HG/T 2467.7-1996 农药可溶性浓剂产品标准编写规范

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【英文标准名称】:Protocolforauthenticationinhostattachmentsoftransientstoragedevices
【原文标准名称】:临时存储装置主要附件的校验协议
【标准号】:IEEE1667-2006
【标准状态】:作废
【国别】:美国
【发布日期】:2006
【实施或试行日期】:
【发布单位】:美国电气电子工程师学会(US-IEEE)
【起草单位】:IEEE
【标准类型】:()
【标准水平】:()
【中文主题词】:存储协议;确认;校验;通信系统;传播技术;元部件;定义;电子仪器;主机;识别保证;信息处理;信息技术;IT安全性;存储;个人计算机;协议;无线电话;服务器;小型计算机系统接口;规范(验收);存储器件;临时存储
【英文主题词】:Accessprotocol;Acknowledgements;Authentication;Communicationsystems;Communicationtechnology;Components;Definitions;Electronicinstruments;Hosts;Identificationassurance;Informationprocessing;Informationtechnology;ITsecurity;Memory;PC;Protocols;Radiotelephones;Server;Smallcomputersysteminterface;Specification(approval);Storagemedia;Transientstores
【摘要】:ThisprojectdefinesastandardprotocolforsecureauthenticationandcreationoftrustbetweenasecurehostandadirectlyattachedTransientStorageDevice(TSD),suchasaUSBflashdrive,portableharddrive,orcellularphone.Theprotocolhasonlyanindirectrelationshipwithdataintegrity/security,anddoesnotdirectlyaddressissuesofauthorizationandenforcement.Theprotocolalsodoesnotaddressdevicesthatareattachedusinganetworkconnection.However,adevicethatusesapoint-to-pointwirelessconnectionsuchasWUSBmaycomplywiththisprotocol.
【中国标准分类号】:L64
【国际标准分类号】:35_040;35_220_01
【页数】:49P.;A4
【正文语种】:英语


【英文标准名称】:GraphiteforHighTemperatureGas-CooledNuclearReactors
【原文标准名称】:高温气体冷却核反应堆用石墨
【标准号】:ASMESTP-NU-009-2008
【标准状态】:现行
【国别】:美国
【发布日期】:2008
【实施或试行日期】:
【发布单位】:美国机械工程师协会(US-ASME)
【起草单位】:ASME
【标准类型】:()
【标准水平】:()
【中文主题词】:面积;锅炉;化学性质;中国;冷却;设计;开发;工程设计;气体;发电;等级;石墨;氦;高温;高温反应堆;信息;辐照;日本;适度;中子;核;核反应堆;概述;卵石层;物理性能;压力容器;反应堆工艺学;反应堆;研讨会;起动;试验;痕量元素;培训
【英文主题词】:Area;Boilers;Chemicalproperties;China;Cooling;Design;Developments;Engineeringdesign;Gases;Generation;Grades;Graphite;Helium;Hightemperature;Hightemperaturereactors;Information;Irradiation;Japan;Moderate;Neutrons;Nuclear;Nuclearreactors;Overviews;Pebblebeds;Physicalproperties;Pressurevessels;Reactortechnology;Reactors;Seminar;Start;Testing;Traceelements;Training
【摘要】:Thisdocumentpresentsthebasicinformationrelativetobulkgraphiteproduction,structure,chemicalproperties,physicalpropertiesandneutronirradiationbehavior.Bulkgraphitecharacteristics,itsmanufacture,propertiesandirradiationbehavioraswellasanewgenerationofnucleargradesarebrieflyreviewed.Anoverviewofgraphitemoderatedgas-cooledreactordesignsisalsopresented.ThereportservesasasummaryofthetrainingseminaronNuclearGraphiteconductedduringtheASMEBoilerandPressureVesselCodeweek,October30.November3,2006,inLouisville,KY.Thereisnouniversallyacceptedcodeforthedesignofgraphitemoderatorstructures.Thehistoryofgraphitemoderatedreactorsistracedfromthebeginningsin1942tothemostrecentutilitystart-upin1989.DevelopmentshavecontinuedovertheinterveningyearsespeciallyintheareaofheliumcooledHighTemperatureReactors.Prismatic30MWth,andpebble-bed10MWth,testreactorswerebroughtintooperationinJapanandChina,respectively.
【中国标准分类号】:Q51
【国际标准分类号】:27_120_10
【页数】:40P;A4
【正文语种】:英语