ISO 15407-1-2000 气压传动五气口方向控制阀、规格18mm和26mm第1部分:不带电接头的安装面

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【英文标准名称】:Pneumaticfluidpower-Five-portdirectionalcontrolvalves,sizes18mmand26mm-Part1:Mountinginterfacesurfaceswithoutelectricalconnector
【原文标准名称】:气压传动五气口方向控制阀、规格18mm和26mm第1部分:不带电接头的安装面
【标准号】:ISO15407-1-2000
【标准状态】:现行
【国别】:国际
【发布日期】:2000-03
【实施或试行日期】:
【发布单位】:国际标准化组织(IX-ISO)
【起草单位】:ISO/TC131
【标准类型】:()
【标准水平】:()
【中文主题词】:界面;数字标志;开口;气动控制设备;气动设备;识别方法;安装面;配气阀;控制阀;形状公差;阀门;气动力学;规则;流体技术;试验;连接器;平接触面;作标记;尺寸;连接
【英文主题词】:Connections;Connector;Controlvalves;Dimensions;Distributingvalves;Flatcontactsurfaces;Fluidtechnologies;Formtolerances;Identificationmethod;Interfaces;Marking;Mountingsurface;Numericaldesignations;Openings;Pneumaticcontrolequipment;Pneumaticequipment;Pneumatics;Rules;Testing;Valves
【摘要】:ThispartofISO15407specifiesthefollowingrequirementsforamountinginterfaceforfive-portpneumaticdirectionalcontrolvalves,sizes18mmand26mm,withoutelectricalconnector,foruseatamaximumratedpressureof1,6MPa[16bar]:—dimensionsandtolerancesoftheinterfacefeatures;—portidentification;—identificationoftheresultofcontrol-mechanismactuation.Itisnotapplicabletothefunctionalcharacteristicsofinterfaces.NOTERequirementsformountingfive-portpneumaticdirectionalcontrolvalvesofsizes18mmand26mmwithoptionalelectricalconnectoraregiveninISO15407-2.note:1)1bar=0,1MPa=10Pa;1MPa=1N/mm
【中国标准分类号】:J16
【国际标准分类号】:23_100_50
【页数】:5P.;A4
【正文语种】:英语

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基本信息

标准名称：	键盘式手风琴通用技术条件
中标分类：	轻工、文化与生活用品 >> 文教、体育、娱乐用品 >> 乐器
替代情况：	替代QB 1298-91;被QB/T 1298-2006代替
发布日期：	1900-01-01
实施日期：	1997-07-01
首发日期：	1900-01-01
作废日期：	2007-08-01
出版社：	中国轻工业出版社
出版日期：	1997-07-01
页数：	14页

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所属分类：轻工文化与生活用品文教体育娱乐用品乐器

【英文标准名称】:StandardPracticeforAnalysisandInterpretationofLight-WaterReactorSurveillanceResults,E706(IA)
【原文标准名称】:E706(IA)轻水堆监测结果的分析和说明标准方法
【标准号】:ASTME853-2001(2008)
【标准状态】:现行
【国别】:美国
【发布日期】:2001
【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】:(Practice)
【标准水平】:()
【中文主题词】:
【英文主题词】:damageexposureparameter;dpa;embrittlement;LWR;pressurevessel;reactorsurveillance;surveillancecapsule;Dosimetry;Fracturetesting--nuclearreactors;Neutronflux/fluence;Neutronradiation--nuclearmaterials/applications;Nuclearreactor
【摘要】:Theobjectivesofareactorvesselsurveillanceprogramaretwofold.Thefirstrequirementoftheprogramistomonitorchangesinthefracturetoughnesspropertiesofferriticmaterialsinthereactorvesselbeltlineregionresultingfromexposuretoneutronirradiationandthethermalenvironment.Thesecondrequirementistomakeuseofthedataobtainedfromthesurveillanceprogramtodeterminetheconditionsunderwhichthevesselcanbeoperatedthroughoutitsservicelife.Tosatisfythefirstrequirementof3.1,thetaskstobecarriedoutarestraightforward.Eachoftheirradiationcapsulesthatcomprisethesurveillanceprogrammaybetreatedasaseparateexperiment.Thegoalistodefineandcarrytocompletionadosimetryprogramthatwill,aposteriori,describetheneutronfieldtowhichthematerialstestspecimenswereexposed.Theresultantinformationwillthenbecomepartofadatabaseapplicableinastrictersensetothespecificplantfromwhichthecapsulewasremoved,butalsoinabroadersensetotheindustryasawhole.Tosatisfythesecondrequirementof3.1,thetaskstobecarriedoutaresomewhatcomplex.Theobjectiveistodescribeaccuratelytheneutronfieldtowhichthepressurevesselitselfwillbeexposedoveritsservicelife.Thisdescriptionoftheneutronfieldmustincludespatialgradientswithinthevesselwall.Therefore,heavyemphasismustbeplacedontheuseofneutrontransporttechniquesaswellasonthechoiceofadesignbasisforthecomputations.Sinceagivensurveillancecapsulemeasurement,particularlyoneobtainedearlyinplantlife,isnotnecessarilyrepresentativeoflong-termreactoroperation,asimplenormalizationofneutrontransportcalculationstodosimetrydatafromagivencapsulemaynotbeappropriate(1-67).Theobjectivesandrequirementsofareactorvessel''ssupportstructure''ssurveillanceprogramaremuchlessstringent,andatpresent,arelimitedtophysics-dosimetrymeasurementsthroughex-vesselcavitymonitoringcoupledwiththeuseofavailabletestreactormetallurgicaldatatodeterminetheconditionofanysupportstructuresteelsthatmightbesubjecttoneutroninducedpropertychanges(1,29,44-58,65-70).1.1Thispracticecoversthemethodology,summarizedinAnnexA1,tobeusedintheanalysisandinterpretationofneutronexposuredataobtainedfromLWRpressurevesselsurveillanceprograms;and,basedontheresultsofthatanalysis,establishesaformalismtobeusedtoevaluatepresentandfutureconditionofthepressurevesselanditssupportstructures(1-70).1.2Thispracticerelieson,andtiestogether,theapplicationofseveralsupportingASTMstandardpractices,guides,andmethods(seeMasterMatrixE706)(1,5,13,48,49).Inordertomakethispracticeatleastpartiallyself-contained,amoderateamountofdiscussionisprovidedinareasrelatingtoASTMandotherdocuments.Supportsubjectareasthatarediscussedincludereactorphysicscalculations,dosimeterselectionandanalysis,andexposureunits.Note18212;(Figure1isdeletedinthelatestupdate.TheuserisreferedtoMasterMatrixE706forthelatestfigureofthestandardsinterconnectivity).1.3Thispracticeisrestrictedtodirectapplicationsrelatedtosurveillanceprogramsthatareestablishedinsupportoftheoperation,licensing,andregulationofLWRnuclearpowerplants.Proceduresanddatarelatedtotheanalysis,interpretation,andapplicationoftestreactorresultsareaddressedinPracticeE560,PracticeE1006,GuideE900