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ISO 1482-1983 开槽沉头自攻螺钉(通用头型)

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【英文标准名称】:Slottedcountersunk(flat)headtappingscrews(commonheadstyle)
【原文标准名称】:开槽沉头自攻螺钉(通用头型)
【标准号】:ISO1482-1983
【标准状态】:作废
【国别】:国际
【发布日期】:1983-09
【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/TC2
【标准类型】:()
【标准水平】:()
【中文主题词】:紧固件;埋头螺钉;自攻丝螺钉;有槽螺钉;槽头螺钉;螺钉;尺寸;名称与符号
【英文主题词】:Acceptancespecification;Commonheads;Countersunkfasteners;Countersunkheadscrews;Deliveryconditions;Designations;Dimensions;External-threadfasteners;Fasteners;Materials;Screws(bolts);Self-tappingscrews;Slottedscrews;Slotted-headfasteners;Steels;Threads;Tolerances(measurement)
【摘要】:SpecifiesthecharacteristicsofscrewswiththreadsizesfromST2,2uptoandincludingST9,5;includesspecificationswithreferencetointernationalStandards;givesanexampleforthedesignation.
【中国标准分类号】:J13
【国际标准分类号】:21_060_10
【页数】:3P;A4
【正文语种】:英语


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【英文标准名称】:Connectionsforgeneraluseandfluidpower-PortsandstudendswithISO228-1threadswithelastomericormetal-to-metalsealing-Part2:heavy-duty(Sseries)andlight-duty(Lseries)studendswithelastomericsealing(typeE).
【原文标准名称】:通用和液压传动用连接件.带弹性体或金属对金属密封的ISO228-1螺纹的端口和螺柱端.第2部分:带弹性体密封(E型)的重型(S系列)和轻型(L系列)螺柱端
【标准号】:NFE49-051-2-2008
【标准状态】:现行
【国别】:法国
【发布日期】:2008-09-01
【实施或试行日期】:2008-09-27
【发布单位】:法国标准化协会(FR-AFNOR)
【起草单位】:
【标准类型】:()
【标准水平】:()
【中文主题词】:名称与符号;尺寸;弹性体;液压管路;流体技术;重型;液压传动;轻型;作标记;金属导管;管接头;管连接件;管道配件;塑料;螺纹栓塞;密封环;密封件;规范(验收);螺柱;螺纹孔;测试;螺纹
【英文主题词】:Designations;Dimensions;Elastomers;Fluidcircuits;Fluidtechnology;Heavy-duty;Hydraulicfluidpower;Light-duty;Marking;Metalconduits;Pipeconnections;Pipecouplings;Pipefittings;Plastics;Screwedplugs;Sealingrings;Seals;Specification(approval);Studs;Tappedholes;Testing;Threads
【摘要】:
【中国标准分类号】:J20
【国际标准分类号】:23_100_40
【页数】:18P;A4
【正文语种】:其他


【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