ASTM A460-2011 包铜钢丝绳标准规格
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来源:标准资料网
【英文标准名称】:StandardSpecificationforCopper-CladSteelWireStrand
【原文标准名称】:包铜钢丝绳标准规格
【标准号】:ASTMA460-2011
【标准状态】:现行
【国别】:
【发布日期】:2011
【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】:A05.12
【标准类型】:(Specification)
【标准水平】:()
【中文主题词】:
【英文主题词】:coatingsmetallic;coppercladmaterials;steelwirecopperclad;steelwirestrand;Copper-cladmaterials--specifications;Metallic-coatedsteelmaterials--specifications;Steelwire(copperprocessed)--specifications;Steel
【摘要】:1.1Thisspecificationcoverscopper-cladsteelwirestrandcomposedofanumberofroundsteel,copper-cladwires,foruseasguys,messengers,spanwires,andforsimilarpurposeswhereelectricalconductanceisnotarequirement.1.2Thevaluesstatedininch-poundunitsaretoberegardedasstandard.ThevaluesgiveninparenthesesaremathematicalconversionstoSIunitsthatareprovidedforinformationonlyandarenotconsideredstandard.
【中国标准分类号】:
【国际标准分类号】:
【页数】:3P.;A4
【正文语种】:
基本信息
标准名称: | 氯化亚铜 |
中标分类: |
化工 >>
无机化工原料 >>
无机盐 |
替代情况: | 调整为HG/T 2960-1979(1997) |
发布日期: | 1900-01-01 |
实施日期: | 1980-01-01 |
首发日期: | 1900-01-01 |
作废日期: | 1900-01-01 |
出版日期: | 1900-01-01 |
页数: | 5页 |
适用范围
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前言
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目录
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引用标准
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所属分类: 化工 无机化工原料 无机盐
【英文标准名称】:Nuclearreactorinstrumentation-Pressurizedlightwaterreactors(PWR)-Monitoringadequatecoolingwithinthecoreduringcoldshutdown
【原文标准名称】:核反应堆仪表.压力轻水反应堆(PWR).冷停过程中堆芯充分冷却的监测
【标准号】:BSIEC62117-2000
【标准状态】:现行
【国别】:英国
【发布日期】:2000-05-15
【实施或试行日期】:2000-05-15
【发布单位】:英国标准学会(GB-BSI)
【起草单位】:BSI
【标准类型】:()
【标准水平】:()
【中文主题词】:加压水冷反应堆;冷却;核电厂;轻水反应堆;核电站;反应釜;定义;电气工程;规范(验收);安全;反应堆装置;使用条件;仪器装置;核反应堆;校正;验证
【英文主题词】:Calibration;Cooling;Definition;Definitions;Electricalengineering;Instrumentation;Lightwaterreactors;Nuclearpowerplants;Nuclearreactors;Nuclear-electricpowerstations;Operatingconditions;Pressurizedwaterreactors;Reactorinstrumentation;Reactorvessels;Safety;Specification(approval);Verification
【摘要】:ThisInternationalStandardappliestopressurizedwaterreactors(PWRs)withconfigurationssimilartothoseshowninfigures1and2andpresentsrequirementsforthemonitoringofadequatecoolingwithinthecoreduringcoldshutdownoperations.Adequatecorecoolingcanbeachievedonlybyprovidingsufficientcoolantflowtothecoretoremovetheheat.Duringcoldshutdownoperations,corecoolingisprovidedbyforcedcirculationwiththeresidualheatremovalsystem(RHRS).However,incertainshutdownoperationswhenwaterlevelinthereactorpressurevessel(RPV)isreducedformaintenanceoperations,forcedcirculationmaybeinterrupted,andthecoremaybecomeoverheated.ItisimportantthatplantoperatorshavereliableinformationtoconfirmthatthetemperatureandflowofcoolantcirculatedthroughtheRPVisadequatetoremoveheatfromthecore.ThisinformationincludesareliablemeasurementofwaterlevelintheRPVoutletpipingusedforcirculatingtheflowfromthecoretotheRHRS,aswellasmeasurementsoftemperatureandflowofthecoolant.Anunreliablemeasurementofwaterlevelcanresultininterruptionofcoolantflowandoverheatingofthecore,aneventthathasoccurredatseveralPWRs.AnnexA,whichdescribessomeoftheseevents,identifiesconditionswhichshouldbeconsideredinthedesignofcorecoolingmonitoringinstrumentation.GoodinternationalpracticestobeusedwhendesigningneworupgradingexistingPWRcorecoolingmonitorsaresummarizedinthisstandard.RequirementsaregiveninthisstandardforinstrumentationtomonitorcorecoolingforsafeoperationofPWRsduringcoldshutdownoperationswhenthecoolanttemperatureisbelow100℃(212°F).Requirementsforcorecoolingmonitoringduringconditionsbeyondadesignbasisaccident(DBA),whichcouldbeaspecificnationalrequirementorconsideration,arenotcoveredinthisstandard.Thecorecoolingmonitoringinstrumentationforcoldshutdownfunctionswhenthereactorcoolantsystem(RCS)isconfiguredforcoldshutdownmaintenanceorrefuelling.Thecircumstancesunderwhichthesemeasurementsystemsneedtofunctionaredescribedinthisstandard.Descriptionsofdiversemeasuringprinciplesandsuitabledevicesaregiventogetherwithrequirementsforthefollowing:-operationalconditions;-installation;-operatordisplays;-testing,calibrationandmaintenance;-equipmentqualification;-documentation.
【中国标准分类号】:F60
【国际标准分类号】:27_120_20
【页数】:28P;A4
【正文语种】:英语