neutronflux/fluence;Nuclearreactorvessels--surveillance;Radiationexposure--nuclearmaterials/applic
【摘要】:PracticesE185andE2215describeaminimumprogramforthesurveillanceofreactorvesselmaterials,specificallymechanicalpropertychangesthatoccurinservice.Thisguidemaybeappliedinordertogenerateadditionalspecificfracturetoughnesspropertyinformationonradiation-inducedpropertychangestobetterassistthedeterminationoftheoptimumreactorvesseloperationschemes.1.1Thisguidediscussestestproceduresthatcanbeusedinconjunctionwith,butnotasalternativesto,thoserequiredbyPracticesE185andE2215forthesurveillanceofnuclearreactorvessels.Thesupplementalmechanicalpropertytestsoutlinedpermittheacquisitionofadditionalinformationonradiation-inducedchangesinfracturetoughness,notchductility,andyieldstrengthpropertiesofthereactorvesselsteels.1.2Thisguideprovidesrecommendationsforthepreparationoftestspecimensforirradiation,andidentifiesspecialprecautionsandrequirementsforreactorsurveillanceoperationsandpostirradiationtestplanning.Guidanceondatareductionandcomputationalproceduresisalsogiven.ReferenceismadetootherASTMtestmethodsforthephysicalconductofspecimentestsandforrawdataacquisition.
【中国标准分类号】:F69
【国际标准分类号】:27_120_10
【页数】:8P.;A4
【正文语种】:英语
【原文标准名称】:对核动力反应堆容器进行补充监控试验的标准指南E706(IH)
【标准号】:ASTME636-2010
【标准状态】:现行
【国别】:美国
【发布日期】:2010
【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】:E10.02
【标准类型】:(Guide)
【标准水平】:()
【中文主题词】:
【英文主题词】:fracturetoughness;irradiation;notchductility;nuclearreactorvessels;surveillance(ofnuclearreactorvessels);Irradiance/irradiation;Neutronflux/fluence;Nuclearreactorvessels--surveillance;Radiationexposure--nuclearmaterials/applic
【摘要】:PracticesE185andE2215describeaminimumprogramforthesurveillanceofreactorvesselmaterials,specificallymechanicalpropertychangesthatoccurinservice.Thisguidemaybeappliedinordertogenerateadditionalspecificfracturetoughnesspropertyinformationonradiation-inducedpropertychangestobetterassistthedeterminationoftheoptimumreactorvesseloperationschemes.1.1Thisguidediscussestestproceduresthatcanbeusedinconjunctionwith,butnotasalternativesto,thoserequiredbyPracticesE185andE2215forthesurveillanceofnuclearreactorvessels.Thesupplementalmechanicalpropertytestsoutlinedpermittheacquisitionofadditionalinformationonradiation-inducedchangesinfracturetoughness,notchductility,andyieldstrengthpropertiesofthereactorvesselsteels.1.2Thisguideprovidesrecommendationsforthepreparationoftestspecimensforirradiation,andidentifiesspecialprecautionsandrequirementsforreactorsurveillanceoperationsandpostirradiationtestplanning.Guidanceondatareductionandcomputationalproceduresisalsogiven.ReferenceismadetootherASTMtestmethodsforthephysicalconductofspecimentestsandforrawdataacquisition.
【中国标准分类号】:F69
【国际标准分类号】:27_120_10
【页数】:8P.;A4
【正文语种】:英语
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