DLT1033.5-2006电力行业词汇第5部分：核能发电.pdf 33页

'ICS01.120F00备案号:19458-2007KIL中华人民共和国电力行业标准DL/T1033.5一2006电力行业词汇第5部分:核能发电ElectricpowerstandardthesaurusPart5:Nuclearpowerplant}a}C}"MAEELo2006-12-17发布2007-05-01实施中华人民共和国国家发展和改革委员会发布 DL/T1033.5一2006目次前言·········································....············....·.··········....·.··········.....·············..···..········.....·.·········...··.··········....··⋯⋯111范围·................................................................................................................................................................12词汇····························································································································································⋯⋯12.1核电厂建设和运行·......................................................................................................................................12.2核电厂设备、材料和系统·.............................................................................................................................32.3核电厂监测、安全和保护·.............................................................................................................................92.4核电厂辐射防护·································································..···········..........................................................112.5核燃料生产、循环和后处理·····························································。·····················································⋯⋯14参考文献...·.···········......···.····.........·.·····............···............····..............·..........................................................⋯⋯16索引·....................................................................................................................................................................17 DL/T1033.5一2006月Ii吕本标准根据《国家发展改革委办公厅关于下达2003年行业标准项目补充计划的通知》(发改办工业[2003]873号)安排制定。本标准分为12部分。第1部分:动力工程第2部分:电力系统第3部分:发电厂、水力发电第4部分:火力发电第5部分:核能发电第6部分:新能源发电第7部分:输电系统第8部分:供电和用电第9部分:电网调度第10部分:电力设备第11部分:事故、保护、安全和可靠性第12部分:电力市场本部分为DUT1033的第5部分，本部分共有544条词汇。本部分中文电力词汇中涉及到本行业中易混淆或与其他行业有歧义的词汇带有含义注释，列在英文之后。若有两个以上相应英文的词汇时，本标准将逐一列在下一行。本标准选用的英文是近年国外习惯用语。本部分词汇在同类别中，中文的电力词汇按汉语拼音排列。中文索引中对于同一词汇在不同章节出现的情况，先列出首次出现位置的章节号，其余在括号内注明。本标准由中国电力企业联合会提出。本部分由电力行业计算机信息技术标准化技术委员会归口管理。本部分由国电信息中心负责解释。本部分主要起草单位:国电信息中心。本部分参加起草单位:国电科技环保集团有限公司、天津市电力公司、黑龙江省电力有限公司、东北电网有限公司、吉林省电力有限公司、江苏省电力公司。本部分主要起草人:刘桂芝、王雨蓬、韩强、齐来喜、吴兴林、周晓林、张水凌、王是、陈德文、乌R丽卿。 DL/T1033.5一2006电力行业词汇第5部分:核能发电1范围本部分规定了电力行业核能发电的名词术语。本部分适用于电力行业工作人员、高等院校师生在对外交流、定货、签订合同、设备验收和学术交流时，使用规范的中、英文名词术语。2词汇2.1核电厂建设和运行2.1.1安全停堆地震Safeshutdownearthquake2.1.2参考电厂设计Referenceplantdesign2.1.3场地选择Siteselection2.1.4单一故障准则Singlefailurecriteria2.1.5地震反应分析Seismicresponseanalysis2.1.6地震反应谱Seismicresponsespectra2.，.7堆芯熔化物Corium2.1.8堆芯寿期Reactorcorelifetime2.1.9多重性和多样性Redundancyanddiversity2.1.10反应堆拆除Reactordismantling2.1.11反应堆毒物排除Reactorpoisonremoval2.1.12反应堆分批装料Reactorbatchloading2.1.13反应堆换料Reactorrefueling2.1.14反应堆启动Reactorstart-up2.1.15反应堆热工设计Reactorthermohydraulicdesign2.1.16反应堆审批Reactorlicensing2.1.17反应堆退役Reactordecommissioning2.1.18反应堆卸料Reactordischarging2.1.19反应堆运行Reactoroperation2.1.20反应堆运行人员Reactoroperator2.1.21反应堆噪声Reactornoise2.1.22反应堆中毒Reactorpoisoning2.1.23反应堆周期Reactorperiod2.1.24反应堆装料Reactorfueling2.1.25核材料管理Nuclearmaterialmanagement2.1.26核电厂防火Fireprotectionofnuclearpowerplant2.1.27核电厂分区管理Zonecontrolofnuclearpowerplant2.1.28核电厂设计Nuclearpowerplantdesign2.1.29核电厂施工Nuclearpowerplantconstruction DL/T1033.5一20062.1.30核电厂退役Nuclearpowerplantdecommissioning2.1.31核电厂运行Nuclearpowerplantoperation2.1.32核电厂运行管理Operationalmanagementofnuclearpowerplant2.1.33核电厂正常启动Normalstart-upofnuclearpowerplant2.1.34核电厂正常停闭Normalshutdownofnuclearpowerplant2.1.35核毒物Nuclearpoison2.1.36核聚变反应堆Fusionreactor2.1.37核燃料管理Nuclearfuelmanagement2.1.38核燃料利用率Nuclearfuelutilization2.1.39核燃料转换Nuclearfuelconversion2.1.40核设备在役检查In-serviceinspectionofnuclearequipment2.1.41换料方案Refuelingscheme2.1.42聚变堆Fusionreactor2.，.43聚变堆材料Fusionreactormaterial建造聚变反应堆需要用到的材料。2.1.44聚变反应Fusionreaction2.1.45聚变反应堆Fusionreactor能持续维持聚变反应，并能利用聚变能和中子的装置。2.1.46聚变增殖堆Fusionbreeder2.1.47建设前期1作Pre-projectandpreconstructionactivity2.1.48降功率运行Underloadedoperation2.1.49紧急停堆Scram2.1.50开堆Reactorstart-up2.1.51空间核电力装置Spacenuclearpowerunit将核能转换成电能，并供给航天器或电推力火箭使用的设备或系统。2.1.52控制棒价值Controlrodworth2.1.53控制棒效率Controlrodeffectiveness2.1.54快速停堆Scram2.1.55裂变毒物Fissionpoison2.1.56裂变一聚变混合堆Fission-fusionhybridreactor裂变与聚变共存，旨在生产易裂变燃料和获取核能的装置。2.1.57配置控制Configurationcontrol2.1.58硼化BoronationBoronizing2.1.59谱漂移控制Spectralshiftcontrol2.1.60燃料致密化Fueldensification2.1.61燃料组件拆卸Fuelassemblydismantling2.1.62热核堆Thermonuclearreactor2.1.63烧干Dryout2.1.64烧毁Burnout2.1.65实体分隔Physicalseparation2.1.66事故停堆Emergencyshutdownofreactor2.1.67逃脱共振几率Resonanceescapeprobability DL/T1033.5一20062.1.68停堆Reactorshutdown2.1.69稀释Dilution2.1.70氛效应Xenonefect2.1.71压力释放(反应堆)Pressurerelease(reactor)2.1.72液态毒物控制Fluidpoisoncontrol2.1.73余热导出After-heatremoval2.1.74运行基准地震Operatingbasisearthquake2.1.75[t}湿Rewetting2.1.76主控制室人因一I一程Maincontrolroomhumanfactorengineering从核电厂的安全性和可靠性出发，使人机功能分配最佳化、人机接口合理化，以充分发挥人机的综合效能。2.1.77转换比Conversionratio2.1.78最终热井Ultimateheatsink2.2核电厂设备、材料和系统2.2.1安全棒Safetyrod2.2.2半速发电机Half-speedgenerator2.2.3半速汽轮机Half-speedsteamturbine2.2.4包壳材料Claddingmaterial2.2.5饱和蒸汽汽轮机Saturatedsteamturbine..2.2.6补偿棒Shimrod2.2.7坏生产堆Plutoniumproductionreactor2.2.8材料jHl率(反应堆)Materialbuckling(reactor)2.2.9常规岛Conventionalisland(CI)2.2.10超热中子堆Epithermalreactor2.2.11池式堆Pooltypereactor2.2.12氮冷堆Nitrogen-cooledreactor2.2.13电厂配套设施Balanceofplant(BOP)2.2.14堆内回路In-pileloop2.2.15堆芯Reactorcore2.2.16堆芯结构材料Corestructuralmaterial2.2.17堆芯收集器Corecatcher2.2.18堆殖区Breedingblanket2.2.19二回路SecondarycircuitSecondarycoolantcircuit用于带出一回路冷却剂热量的二次冷却剂循环系统。2.2.20乏燃料元件Spentfuelelement2.2.21反应堆Reactor以铀或怀作核燃料，实现受控核裂变链式反应的装置。2.2.22反应堆保护装置Reactorprotectiondevice2.2.23反应堆部件Reactorcomponent2.2.24反应堆材料Reactormaterial2.2.25反应堆材料辐照效应Irradiationeffectofreactormaterial2.2.26反应堆除气系统Reactorof-gassystem DL/T1033.5一20062.2.27反应堆堆内构件Reactorinternal2.2.28反应堆堆芯Reactorcore2.2.29反应堆二回路Reactorsecondarycircuit2.2.30反应堆工艺Reactortechnology2.2.31反应堆检测仪表Reactorinstrumentation2.2.32反应堆减速剂Reactormoderator2.2.33反应堆结构Reactorstructure2.2.34反应堆结构材料Reactorstructuralmaterial2.2.35反应堆孔道Reactorchannel2.2.36反应堆控制材料Reactorcontrolmaterial用于制造控制元件和液体中子吸收剂的材料。2.2.37反应堆控制系统Reactorcontrolsystem2.2.38反应堆冷却剂Reactorcoolant2.2.39反应堆冷却剂补给系统Reactorcoolantsupplementarysystem2.2.40反应堆冷却剂材料Reactorcoolantmaterial2.2.41反应堆冷却剂系统Reactorcoolantsystem2.2.42反应堆冷却系统Reactorcoolingsystem2.2.43反应堆慢化剂Reactormoderator2.2.44反应堆慢化剂材料Reactormoderatormaterial2.2.45反应堆模拟器Reactorsimulator2.2.46反应堆内部部件Reactorinternal2.2.47反应堆屏蔽Reactorshielding2.2.48反应堆屏蔽材料Reactorshieldingmaterial屏蔽反应堆的核辐射，保护工作人员和设备免受辐射损伤所用的材料。2.2.49反应堆燃料Reactorfuel2.2.50反应堆燃料元件Reactorfuelelement2.2.51反应堆栅格Reactorlattice2.2.52反应堆栅元Reactorcell2.2.53反应堆实验装置Reactorexperimentalfacility2.2.54反应堆压力容器Reactorpressurevessel(RPV)2.2.55反应堆压力容器材料Materialsforreactorpressurevessel2.2.56反应堆压缩机Reactorcompressor2.2.57反应堆一回路Reactorprimarycircuit2.2.58反应堆载热剂Reactorcoolant2.2.59反应堆振荡器Reactoroscillator2.2.60反应堆主管道材料Reactorcoolantpipingmaterial2.2.61反应堆装料Reactorfueling2.2.62反应性引入Reactivityinsertion2.2.63沸水堆Boilingwaterreactor(BWR)2.2.64沸水堆压力容器BWRpressurevessel2.2.65辐照过的核燃料元件IrradiatednuclearfuelelementSpentfuelelement2.2.66辐照孑!道Irradiationchannel DL/T1033.5一20062.2.67改进型气冷堆Advancedgas-cooledreactor(AGR)2.2.68高浓缩铀(80%一100%)Highlyenricheduranium2.2.69高温气冷堆High-temperaturegas-cooledreactor(HTGR)2.2.70供热堆Processheatreactor2.2.71汞冷堆Mercurycooledreactor2.2.72海水淡化Seawaterdesalination2.2.73核岛Nuclearisland(NI)2.2.74核电厂安全级电气设备Safetyrelatedelectricalequipmentfornuclearpowerplant用于反应堆紧急停堆、安全壳隔离和堆芯应急冷却等安全系统的电气设备。2.2.75核电厂厂用电系统Housepowersupplyofnuclearpowerplant核电厂运行和反应堆关停或事故情况下所需的电源系统。2.2.76核电厂汽轮发电机Turbogeneratorfornuclearpowerplant有全速和半速两种，也就是两极和四极两种。对于压水堆核电厂，因具有蒸汽参数较低和流量较大的特点，常用半速或四极发电机。2.2.77核反应Nuclearreaction2.2.78核供汽系统Nuclearsteamsupplysystem(NSSS)2.2.79核汽轮机Nuclearsteamturbine通常指用于压水堆、沸水堆、重水堆和石墨水冷堆核电厂的饱和蒸汽汽轮机。2.2.80核燃料Nuclearfuel2.2.81核燃料元件Nuclearfuelelement2.2.82核石墨Nucleargraphite2.2.83核碎片Nuclearfragment2.2.84核蒸汽供应系统Nuclearsteamsupplysystem(NSSS)2.2.85化学和容积控制系统Chemicalandvolumecontrolsystem2.2.86环状燃料元件Annularfuelelement2.2.87钾冷堆Potassiumcooledreactor2.2.88紧急停堆棒Scramrod2.2.89空气冷却堆Air-cooledreactor2.2.90空心燃料棒Hollowfuelrod2.2.91控制棒Controlrod2.2.92控制棒驱动装置Controlroddrive2.2.93快堆Fastreactor2.2.94快中子堆Fastneutronreactor2.2.95快中子增殖堆Fastbreederreactor(FBR)2.2.96冷却剂净化系统Coolantcleanupsystem2.2.97膜态沸腾Filmboiling2.2.98钠泵Sodiumpump2.2.99钠回路Sodiumloop2.2.100钠冷堆Sodium-cooledreactor2.2.101钠冷快中子增殖堆Sodium-cooledfastbreederreactor2.2.102钠冷石墨慢化堆Sodium-cooledgraphicmoderatedreactor(SGR)2.2.103培训堆Trainingreactor2.2.104硼回收系统Boronrecyclesystem DL/T1033.5一20062.2.105被慢化剂Berylliummoderator2.2.106贫化铀Depleteduranium2.2.107气冷堆Gas-cooledreactor2.2.108气冷快堆Gas-cooledfastreactor(GCFR)2.2.109气体冷却剂Gascoolant2.2.110汽水分离再热器Moistureseparator-reheater核汽轮机高低缸之间用来将蒸汽除湿和加热的装置。2.2.111氢化物慢化剂Hydridemoderator2.2.112氢冷堆Hydrogen-cooledreactor2.2.113氢氧化物慢化剂Hydroxidemoderator2.2.114轻水冷却剂Lightwatercoolant2.2.115轻水慢化剂Lightwatermoderator2.2.116燃料板FuelplateFuelslab2.2.117燃料棒Fuelrod2.2.118燃料棒包壳材料Fuelrodcladdingmaterial2.2.119燃料棒束Fuelbundle2.2.120燃料包覆层Fuel-cladding2.2.121燃料包壳Fuelcan2.2.122燃料包套Fueljacket2.2.123燃料管道Fuelchannel2.2.124燃料浆液Fuelslurry2.2.125燃料颗粒Fuelparticle2.2.126燃料孔道Fuelchannel2.2.127燃料块Fuelslug2.2.128燃料片Fuelsheet2.2.129燃料球Fuelsphere2.2.130燃料扫描Fuelscanning2.2.131燃料外壳Fuelsheath2.2.132燃料细棒Fuelpin2.2.133燃料悬浮液Fuelsuspension2.2.134燃料元件Fuelelement2.2.135燃料元件稳流套Shroud2.2.136燃料装卸搬运系统Fuelhandlingsystem2.2.137燃料组件Fuelassembly2.2.138燃料组件结构材料Structuralmaterialoffuelassembly2.2.139热传输介质Heattransportmedium2.2.140热传输介质净化系统Heattransportmediumpurificationsystem为保持重水堆热传输系统中重水的纯度，除去其所含有害杂质的系统。2.2.141热传输介质压力和装置控制系统Heattransportpressureandinventorysystem为热传输系统提供介质压力和装置控制的主要辅助系统。2.2.142热堆Thermalreactor2.2.143热管道Hotchannel DI,/T1033.5一20062.2.144热离子燃料元件Thermionicfuelelement2.2.145热中子堆Thermalneutronreactor2.2.146热柱Thermalcolumn2.2.147熔盐冷却剂Moltensaltcoolant2.2.148稍浓缩铀(0.7%-5%)Slightlyenricheduranium2.2.149生产堆Productionreactor2.2.150石墨慢化堆Graphitemoderatedreactor2.2.151石墨气冷堆Gas-cooledgraphite-moderatedreactor2.2.152石墨水冷堆Graphite-moderatedwater-cooledreactor2.2.153实验堆Experimentalreactor2.2.154实验孔道Experimentalchannel2.2.155事故棒Emergencyrod2.2.156试验堆Testreactor2.2.157束孔Beamhole2.2.158双循环冷却系统Dualcyclecoolingsystem2.2.159水冷堆Water-cooledreactor2.2.160水慢化堆Water-moderatedreactor2.2.161四极汽轮发电机Four-polesteamturbinegenerator2.2.162天然铀Naturaluranium2.2.163调节棒Regulatingrod2.2.164稳压器(核)Pressurizer2.2.165稳压容器Pressurizer2.2.166先进沸水堆AdvancedBWR(ABWR)采用内置泵和堆内循环等技术改进的沸水堆。2.2.167先进轻水堆Advancedlightwaterreactor先进压水堆和先进沸水堆的统称。2.2.168先进压水堆AdvancedPWR(APWR)采用非能动安全系统等技术改进的压水堆，如美国的AP600型。2.2.169芯(反应堆)Core(reactor)2.2.170新燃料储存架Newfuelassemblystoragerack2.2.171压水堆Pressurizedwaterreactor(PWR)2.2.172压水堆本体PWRvesselanditsinternal2.2.173压水堆堆内构件PWRinternal压水堆压力容器内除燃料组件及其相关组件以外的所有其他构件。2.2.174压水堆可燃毒物组件BurnablepoisonassemblyforPWR用于减小初始堆芯剩余反应性，减少冷却剂的硼浓度，保证反应堆具有负的慢化剂温度系数。2.2.175压水堆控制棒驱动机构ControlroddrivemechanismforPWR使压水堆的控制棒上下运动或保持在某一高度的机构。2.2.176压水堆控制棒组件ControlrodassemblyforPWR用于反应堆启动、停堆和调整功率，以补偿反应堆反应性快速变化的控制部件。2.2.177压水堆燃料组件PWRfuelassembly压水堆内以热能形式释放核能的部件，由燃料棒、定位格架和骨架组成。2.2.178压水堆压力容器PWRpressurevessel DL/T1033.5一2006包容堆芯核燃料、控制部件、堆内构件和反应堆冷却剂的钢制承压容器。2.2.179压水堆一次冷却剂泵PWRprimarycoolantpump2.2.180压水堆蒸汽发生器传热管材料HeattransfertubematerialofPWRsteamgenerator2.2.181压水堆中子源组件NeutronsourceassemblyforPWR用于提高反应堆启动时的中子注量率水平，以保证反应堆安全启动。2.2.182研究堆Researchreactor2.2.183研究与试验堆Researchandtestreactor2.2.184液态金属冷却堆Liquidmetalcooledreactor2.2.185液态金属冷却剂Liquidmetalcoolant2.2.186液态金属冷却快中子增殖堆Liquidmetalcooledfastbreederreactor(LMFBR)2.2.187一次冷却剂系统Primarycoolantsystem2.2.188一回路Primarycircuit使反应堆冷却剂在规定压力和温度条件下进行循环的系统。2.2.189一回路卸压设备Primarycircuitpressurereliefequipment2.2.190一体化冷却系统Integratedcoolingsystem2.2.191有机冷却剂Organiccoolant2.2.192有机慢化剂Organicmoderator2.2.193余热排出系统Residualheatremovalsystem2.2.194再生区Blanket(breeding)2.2.195增压比Superchargingpressureratio2.2.196增殖区Breedingblanket2.2.197蒸汽发生器Steamgenerator压水堆核电厂中将反应堆冷却剂热量传给二次冷却剂产生蒸汽的设备。2.2.198蒸汽和动力转换系统Steamandpowerconversionsystem2.2.199直接循环冷却系统Directcyclecoolingsystem2.2.200中浓缩铀(5%-80%)Moderatelyenricheduranium2.2.201中子反射层Neutronreflector2.2.202重水Heavywater2.2.203重水堆Heavywaterreactor(HWR)2.2.204重水堆氖化和除氖系统DeuterationanddedeuterationsystemofHWR在新树脂氖化床中重水取代轻水和在废树脂除氖床中轻水取代重水的系统。2.2.205重水堆慢化剂覆盖气体系统ModeratorcovergassystemofHWR2.2.206重水堆慢化剂系统ModeratorsystemofHWR2.2.207重水堆燃料通道组件FuelassemblyandfuelchannelassemblyforHWR2.2.208重水堆燃料装卸系统RefuelingsystemofHAIR2.2.209重水堆热传输系统HeattransportsystemofHWR2.2.210重水堆停堆冷却系统ShutdowncoolingsystemofHWR2.2.211重水堆装卸料机RefuelingmachineofHWR2.2.212重水冷却堆Heavywatercooledreactor2.2.213重水冷却剂Heavywatercoolant2.2.214重水慢化堆Heavywatermoderatedreactor2.2.215重水慢化剂Heavywatermoderator2.2.216装料机Fuelingmachine DL/T1033.5一2006Chargingmachine2.3核电厂监测、安全和保护2.3.1安全密封Securityseal2.3.2安全壳(反应堆)Containment(reactor)2.3.3安全壳隔离系统Containmentisolationsystem2.3.4安全壳喷淋系统Containmentspraysystem2.3.5安全壳壳体(反应堆)Containmentshell(reactor)2.3.6安全壳氢复合系统Containmenthydrogenrecombinationsystem2.3.7安全壳通风净化系统Containmentventilationandpurgesystem2.3.8安全壳系统Containmentsystem2.3.9安全壳消氢系统Containmenthydrogenrecombinationsystem控制安全壳内的大气中氢浓度不超过形成爆炸混合物限值的系统。2.3.10安全锁Securitylock2.3.11安全注射系统Safetyinjectionsystem压水堆一回路发生事故后迅速向堆芯注射含硼水的系统。2.3.12保险装置Safetydevice2.3.13表面放射性沾污监测Surfaceradioactivecontaminationmonitoring2.3.14迟发辐射效应Delayedradiationeffect2.3.15磁韧致辐射Magneticbremsstrahlung2.3.16低压冷却剂注入系统Lowpressurecoolantinjectionsystem2.3.17电子探测Electrondetection2.3.18堆内温度测量In-coretemperaturemeasurement2.3.19堆芯保护系统Coreprotectionsystem2.3.20堆芯测量系统In-coremeasurementsystem主要指温度和中子注量率测量。2.3.21堆芯紧急冷却系统Emergencycorecoolingsystem(ECCS)2.3.22堆芯喷淋系统Corespraysystem2.3.23堆芯燃料管理In-corefuelmanagement2.3.24堆芯限制器Reactorcorerestraint2.3.25堆芯淹没系统Corefloodingsystem2.3.26堆芯再淹没系统Corerefloodingsystem2.3.27堆芯中子注量率测量In-coreneutronfluxmeasurement为提高反应堆功率密度和燃料元件燃耗深度，必须测量的称为中子注量率的中子数密度与中子速度的乘积。2.3.28乏燃料储存Spentfuelstorage2.3.29反应堆安全Reactorsafety2.3.30反应堆安全保险装置Reactorsafetyfuse2.3.31反应堆保护参数Reactorprotectionparameter2.3.32反应堆保护系统Reactorprotectionsystem2.3.33反应堆保护装置Reactorprotectiondevice2.3.34反应堆报警系统Reactoralarmsystem2.3.35反应堆第二停堆系统Secondreactortripsystem2.3.36反应堆数字化保护系统Digitalreactorprotectionsystem DL/T1033.5一2006基于微处理机技术的反应堆保护装置。2.3.37反应堆停堆系统Reactortripsystem2.3.38反应堆压力容器水位测量WaterlevelmeasurementofRPV2.3.39反应堆仪表监测系统Reactorinstrumentationmonitoringsystem2.3.40防护衣具Protectiveclothing2.3.41放射化学实验室Radiochemicallaboratorie2.3.42放射效应Radiationeffect2.3.43放射性沉降粒子Falloutparticulate2.3.44放射性沉降物Radioactivefallout2.3.45放射性废物Radioactivewaste2.3.46放射性污染规章Radioactivecontaminationregulation2.3.47放射性药物Radiopharmaceutical2.3.48沸水堆应急堆芯冷却系统EmergencycorecoolingsystemofBWR用于在堆芯失水时直接向堆内注入冷却水，以防止堆芯熔化的安全保护系统。2.3.49辐射环境监测Environmentalradiationmonitoring2.3.50辐射监测Radiationmonitoring2.3.51辐射监测器Radiationmonitor2.3.52辐射探测Radiationdetection2.3.53辐照过的核燃料储存Irradiatednuclearfuelstorage2.3.54辐照盒Irradiationcapsule2.3.55辐照用具Irradiationrig2.3.56辅助给水系统Auxiliaryfeedwatersystem2.3.57高压冷却剂注入系统High-pressurecoolantinjectionsystem2.3.58核安全保障Nuclearsafeguard2.3.59核安全保障规章Nuclearsafeguardregulation2.3.60核保险Nuclearinsurance2.3.61核电厂流出物监测Monitoringofeffluentfromnuclearpowerplant2.3.62核电厂一回路监测系统MonitoringsystemofprimarycircuitofNPP2.3.63核功率测量Nuclearpowermeasurement2.3.64核物料Nuclearmaterial2.3.65缓发辐射效应Delayedradiationeffect2.3.66检测(放射性)Surveillance(radioactivity)2.3.67空间分布Spacedistribution2.3.68孔栏(聚变堆)Diaphragm(fusionreactor)2.3.69控制棒位置指示Detectionofcontrolrodposition2.3.70裂变产物Fissionproduct2.3.71裂变碎片Fissionfragment2.3.72慢性辐射效应Chronicradiationeffect2.3.73内衬Liner2.3.74能量范围Energyrange2.3.75偏滤器Divertor2.3.76屏蔽容器Cask2.3.77破裂Rupture DL/T1033.5一20062.3.78破损Failure2.3.79破损方式分析Failuremodeanalysis2.3.80取样器Sampler2.3.81群常数Groupconstant2.3.82热实验室Hotlab2.3.83热室Hotcell2.3.84热室机械手Hotcellmanipulator2.3.85烧毁装置Burnoutdevice2.3.86剩余Sjj率Residualpower2.3.87束流Beamcurrent2.3.88同步辐射Synchronousradiation2.3.89物料操作Materialhandling2.3.90物料平衡Materialbalance2.3.91物料平衡区(核燃料加工)Materialbalancearea2.3.92压水堆应急堆芯冷却系统EmergencycorecoolingsystemofPWR2.3.93应急给水系统Emergencyfeedwatersystem2.3.94远距离操作Remotehandling2.3.95远距离操作设备Remotehandlingequipment2.3.96远距离观测设备Remoteviewingequipment2.3.97噪声诊断系统Noisediagnosissystem2.3.98增殖芯块Breedingpellet2.3.99真空系统Vacuumsystem2.3.100重水堆安全系统SafetysystemofHWR为缓解严重事故后果而专门设置的工艺系统。2.3.101重要厂用水系统Essentialservicewatersystem2.3.102抓取装置Grab2.3.103专设安全设施EngineeredsafetyfeatureofNPP为限制反应堆事故后果而专门设置的各种安全系统。2.3.104专设安全设施驱动系统Engineeredsafetyfacilityactuationsystem2.4核电厂辐射防护2.4.1标准人Standardman2.4.2表面放射性沾污Surfaceradioactivecontamination2.4.3部分身体辐照Partialbodyirradiation2.4.4材料辐照效应Materialradiationeffect2.4.5参考人Referenceman2.4.6长期辐照Long-termirradiation2.4.7超致死辐照Supralethalirradiation2.4.8超致死剂量Supralethaldose2.4.9等剂量曲线Isodosecurve2.4.10放射生态学Radioecology2.4.11放射损伤Radiationinjury2.4.12放射性核素代谢Radionuclidemetabolism2.4.13放射性核素动力学Radionuclidekinetic DL/T1033.5一20062.4.14放射性核素分布Radionuclidedistribution2.4.15放射性核素更新Radionuclideturnover2.4.16放射性核素环境转移Radionuclidetransferinenvironment2.4.17放射性核素排出Radionuclideelimination2.4.18放射性核素体内转移Radionuclidetransferinorganism2.4.19放射性核素吸收Radionuclideabsorption2.4.20放射性核素在人体内的代谢Radionuclidemetabolismwithinhumanbody2.4.21放射性核素滞留Radionuclideretention2.4.22放射性监护Radioactivitysurveillance2.4.23放射性排放标准Radioactivitylimitsofrelease2.4.24放射性去污Radioactivitydecontamination2.4.25放射性去污剂Radioactivitydecontaminationagent2.4.26放射性去污装置Radioactivitydecontaminationfacility2.4.27放射性同位素动力学Radioisotopekinetic2.4.28放射性污染RadioactivecontaminationRadioactivepollution2.4.29辐射屏蔽Radiationshielding2.4.30辐射生物效应Biologicaleffectofradiation2.4.31辐射损害(非生物)Radiationdamage(nonbiologic)2.4.32辐射损伤Radiationinjury2.4.33辐射危害Radiationhazard2.4.34辐射效应Radiationeffect2.4.35辐射遗传效应Geneticradiationeffect2.4.36辐射影响Radiationimpact2.4.37辐照Irradiation2.4.38个人剂量监测Personaldosemonitoring2.4.39辐射防护基本原则Basicprinciplesofradiationprotection2.4.40辐射防护技术Radiationprotectiontechnique2.4.41辐射防护评价Radiationprotectionassessment2.4.42辐射防护指南Radiationprotectionguide2.4.43辐射活化Radioactivation2.4.44辐射剂量Radiationdose2.4.45辐射剂量标准Radiationdosestandard2.4.46辐射剂量单位Radiationdoseunit2.4.47辐射剂量分布Radiationdosedistribution2.4.48固体废物处理系统Solidwasteprocessingsystem2.4.49核安全保障Nuclearsafeguard2.4.50核电厂源项Sourcetermfromnuclearpowerplant2.4.51核辐射安全Radiationsafety2.4.52化学辐射效应Chemicalradiationeffect2.4.53环境影响评价Environmentalimpactassessment2.4.54积分剂量Integraldose2.4.55剂量当量Doseequivalent DL/T1033.5一20062.4.56剂量负担Dosecommitment2.4.57齐1量率Doserate2.4.58剂量效应关系Dose-responserelationship2.4.59建议书(辐射防护)Recommendations(radiationprotection)2.4.60局部辐射效应Localradiationeffect2.4.61空间剂量分布Spatialdosedistribution2.4.62控制区Controlledareas2.4.63累积照射指标Cumulativeexposureindex2.4.64离体辐照Extracorporealirradiation2.4.65连续辐照Continuousirradiation2.4.66裂变产物释放Fissionproductrelease2.4.67裂变碎片探测Fissionfragmentdetection2.4.68慢性辐照Chronicirradiation2.4.69内辐照Internalirradiation2.4.70内污染Internalcontamination2.4.71屏蔽层Shields(reactor)2.4.72破损包壳探测Burstcandetection2.4.73破损燃料块探测Burstslugdetection2.4.74破损元件探测Failedelementdetection2.4.75躯体辐射剂量Bodyeffectdose2.4.76全身辐照Whole-bodyirradiation2.4.77热屏蔽层Thermalshield2.4.78人的辐射效应Radiationeffectonman2.4.79射线照射量Radiationexposure2.4.80深部剂量Depthdose2.4.81深部剂量分布Depthdosedistribution2.4.82生物半减期Biologicalhalf-life2.4.83生物辐射效应Biologicalradiationeffect2.4.84生物屏蔽Biologicalshielding2.4.85生物屏蔽层Biologicalshield2.4.86时间剂量分布Temporaldosedistribution2.4.87事故性辐照Accidentalirradiation2.4.88瞬时剂量分布Temporaldosedistribution2.4.89体外辐照Extracorporealirradiation2.4.90外辐照Externalirradiation2.4.91吸收份额Absorbedfraction2.4.92吸收剂量Absorbeddose2.4.93吸收剂量分布Absorbeddosedistribution2.4.94小剂量辐照Lowdoseirradiation2.4.95仪表辐射效应Instrumentradiationeffect2.4.96仪表抗辐照Instrumentantiradiation2.4.97仪表失效效应Instrumentdeficienteffect2.4.98有效半减期Effectivehalf-life DL/T1033.5一20062.4.99有效遗传剂量Geneticallysignificantdose2.4.100闽剂量Thresholddose2.4.101远隔辐射效应Abscopalradiationeffect2.4.102远期辐射效应Lateradiationeffect2.4.103早期辐射效应Earlyradiationeffect2.4.104质子探测Protondetection2.4.105致死辐射剂量Lethalradiationdose2.4.106致死辐照Lethalirradiation2.4.107滞留Retention2.4.108中子探测Neutrondetection2.5核燃料生产、循环和后处理2.5.1地下处置Undergrounddisposal2.5.2乏燃料Spentfuel2.5.3乏燃料储存Spentfuelstorage2.5.4乏燃料储存池SpentfuelstoragepitSpentfuelstoragepool2.5.5乏燃料储存池冷却和净化系统Spentfuelstoragepitcoolingandcleanupsystem2.5.6乏燃料处置Spentfueldisposal对反应堆中使用后卸出的核燃料实施一种不可回取的处理。2.5.7乏燃料元件Spentfuelelement2.5.8乏燃料运输Spentfueltransport2.5.9放射分析法Radiometricanalysis2.5.10放射化学分析Radiochemicalanalysis2.5.11放射性废水Radioactivewastewater2.5.12放射性废物处理Radioactivewasteprocessing2.5.13放射性废物设施Radioactivewastefacility2.5.14放射性废物贮存Radioactivewastestorage2.5.15放射性废渣Radioactivewasteresidue2.5.16辐射吸收分析Radiationabsorptionanalysis2.5.17辐照I厂Irradiationplant2.5.18核燃料后处理Nuclearfuelreprocessing2.5.19核燃料后处理厂Nuclearfuelreprocessingplant2.5.20核燃料制造厂Nuclearfuelfabricationplant2.5.21核设施Nuclearfacility2.5.22黄饼Yellowcake2.5.23混合氧化物燃料厂Mixedoxidefuelfabricationplant2.5.24加速器Accelerator2.5.25加速器设备Acceleratorfacility2.5.26加速器增殖堆Acceleratorbreeder2.5.27可燃毒物BurnablepoisonBurnoutpoison2.5.28粒子加速器Particleaccelerator2.5.29平衡燃料循环Equilibriumfuelcycle DL/T1033.5一20062.5.30燃料循环Fuelcycle2.5.31燃料元件制造Fuelelementfabrication2.5.32燃料再循环Fuelrecycle2.5.33燃料组件辐照性能Irradiationperformanceoffuelassembly2.5.34燃料组件制造Fuelassemblyfabrication2.5.35I司位素分离I厂Isotopeseparationplant2.5.36铀一怀循环Uranium-plutoniumcycle2.5.37铀浓缩物Uraniumconcentrate2.5.38重水厂Heavywaterplant DL/T1033.5一2006参考文献1.中国电力信息中心.电力主题词表.北京:中国电力出版社，20022.《中国电力百科全书》编辑委员会，中国电力出版社《中国电力百科全书》编辑部编.中国电力百科全书.北京:中国电力出版社，20013.中国科学技术情报研究所《汉语主题词表》自然科学部分维护组编.汉语主题词表.北京:科学技术文献出版社，1991 DL/T1033.5一2006索引A安全棒Safetyrod2.2.1安全壳(反应堆)Containment(reactor)2.3.2安全壳隔离系统Containmentisolationsystem2.3.3安全壳壳体(反应堆)Containmentshells(reactor)2.3.5安全壳喷淋系统Containmentspraysystem2.3.4安全壳氢复合系统Containmenthydrogenrecombinationsystem2.3.6安全壳通风净化系统Containmentventilationandpurgesystem2.3.7安全壳系统Containmentsystem2.3.8安全壳消氢系统Containmenthydrogenrecombinationsystem2.3.9安全密封Securityseal2.3.1安全锁Securitylock2.3.10安全停堆地震Safeshutdownearthquake2.1.1安全注射系统Safetyinjectionsystem2.3.11B半速发电机Half-speedgenerator2.2.2半速汽轮机Half-speedsteamturbine2.2.3包壳材料Claddingmaterial2.2.4饱和蒸汽汽轮机Saturatedsteamturbine2.2.5保险装置Safetydevice2.3.12标准人Standardman2.4.1表面放射性沾污Surfaceradioactivecontamination2.4.2表面放射性沾污监测Surfaceradioactivecontaminationmonitoring2.3.13补偿棒Shimrod2.2.6怀生产堆Plutoniumproductionreactor2.2.7部分身体辐照Partialbodyirradiation2.4.3C材料辐照效应Materialradiationeffect2.4.4材料曲率(反应堆)Materialbuckling(reactor)2.2.8参考电厂设计Referenceplantdesign2.1.2参考人Referenceman2.4.5长期辐照Long-termirradiation2.4.6常规岛Conventionalisland(CI)2.2.9场地选择Siteselection2.1.3超热中子堆Epithermalreactor2.2.10超致死辐照Supralethalirradiation2.4.7超致死剂量Supralethaldose2.4.8池式堆Pooltypereactor2.2.11迟发辐射效应Delayedradiationeffect2.3.14磁韧致辐射Magneticbremsstrahlung2.3.15 DL/T1033.5一2006D单一故障准则Singlefailurecriteria2.1.4氮冷堆Nitrogen-cooledreactor2.2.12等剂量曲线Isodosecurve2.4.9低压冷却剂注入系统Lowpressurecoolantinjectionsystem2.3.16地下处置Undergrounddisposal2.5.1地震反应分析Seismicresponseanalysis2.1.5地震反应谱Seismicresponsespectra2.1.6电厂配套设施Balanceofplant,BOP2.2.13电子探测Electrondetection2.3.17调节棒Regulatingrod2.2.163堆内回路In-pileloop2.2.14堆内温度测量In-coretemperaturemeasurement2.3.18堆芯Reactorcore2.2.15堆芯保护系统Coreprotectionsystem2.3.19堆芯测量系统In-coremeasurementsystem2.3.20堆芯结构材料Corestructuralmaterial2.2.16堆芯紧急冷却系统Emergencycorecoolingsystem(ECCS)2.3.21堆芯喷淋系统Corespraysystem2.3.22堆芯燃料管理In-corefuelmanagement2.3.23堆芯熔化物Corium2.1.7堆芯收集器Corecatcher2.2.17堆芯寿期Reactorcorelifetime2.1.8堆芯限制器Reactorcorerestraint2.3.24堆芯淹没系统Corefloodingsystem2.3.25堆芯再淹没系统Corerefloodingsystem2.3.26堆芯中子注量率测量In-coreneutronfluxmeasurement2.3.27堆殖区Breedingblanket2.2.18多重性和多样性Redundancyanddiversity2.1.9E二回路Secondarycircuit,Secondarycoolantcircuit2.2.19F乏燃料Spentfuel2.5.2乏燃料储存Spentfuelstorage2.3.28(2.5.3)乏燃料储存池Spentfuelstoragepit,Spentfuelstoragepool2.5.4乏燃料储存池冷却和净化系统Spentfuelstoragepitcoolingandcleanupsystem2.5.5乏燃料处置Spentfueldisposal2.5.6乏燃料元件Spentfuelelement2.2.20(2.5.7)乏燃料运输Spentfueltransport2.5.8反应堆reactor2.2.21反应堆安全Reactorsafety2.3.29反应堆安全保险装置Reactorsafetyfuse2.3.30反应堆保护参数Reactorprotectionparameter2.3.31 DL/T1033.5一2006反应堆保护系统Reactorprotectionsystem2.3.32反应堆保护装置Reactorprotectiondevice2.2.22(2.3.33)反应堆报警系统Reactoralarmsystem2.3.34反应堆部件Reactorcomponent2.2.23反应堆材料Reactormaterial2.2.24反应堆材料辐照效应Irradiationeffectofreactormaterial2.2.25反应堆拆除Reactordismantling2.1.10反应堆除气系统Reactorof-gassystem2.2.26反应堆第二停堆系统Secondreactortripsystem2.3.35反应堆毒物排除Reactorpoisonremoval2.1.11反应堆堆内构件Reactorinternal2.2.27反应堆堆芯Reactorcore2.2.28反应堆二回路Reactorsecondarycircuit2.2.29反应堆分批装料Reactorbatchloading2.1.12反应堆工艺Reactortechnology2.2.30反应堆换料2.1.13Reactorrefueling反应堆减速剂Reactormoderator2.2.32反应堆检测仪表Reactorinstrumentation2.2.31，勺J、反应堆结构Reactorstructure2.2.︶份4、反应堆结构材料Reactorstructuralmaterial2.2.~反应堆孔道Reactorchannel2.2.35反应堆控制材料Reactorcontrolmaterial2.2.36反应堆控制系统Reactorcontrolsystem2.2.37反应堆冷却剂Reactorcoolant2.2.38反应堆冷却剂补给系统Reactorcoolantsupplementarysystem2.2.39反应堆冷却剂材料Reactorcoolantmaterial2.2.40反应堆冷却剂系统Reactorcoolantsystem2.2.41反应堆冷却系统Reactorcoolingsystem2.2.42反应堆慢化剂Reactormoderator2.2.43反应堆慢化剂材料Reactormoderatormaterial2.2.44反应堆模拟器Reactorsimulator2.2.45反应堆内部部件Reactorinternal2.2.46反应堆屏蔽Reactorshielding2.2.47反应堆屏蔽材料Reactorshieldingmaterial2.2.48反应堆启动Reactorstartup2.1.14反应堆燃料Reactorfuel2.2.49反应堆燃料元件Reactorfuelelement2.2.50反应堆热工设计Reactorthermohydraulicdesign2.1.15反应堆审批Reactorlicensing2.1.162.2.53反应堆实验装置Reactorexperimentalfacilities反应堆数字化保护系统Digitalreactorprotectionsystem2.3.36反应堆停堆系统Reactortripsystem2.3.37反应堆退役Reactordecommissioning2.1.17 DL/T1033.5一2006反应堆卸料Reactordischarging2.1.18反应堆压力容器Reactorpressurevessels(RPV)2.2.54反应堆压力容器材料materialforreactorpressurevessel2.2.55反应堆压力容器水位测量WaterlevelmeasurementofRPV2.3.38反应堆压缩机Reactorcompressor2.2.56反应堆一回路Reactorprimarycircuit2.2.57反应堆仪表监测系统Reactorinstrumentationmonitoringsystem2.3.39反应堆运行Reactoroperation2.1.19反应堆运行人员Reactoroperator2.1.20反应堆载热剂Reactorcoolant2.2.58反应堆噪声Reactornoise2.1.21反应堆栅格Reactorlattices2.2.51反应堆栅元Reactorcells2.2.52反应堆振荡器Reactoroscillator2.2.59反应堆中毒Reactorpoisoning2.1.22反应堆周期Reactorperiod2.1.23反应堆主管道材料Reactorcoolantpipingmaterial2.2.60反应堆装料Reactorfueling2.1.24(2.2.61)反应性引入Reactivityinsertion2.2.62防护衣具Protectiveclothing2.3.40放射分析法Radiometricanalysis2.5.9放射化学分析Radiochemicalanalysis2.5.10放射化学实验室Radiochemicallaboratories2.3.41放射生态学Radioecology2.4.10放射损伤Radiationinjury2.4.11放射效应Radiationefect2.3.42放射性沉降粒子Falloutparticulate2.3.43放射性沉降物Radioactivefallout2.3.44放射性废水Radioactivewastewater2.5.11放射性废物Radioactivewaste2.3.45放射性废物处理Radioactivewasteprocessing2.5.12放射性废物设施Radioactivewastefacility2.5.13放射性废物贮存Radioactivewastestorage2.5.14放射性废渣Radioactivewasteresidue2.5.15放射性核素代谢Radionuclidemetabolism2.4.12放射性核素动力学Radionuclidekinetic2.4.13放射性核素分布Radionuclidedistribution2.4.14放射性核素更新Radionuclideturnover2.4.15放射性核素环境转移Radionuclidetransferinenvironment2.4.16放射性核素排出Radionuclideelimination2.4.17放射性核素体内转移Radionuclidetransferinorganism2.4.18放射性核素吸收Radionuclideabsorption2.4.19放射性核素在人体内的代谢Radionuclidemetabolismwithinhumanbody2.4.20 DL/T1033.5一2006242，1放射性核素滞留Radionuclideretention.24，2白放射性监护Radioactivitysurveillance.242内J放射性排放标准Radioactivitylimitsofrelease.，42月峙放射性去污Radioactivitydecontamination白.242~、放射性去污剂Radioactivitydecontaminationagent.︶242矛勺放射性去污装置Radioactivitydecontaminationfacility.2427放射性同位素动力学Radioisotopekinetic.，月，R山峙‘放射性污染Radioactivecontamination,Radioactivepollution.︸2内46j放射性污染规章Radioactivecontaminationregulation.，内月1﹂峙1曰放射性药物Radiopharmaceutical.6内J沸水堆Boilingwaterreactor(BWR)2.2…64沸水堆压力容器BWRpressurevessel2.2勺飞40沸水堆应急堆芯冷却系统EmergencycorecoolingsystemofBWR~曰024内O、辐射防护基本原则Basicprinciplesofradiationprotection…︶少2440辐射防护技术Radiationprotectiontechnique2441辐射防护评价Radiationprotectionassessment辐射防护指南Radiationprotectionguide2.4.42辐射环境监测Environmentalradiationmonitoring2.3.49辐射活化Radioactivation2.4.43辐射剂量Radiationdose2.4.44辐射剂量标准Radiationdosestandard2.4.45辐射剂量单位Radiationdoseunit2.4.46辐射剂量分布Radiationdosedistribution2.4.47辐射监测Radiationmonitoring2.3.50辐射监测器Radiationmonitor2.3.51辐射屏蔽Radiationshielding2.4.29辐射生物效应Biologicaleffectofradiation2.4.30辐射损害(非生物)Radiationdamage(nonbiologic)2.4.31辐射损伤Radiationinjury2.4.32辐射探测Radiationdetection2.3.52辐射危害Radiationha7,qrd2.4.33辐射吸收分析Radiationabsorptionanalysis2.5.16辐射效应Radiationeffect2.4.34辐射遗传效应Geneticradiationeffect2.4.35辐射影响Radiationimpact2.4.36辐照Irradiation2.4.37辐照工厂Irradiationplant2.5.17辐照过的核燃料储存Irradiatednuclearfuelstorage2.3.53辐照过的核燃料元件IrradiatednuclearfuelelementSpentfuelelement2.2.65辐照盒Irradiationcapsule2.3.54辐照孔道Irradiationchannel2.2.66辐照用具Irradiationrig2.3.55 DL/T1033.5一2006辅助给水系统Auxiliaryfeedwatersystem2.3.56G改进型气冷堆Advancedgas-cooledreactor(AGR)2.2.67高浓缩铀(80%~100%)Highlyenricheduranium2.2.68高温气冷堆High-temperaturegas-cooledreactor(HTGR)2.2.69高压冷却剂注入系统High-pressurecoolantinjectionsystem2.3.57个人剂量监测Personaldosemonitoring2.4.38供热堆Processheatreactor2.2.70汞冷堆Mercurycooledreactor2.2.71固体废物处理系统Solidwasteprocessingsystem2.4.48H海水淡化Seawaterdesalination2.2.72合理可行尽量低Aslowasreasonablyachievable2.1.25核安全保障Nuclearsafeguards2.3.58(2.4.49)核安全保障规章Nuclearsafeguardregulations2.3.59核保险Nuclearinsurance2.3.60核材料管理Nuclearmaterialsmanagement2.1.26核岛Nuclearisland(NI)2.2.73核电厂安全级电气设备Safetyrelatedelectricalequipmentfornuclearpowerplant2.2.74核电厂厂用电系统Housepowersupplyofnuclearpowerplant2.2.75核电厂防火Fireprotectionofnuclearpowerplant2.1.27核电厂分区管理Zonecontrolofnuclearpowerplant2.1.28核电厂流出物监测Monitoringofeffluentsfromnuclearpowerplant2.3.61核电厂汽轮发电机Turbogeneratorfornuclearpowerplant2.2.76核电厂设计Nuclearpowerplantdesign2.1.29核电厂施工Nuclearpowerplantconstruction2.1.30核电厂退役Nuclearpowerplantdecommissioning2.1.31核电厂一回路监测系统MonitoringsystemofprimarycircuitofNPP2.3.62核电厂源项Sourcetermfromnuclearpowerplant2.4.50核电厂运行Nuclearpowerplantoperation2.1.32核电厂运行管理Operationalmanagementofnuclearpowerplant2.1.33核电厂正常启动Normalstartupofnuclearpowerplant2.1.34核电厂正常停闭Normalshutdownofnuclearpowerplant2.1.35核毒物Nuclearpoison2.1.36核反应Nuclearreaction2.2.77核辐射安全Radiationsafety2.4.51核功率测量Nuclearpowermeasurement2.3.63核供汽系统Nuclearsteamsupplysystem(NSSS)2.2.78核聚变反应堆Fusionreactor2.1.37核汽轮机Nuclearsteamturbine2.2.79核燃料Nuclearfuel2.2.80核燃料管理Nuclearfuelmanagement2.1.38核燃料后处理Nuclearfuelreprocessing2.5.18 DL/T1033.5一20062核燃料后处理厂Nuclearfuelreprocessingplant5.19，39核燃料利用率Nuclearfuelutilization︸2281核燃料元件Nuclearfuelelement，亡20J核燃料制造厂Nuclearfuelfabricationplant︸2‘.40.核燃料转换Nuclearfuelconversion12141核设备在役检查In-serviceinspectionofnuclearequipment21核设施Nuclearfacility2.582核石墨Nucleargraphite2.283核碎片Nuclearfragment2.264核物料Nuclearmaterial2.384核蒸汽供应系统Nuclearsteamsupplysystem(NSSS)2.252化学辐射效应Chemicalradiationeffect2.485化学和容积控制系统Chemicalandvolumecontrolsystem2.22环境影响评价Environmentalimpactassessment4.53勺0升00环状燃料兀件Annularfuelelement︺6‘缓发辐射效应2.3JDelayedradiationeffect4，换料方案Refuelingscheme2.1︸22黄饼Yellowcake2.5混合氧化物燃料)‘Mixedoxidefuelfabricationplant2.5.23J积分剂量Integraldose2.4.54齐日量当量Doseequivalent2.4.552…456PEI]量负#r1.Dosecommitment257剂量率Doserate，58剂量效应关系Dose-responserelationship︸，…524加速器Accelerator~225加速器设备Acceleratorfacility，26加速器增殖堆Acceleratorbreeder︸勺287钾冷堆Potassiumcooledreactor︸236检测(放射性)Surveillance(radioactivity)2.l48建设前期工作Pre-projectandpreconstructionactivity2建议书(辐射防护)Recommendations(radiationprotection)4.59勺40降功率运行山产Underloadedoperation211、n划紧急停堆Scram‘︸2今只O紧急停堆棒Scramrod.J︶C勺月乙n石峙Ul局部辐射效应Localradiationefect…︶214，J聚变堆Fusionreactor2.44.聚变堆材料Fusionreactormaterial12141、聚变反应Fusionreaction…~21.4护61聚变反应堆Fusionreactor2心.4月1了聚变增殖堆FusionbreederK开堆Reactorstartup2.1.5123 DL/T1033.5一20062.527可燃毒物Burnablepoison,Burnoutpoison2367空间分布Spacedistribution2.l52空间核电力装置Spacenuclearpowerunit2…46l空间剂量分布Spatialdosedistribution289空气冷却堆Air-cooledreactor290空心燃料棒Hollowfuelrod68勺3‘孔栏(聚变堆)Diaphragms(fusionreactor)2:29l控制棒Controlrod532控制棒价值Controlrodworth2292控制棒驱动装置Controlroddrive6923控制棒位置指示Detectionofcontrolrodposition2…l54控制棒效率Controlrodeffectiveness62，‘控制区Controlledareas932快堆Fastreactor2…l5快速停堆Scram94，1快中子堆Fastneutronreactor952快中子增殖堆Fastbreederreactor(FBR)L累积照射指标Cumulativeexposureindex2.4.63冷却剂净化系统Coolantcleanupsystem2.2.96离体辐照Extracorporealirradiation2.4.64粒子加速器Particleaccelerator2.5.28连续辐照Continuousirradiation2.4.65裂变产物Fissionproduct2.3.70裂变产物释放Fissionproductrelease2.4.66裂变毒物Fissionpoison2.1.56裂变一聚变混合堆Fission-fusionhybridreactor2.1.57裂变碎片Fissionfragment2.3.712.4.67裂变碎片探测FissionfragmentdetectionM慢性辐射效应Chronicradiationeffect2.3.72慢性辐照Chronicirradiation2.4.68膜态沸腾Filmboiling2.2.97N内衬Liner2.3.732469内辐照Internalirradiation2470内污染Internalcontamination8229钠泵Sodiumpump2299钠回路Sodiumloop221(X)钠冷堆Sodium-cooledreactor22101钠冷快中子增殖堆Sodium-cooledfastbreederreactor02221钠冷石墨慢化堆Sodium-cooledgraphicmoderatedreactor(SGR)2374能量范围Energyrange DL/T1033.5一2006P培训堆Trainingreactor2.2.1031~、8配置控制Configurationcontrol2.1︸21~勺9硼化Boronation,Boronizing.122104硼回收系统1Boronrecyclesystem22d05.被慢化剂Beryliummoderator12内，5、偏滤器Divertor︶尸2贫化铀Depleteduranium2.106勺-气2Q平衡燃料循环Equilibriumfuelcycle‘︶247曰.屏蔽层Shields(reactor)1，内，︸6j屏蔽容器Cask白夕，门门7﹂产破裂Rupture一破损Failure2.3.782472破损包壳探测Burstcandetection2内79J破损方式分析Failuremodeanalysis，473破损燃料块探测Burstslugdetection白2474破损元件探测Failedelementdetection2160谱漂移控制1SpectralshiftcontrolQ气冷堆Gas-cooledreactor2.2.107气冷快堆Gas-cooledfastreactor(GCFR)2.2.108气体冷却剂Gascoolant2.2.109汽水分离再热器Moistureseparator-reheater2.2.110氢化物慢化剂Hydridemoderator2.2.111氢冷堆Hydrogen-cooledreactor2.2.112氢氧化物慢化剂Hydroxidemoderator2.2.113轻水冷却剂Lightwatercoolant2.2.114轻水慢化剂Lightwatermoderator2.2.115躯体辐射剂量Bodyefectdose2.4.75取样器Sampler2.3.80全身辐照Whole-bodyirradiation2.4.76群常数Groupconstant2.3.81RJ.16燃料板Fuelplate,Fuelslab2.2且J1，.声燃料棒Fuelrod2.2.11.1一城燃料棒包壳材料Fuelrodcladdingmaterial2.2.1︶‘.1Q燃料棒束Fuelbundles2.2.I户J，n.燃料包覆层Fuel-cladding2.2.工白︸J.，1燃料包壳Fuelcan2.2.1‘，22.燃料包套Fueljacket2.2.且，2八.、燃料管道Fuelchannel2.2.且︶J.，4燃料浆液Fuelslurry2.2.1︸曰.21勺燃料颗粒Fuelparticle2.2.1 DL/T1033.5一2006燃料孔道Fuelchannel2.2.126燃料块Fuelslug2.2.127燃料片Fuelsheet2.2.128燃料球Fuelsphere2.2.129燃料扫描Fuelscanning2.2.130燃料外壳Fuelsheath2.2.131燃料细棒Fuelpin2.2.132燃料悬浮液Fuelsuspension2.2.133燃料循环Fuelcycle2.5.30燃料元件Fuelelement2.2.134燃料元件稳流套Shroud2.2.135燃料元件制造Fuelelementfabrication2.5.31燃料再循环Fuelrecycle2.5.32燃料致密化Fueldensification2.1.61燃料装卸搬运系统Fuelhandlingsystem2.2.136燃料组件Fuelassembly2.2.137燃料组件拆卸Fuelassemblydismantling2.1.62燃料组件辐照性能Irradiationperformanceoffuelassembly2.5.33燃料组件结构材料Structuralmaterialoffuelassembly2.2.138燃料组件制造Fuelassemblyfabrication2.5.34热传输介质Heattransportmedium2.2.139热传输介质净化系统Heattransportmediumpurificationsystem2.2.140热传输介质压力和装置控制系统Heattransportpressureandinventorysystem2.2.141热堆Thermalreactor2.2.142热管道Hotchannel2.2.143热核堆Thermonuclearreactor2.1.63热离子燃料元件Thermionicfuelelement2.2.144热屏蔽层Thermalshield2.4.77热实验室Hotlab2.3.82热室Hotcell2.3.83热室机械手Hotcellmanipulator2.3.84热中子堆Thermalneutronreactor2.2.145热柱Thermalcolumns2.2.146人的辐射效应Radiationeffectonman2.4.78熔盐冷却剂Moltensaltcoolant2.2.147S烧干Dryout2.1.64烧毁Burnout2.1.65烧毁装置Burnoutdevice2.3.85稍浓缩铀(0.7%^-5%)Slightlyenricheduranium2.2.148射线照射量Radiationexposure2.4.79深部剂量Depthdose2.4.80深部剂量分布Depthdosedistribution2.4.81 DL/T1033.5一2006，生产堆Productionreactor︸2.149，4R2生物半减期Biologicalhalf-life‘4Q气生物辐射效应O、Biologicalradiationeffect︶Q4生物屏蔽八Biologicalshielding2.4︶01生物屏蔽层八Biologicalshield2.4︶口n6乘」余功率6Residualpower2.3llln石墨慢化堆Graphitemoderatedreactor2.2jUltI工石墨气冷堆Gas-cooledgraphite-moderatedreactor2.2Jll勺l石墨水冷堆Graphite-moderatedwater-cooledreactor2.2J﹄24Q护6时间剂量分布Temporaldosedistribution八21麦厂实体分隔PhysicalseparationUo，今ll，l、实验堆Experimentalreactor︸︸j︶勺2lsel4实验孔道Experimentalchannel‘︶今2l~、l事故棒Emergencyrod︸︶J，1麦7事故停堆Emergencyshutdownofreactor‘U.今4Q，事故性辐照Accidentalirradiation︸OJ22ll行人试验堆TestreactorJU2，l工、l束孔Beamholes尹1J2八o勺、束流Beamchtre爪︶n夕2勺l~、O双循环冷却系统Dualcycleood如$rSystem‘︸八22l-、g水冷堆Water-cooledreactor︺，勺l户6n水慢化堆Water-moderatedreactor‘1曰24Q0瞬时剂量分布Temporaldosedistribution乃02，161四极汽轮发电机Four-polesteamturbinegenerator︸T，，行人O逃脱共振几率.盆UCResonanceescapeprobability︸QO八体外辐照Extracorporealirradiation2.4产勺天然铀Naturaluranium‘2.162今6n停堆Reactorshutdown︸，00同步辐射Synchronousradiation2.300勺1、同位素分离工厂Isotopeseparationplant2.5、︶︸WQ八外辐照UExternalirradiation2.4产，64稳压器(核)Pressurizer2.2几l一人1、稳压容器Pressurizer2.2lU︶O9物料操作materialhandling2.3OQ0物料平衡Materialbalance2.3Z物料平衡区(核燃料加工)Materialbalancearea2.3.91X吸收份额Absorbedfraction2.4.91吸收剂量Absorbeddose2.4.92吸收剂量分布Absorbeddosedistribution2.4.93稀释Dilution2.1.7027 DL/T1033.5一20062.16先进沸水堆AdvancedBWR(ABWR)2.167先进轻水堆Advancedlightwaterreactor2.168先进压水堆AdvancedPWR(APWR)2.1.71氮效应Xenonefect2.4.94小剂量辐照Lowdoseirradiation2.169芯(反应堆)Cores(reactor)2.170新燃料储存架NewfuelassemblystoragerackY21月2了压力释放(反应堆)Pressurerelease(reactor)22.71里压水堆Pressurizedwaterreactor(PWR)22曰72.工压水堆本体PWRvesselanditsinternal22J73.1压水堆堆内构件PWRinternal22弓74.1压水堆可燃毒物组件BurnablepoisonassemblyforPWR7522门.1压水堆控制棒驱动机构ControlroddrivemechanismforPWR22，76.盈压水堆控制棒组件ControlrodassemblyforPWR17几压水堆燃料组件PWRfuelassembly782，11‘压水堆压力容器PWRpressurevessel.792，，.‘盈压水堆一次冷却剂泵PWRprimarycoolantpump.22内0J户压水堆应急堆芯冷却系统EmergencycorecoolingsystemofPWR…80，，，.压水堆蒸汽发生器传热管材料臼‘1HeattransfertubematerialofPWRsteamgenerator2勺181‘1压水堆中子源组件NeutronsourceassemblyforPWR2，泊82.l研究堆Researchreactor…~，，j.83‘1研究与试验堆Researchandtestreactor︸2173.液态毒物控制Fluidpoisoncontrol.2.21别液态金属冷却堆Liquidmetalcooledreactor2卫185液态金属冷却剂Liquidmetalcoolant2.21双液态金属冷却快中子增殖堆Liquidmetalcooledfastbreederreactor(LMFBR)2.21即一次冷却剂系统Primarycoolantsystem朋2…21一回路Primarycircuit21朋一回路卸压设备Primarycircuitpressurereliefequipment，1灾乙一体化冷却系统Integratedcoolingsystem2A95仪表辐射效应Instrumentradiationefect，闷96~仪表抗辐照Instrumentantiradiation2月97仪表失效效应Instrumentdeficientefect2…303产应急给水系统Emergencyfeedwatersystem2八6j铀一杯循环Uranium-plutoniumcycle2心j7铀浓缩物Uraniumconcentrate19.1有机冷却剂Organiccoolant2.22219，‘有机慢化剂Organicmoderator2498有效半减期Efectivehalf-life2月9峙有效遗传剂量Geneticalysignificantdose21741余热导出After-heatremoval余热排出系统Residualheatremovalsystem2.2.193 DL/T1033.5一2006闽剂量Thresholddose2.4.100远隔辐射效应Abscopalradiationeffect2.4.101远距离操作Remotehandling2.3.94远距离操作设备Remotehandlingequipment2.3.95远距离观测设备Remoteviewingequipment2.3.96远期辐射效应Lateradiationeffect2.4.102运行基准地震Operatingbasisearthquake2.1.75ri再生区Blankets(breeding)2.2.194再湿Rewetting2.1.76早期辐射效应Earlyradiationeffect2.4.103噪声诊断系统Noisediagnosissystem2.3.97增压比Superchargingpressureratio2.2.195增殖区Breedingblanket2.2.196Q只增殖芯块Breedingpellet2.3.了UQ八，真空系统Vacuumsystem2.3.矛︸，Q月1了蒸汽发生器Steamgenerator2.2.户蒸汽和动力转换系统Steamandpowerconversionsystem2.2.198直接循环冷却系统Directcyclecoolingsystem2.2.199质子探测Protondetection2.4.104致死辐射剂量Lethalradiationdose2.4.105致死辐照Lethalirradiation2.4.106滞留Retention2.4.107中浓缩铀(5%-80%)Moderatelyenricheduranium2.2.200中子反射层Neutronreflectors2.2.201中子探测Neutrondetection2.4.108重水Heavywater2.2.202重水厂Heavywaterplant2.5.38重水堆Heavywaterreactor(HWR)2.2.203重水堆安全系统SafetysystemofHWR2.3.100重水堆氖化和除氖系统DeuterationanddedeuterationsystemofHWR2.2.204重水堆慢化剂覆盖气体系统ModeratorcovergassystemofHWR2.2.205重水堆慢化剂系统ModeratorsystemofHWR2.2.206重水堆燃料通道组件FuelassemblyandfuelchannelassemblyforHWR2.2.207重水堆燃料装卸系统RefuelingsystemofHWR2.2.208重水堆热传输系统HeattransportsystemofHWR2.2.209重水堆停堆冷却系统ShutdowncoolingsystemofHWR2.2.210重水堆装卸料机RefuelingmachineofHWR2.2.211重水冷却堆Heavywatercooledreactor2.2.212重水冷却剂Heavywatercoolant2.2.213重水慢化堆Heavywatermoderatedreactor2.2.214重水慢化剂Heavywatermoderator2.2.215重要厂用水系统Essentialservicewatersystem2.3.101 DL/T1033.5一2006主控制室人因工程Maincontrolroomhumanfactorsengineering2.1.77抓取装置Grab2.3.102专设安全设施EngineeredsafetyfeaturesofNPP2.3.103专设安全设施驱动系统Engineeredsafetyfacilityactuationsystem2.3.104转换比Conversionratio2.1.78装料机Fuelingmachine,Chargingmachine2.2.216最终热井Ultimateheatsink2.1.79'