核电专业英语词汇

1、 10原子核、核子及相关术语质子 proton 中子 neutron电子 electron核子 nucleon核nucleus pl.nuclei原子 atom光子 photon正电子 positron量子 quantum, quanta (pl.)电子伏特 electron-volt (eV)兆电子伏特 mega electron-volt (MeV)同位素 isotope原子序数 atomic number质量数 mass number超铀元素 transuranium element元素周期表 periodic table热中子 thermal neutron 快中子 fast neut

2、ron复合核compound nucleus相关元素与材料核燃料与增殖材料铀 uraniumU 钚 plutoniumPu氘，重氢 deuterium，heavy hydrogen氚 tritium混合氧化物燃料MOX燃料Mixed(Uranium and Plutonium) OXide fuel二氧化铀 uranium dioxide浓缩铀 enriched uranium 贫铀 depleted uranium碳化铀 uranium carbide钍 thorium锂 lithium锕系元素 actinide element易裂变的 fissile可裂变的、可裂变物质 fissionab

3、le增殖同位素 fertile isotope 核嬗变 nuclear transmutation转化 conversion其它核材料及核电厂用材料慢化剂 moderator轻水 light water 重水 heavy water石墨 graphite冷却剂 coolant氦 helium液态金属 liquid metal钠 sodium包壳 cladding铝 aluminium 镁 magnesium锆 zirconium2/4 合金 zircaloy-2/4不锈钢 stainless steel 把握材料 control material通量展平flux-shaping银 silver

4、铟 indium镉 cadmium可燃毒物 burnable poison硼 boron硼酸 boric acid锂 lithium铍 beryllium乏燃料 spent fuel因科镍，因康 INCONEL不锈钢 stainless steel核反响及相关术语decay 衰变fission 裂变fusion 聚变nuclear reaction 核反响chain reaction 链式反响cross section截面microscopic cross section 微观截面macroscopic cross section 宏观截面absorbing cross section吸取截面

5、scattering cross section散射截面barn 靶恩delayed neutron 缓发中子prompt neutron 瞬发中子prompt criticality 瞬发临界fissile易裂变的fissionab可裂变的le morderate / slow down慢化breeding ratio增殖比burnup燃耗reactivity 反响性neutron cycle 中子循环fission product 裂变产物criticality临界prompt critical 瞬发临界flux通量xenon 氙iodine 碘actinide 锕系元素 reactivi

6、ty worth 反响性价值慢化剂温度系数 moderatortemperaturecoefficient反响性系数 reactivitycoefficient剩余反响性 excessreactivity燃料比功率 fuelspecificpower倍增因子 multiplication factor有效增殖系数 effectivemultiplicationfactor；effective multiplication constant无限介质增殖系数 infinite multiplicationfactor； infinite multiplication constant快中子增殖系数

7、 fast fission factor热中子利用系数thermalutilizationfactor不泄漏几率 nonleakageprobability逃脱共振俘获几率resonanceescapeprobability四因子公式 four-factorformula多普勒增宽 Doppler broadening*总集成中子通量 /总积分中子通量 TotalIntegrated Neutron Flux = Integrated Flux or Fluence (注量) = Neutron density VelocityTime 单位：n/m3 m/s s = n/m2反响堆压水堆 P

8、ressurized Water Reactor (PWR)沸水堆 Boiling Water Reactor (BWR)加拿大重水铀反响堆坎杜堆 CANadian Deuterium and Uranium reactor (CANDU) /pressurized heavy water reactor (PHWR)英国气冷堆美诺克斯堆British gas-cooled Magnox reactor高温气冷堆 high temperature gas-cooled reactor (HTGR)快中子增殖反响堆 fast breeder reactor (FBR)轻水堆 Light Wate

9、r Reactor (LWR)先进反响堆 advanced reactor超临界水反响堆 supercritical water reactor欧洲压水堆第三代反响堆之一 European Pressurized water Reactor (EPR)美国600/1000第三代(+)反响堆之一 AP(WR)600 / 1000核电厂部件、设备与系统燃料芯块 fuel pellet 燃料元件 fuel element燃料棒 fuel rod燃料组件 fuel assembly定位格架 spacer grid 法兰 flange密封环 seal ring阻力塞 plug(上/下)腔室 (upper

10、 / lower ) plenum堆芯，活性区 core反响堆压力 容器 Reactor Pressure Vessel(RPV)上封头 upper closure head液压螺栓拉伸机张紧机) hydraulic studtensioner包覆层 clad(碳钢外表的防腐蚀堆焊层)把握棒 control rod把握棒组件 ControlElementAssembly(CEA)可燃吸取棒 burnable absorber rod把握棒驱动机构 ControlElementDriveMechanism (CEDM)变送器 transmitter信号调理 signal regulation吊篮

11、 barrel进/出口接收 inlet / outlet nozzle冷/热端，冷/热腿，冷/热管段 cold / hot leg反响堆堆内构件 reactor vessel internals肿胀 swelling腐蚀 corrode, corrosion侵蚀 erode, erosion氧化 oxidation, oxidize完整性 integrity反响堆冷却剂泵主泵 Reactor CoolantPump (RCP)屏蔽泵 canned (motor) pump轴封泵 shaft seal pump反响堆冷却剂系统一回路系统 ReactorCoolant System (RCS)核蒸

12、汽供给系统 NuclearSteamSupplySystem (NSSS)一回路 primary loop/circuit一回路系统/主回路系统 primary system二回路 secondary loop 稳压器 pressurizer (PRZ)波动管 surge line汽水分别器 moisture separator枯燥器二/三级汽水分别器steam dryer安全阀 safety valve卸压阀 relief valve溢流阀 overflow valve主蒸汽隔离阀 main steam isolation valve单向阀 check valve止回阀 non-return

13、 valve主蒸汽联箱 main steam header给水调整阀 feed regulating valve 蒸汽发生器 Steam Generator (SG)主蒸汽管 Main Steam Line (MSL)汽轮机 steam turbine汽水分离再热器MoistureSeparatorReheater (MSR)给水泵 feed (water) pump上充泵 charging pump凝汽器 condenser发电机 (electric) generator安全壳 containment地基，根底 foundation烟道 stack贯穿件 penetration核岛 nucl

14、ear island常规岛 conventional island核电厂配套子项 Balance of Plant (BOP)回路辅助系统 auxiliarysystemforprimary loop化容系统 Chemicaland Volume Control System (CVCS)专设安全设施 Engineered Safety Feature(ESF)余热排出系统 ResidualHeat-RemovalSystem (RHRS)应急堆芯冷却系统 Emergency Core CoolingSystem (ECCS),安注系统Safety Injection (SI) System直

15、接注射系统 direct vessel injection (DVI) 换料水箱 RefuelingWater StorageTank(IRWST)(乏)燃料贮存水池 (spent) fuel storage pool燃料装卸系统 fuel handling system蓄压箱 accumulator机组 unit关心喷淋 auxiliary spray柴油发电机 Diesel generator自动保护系统 Automatic Protective System(APS)自动降压系统 automatic depressurizationsystem (ADS)仪控系统 Instrumenta

16、tionandControlSystem (I & C system)开关设备，开关柜 switch gear蒸汽轴封系统，压盖蒸汽密封系统glandsteam system汽轮机旁路管 turbine bypass line关心给水泵 auxiliary feedwater pump汽动给水泵 turbine driven feedwater pumpconduit冷凝水泵condensate pump冷凝水增压泵 condensate booster pump水润滑轴承 water lubricated bearing人孔 man way检修孔 accessory port反响堆运行运行

17、operation运行工况 operating condition操纵员 operator维护 maintenance监视、监视surveillance监视试样 surveillance specimen辐照监视管 irradiation surveillance capsule 辐照监视试样盒 surveillancespecimencompartment硼浓度 boron concentration稀释 dilution / dilute 硼注入boroninjection停堆 shutdown紧急停堆 scram / trip停役 outage换料停堆 refuelingoutage/r

18、efuelingshutdown换料 refuel卸料 discharge倒料 shuffling满功率运行 full power operation负荷跟踪 load following甩负荷 load shedding, load rejection(把握棒等的)插入 insertion(把握棒等的)抽出 withdrawal反响堆调整系统 Reactor Regulating System(RRS)(蒸汽发生器)排污、下泄 blowdown规程 procedure技术规格 technical specification瞬态，瞬变 transient安装调试 installation an

19、d commissioning冷态试验 coldfunctionaltest热态试验 hotfunctionaltest(反响堆)启动试验 (reactor) start up test退役 decommissioning主控室 main control room方位角偏差 azimuthal tilt径向功率分布 radial power distribution轴向功率分布 axial power distribution 燃料治理方案fuel management scheme燃料包壳交互作用 fuel-clad interactioneffect芯块- 包壳交互作用 (PCI)pell

20、et-cladinteraction(燃料)栅格、晶格 lattice反响堆安全核安全 nuclear safety安全功能 safetyfunction衰变热 decay heat余热 residual heat空泡系数 void coefficient法律 law法规 regulation / code联邦治理法规 Code of Federal Regulations(CFR)法案美 Act导则 guidance1/2/3 safety class 1/2/3牢靠性 reliability容限，裕量，边界margin堆芯热裕量core thermal margin 堵管裕量 tube p

21、lugging margin 运行安全裕量 operating margin标准，准则 criterion，复数形式: criteria概率安全分析 Probabilistic Safety Analysis (PSA)概率风险分析 Probabilistic Risk Analysis(PRA)deterministic safetyanalysis初步安全分析报告 PreliminarySafetyAnalysis Report (PSAR)最终安全分析报告Final Safety AnalysisReport (FSAR)安全评价报告 safety evaluation report大事

22、 incident事故 accident后果 consequence严峻事故 severe accident堆芯损毁 core damage 堆芯溶化 core meltdown全厂断电 station blackout失水事故Loss-of-coolantAccident (LOCA)反应性引入事故 ReactivityInsertionAccident (RIA)未能紧急停堆的估量瞬变 AnticipatedTransient Without Scram (ATWS)失电 Loss of Power失流 Loss of flow先漏后破leak before break (LBB)故障安全

23、，失效保护 fail-safe单一故障准则 single-failure criterion共因故障 common cause failure固有安全性 inherent safety非能动安全 passive safety 冗余性 redundancy多样性 diversity多层屏障 multiple barrier纵深防范 defense in depth工作不正常，故障 malfunction失效 failure假设始发大事 postulated initiating events事故工况 accident condition严峻事故 severe accident事故处理 accid

24、ent management设计基准事故 design basis accident负荷丧失事故lossofelectricalload潜热latent heataccident焓，热函 sensible heat, enthalpy主给水丧失事故lossofmain定期安全检查 periodic safety inspectionwateraccident许可证 license卡棒事故 stuck rod accident监管 regulation弹棒事故 rod ejection accident 核安全准则 nuclear safety criteria堵管裕量 tube pluggin

25、g margin 三哩岛事故 ThreeMileIsland(TMI)管道甩摆限制 pipe whip restraintaccident在役检查 inservice inspection切尔诺贝利事故 Chernobyl accident承压热冲击 pressurized thermal shock放射性与辐射防护radioactivity放射性shielding 屏蔽scatter 散射biological shield 生物屏蔽deflect, deflection 折射剂量 dose衍射 diffractiondose equivalent 剂量当量穿透 penetrate, pene

26、trationcollective dose 集体剂量交互作用 interact, interactionindividual dose 个人剂量ionization 电离ingest, ingestion 摄入，摄取湮灭 annihilate (v.), annihilation (n.)inhale, inhalation吸入衰减 attenuate(v.), attenuation(n.)coma 昏迷projectile 入射离子cramp 绞痛radiation protection 辐射防护diarrhea 腹泻radiation, ray辐射，射线tremor抖动irradiat

27、ion辐照向外辐射vomit呕吐internal exposure 内照耀somatic 身体的external exposure 外照耀somatic effect躯体反响occupational dose 职业照耀剂量radiation sickness 辐照病变fluence 注量symptom征兆cosmic ray宇宙射线therapy治疗x-ray X 射线survivor 幸存者/ 射线 / rayactivation product 活化产物health physics保健物理effluent废水feednatural background 自然本底sivert希弗spectr

28、um 谱雷姆 rem 氡 radonas low as reasonably achievable (ALARA) 合理可行尽量低radioactive waste disposal 放射性废物处理high-level (radioactive) waste高放废物low-level (radioactive) waste低放废物有关机构International Atomic Energy Agency (IAEA) 国际原子能机构American Society of Mechanical Engineers (ASME) 美国机械工程师学会Nuclear Regulatory Commi

29、ssion (NRC/USNRC) 美国核管会Department Of Energy (DOE) 美国能源部World Association of Nuclear Operators (WANO) 世界核电运营者协会International Commission on Radiological Protection (ICRP) 国际辐射防护委员会China Atomic Energy Authority CAEA中国国家原子能机构State Environment Protection Administration of China国家环保总局其它术语lateral横向longitud

30、inal 纵向radial 径向perpendicular to垂直于材料失效术语corrosion 腐蚀stress corrosion cracking 应力腐蚀开裂rapture, fracture, break断裂breach 破口肿胀 swelling cavitation 气蚀pitting 点蚀/孔蚀crevice corrosion 缝隙腐蚀erosion冲蚀FAC flow accelerated corrosion 流淌加速腐蚀wastage 耗蚀(SG tube)dent 凹陷，凹痕fatigue疲乏ageing 老化vertically mounted 垂直/立式安装c

31、ircumferential环向axial 轴向periphery 周边degradation 降级wear 磨损fretting wear 微动磨损creep 蠕变stress 应力strain 应变creep strength 蠕变强度tensile strength 抗拉强度yield strength屈服强度rapture strength 断裂强度nil-ductility transition temperature 零延性转变温度thermal stress热应力irradiation swelling 辐照肿胀deposit welding, overlaying, build

32、-up welding,surface welding 堆焊seal weld密封焊核电工程术语procurement 征购site厂址call for bid, call for tender招标commercial offer商务标technical offer技术标commencement开工contract 合同firm contract 不行更改的合同subcontract分包合同commitment承诺，任务job site 工地，工作现场technical requirement技术要求其它compound 化合物mixture混合物mass质量momentum动量energy能

33、量potential (energy) 势能kinetic energy动能inertia惯性half-life半衰期mean free path 平均自由程fuel cycle燃料循环hot spot 热点hot-channel factor热管因子departure from nucleate boiling ratio (DNBR)偏离泡核沸腾比heat transfer 传热heat exchanger 换热器heat conduction 导热convection对流热辐射 thermal / heat radiation干度 quality蒸汽 steam预应力钢 筋混凝土 pre

34、stressed reinforcedheat affected zone (HAZ) 焊接热影响区技术规格 technical specificationnon-conformance不符合项delivery交货warehouse 仓库construction schedule 施工打算Free on Board (FOB) 离岸价格Cost Insurance and Freight (CIF) 到岸价格Engineering,Procurement&ConstructionEPC 合同-设计选购建筑power grid 电网distribution system输变电系统concrete

35、 / prestressed concrete钢筋混凝土 reinforced concrete 铁钢沙混凝土 Steel shot concret筋，钢筋束 tendon流量安排 flow distribution电网 power grid业主 utility承包商 contractor分包商 sub-contractor压降 pressure dropdifferential pressure水位 (water) level规定，条款；保障；装备 provision地震 earthquake地震的 seismic 飓风 tornado暖通空调 Heating,Ventilation and

36、AirConditioning (HVAC)热阱 heat sink惰转 coastdown惰转流量coastdown flow功率失常激增，功率漂移 power excursion减轻，缓解 v. mitigate, n. mitigation公差、容差 allowance间隙，公差 clearance权重因子 weighting factor有必要了解的词汇与短语as a rule of thumb依据阅历by orders of magnitude以数量级incipient failure 早期故障, 初期故障eliminate, elimination消退derive, derivat

37、ion, deduce, deduction源mechanism, approach, principle, theory机理，原理susceptible 敏感的susceptibility 敏感性toxic有毒的acute 急剧的inherit遗传hereditary 遗传性的altitude高度postulate, postulation 假定，假设permeable 可渗透的, 有渗透性的impermeable不行渗透的brittle fracture 脆性裂开embrittlement脆化toughness 韧性ductility延展性第2章阅读理解题练习Passage 1As a r

38、esult reactor designers have paid great attention to the inherent safety ofreactorswhichcanbeachievedbynegativetemperatureandpowercoefficients and fail-safe control systems. It can be said with some confidencethat present-day thermal reactors are safe in the sense that under no conceivable circumsta

39、nce can they explode like a bomb, and control systems have beendesignedwhichcan,intheeventofanymalfunctiononthepartofthereactoror its associated plant, automatically and rapidly shut down the reactor, i.e. make it subcriticalbyasubstantialamount,inaveryfewseconds.According to the paragraph, inherent

40、 safety of reactors can be achievedby. Ctheoperators;positive temperature and positive power coefficients;negative temperature and negative power coefficients;passive safety system and positive power coefficients.Thebesttitleofthepassagemayprobablybe. Dfail-safecontrolsystem；thermalreactorsafetyando

41、peration;automaticprotectivesystem;inherentsafetydesignofreactors.Passage IIThe biological shield should contain some hydrogen compound to slow downfast neutrons, and be dense enough to attenuate gamma radiation effectively.Concrete satisfies both these requirements fairly well and is suitable for l

42、andbase reactors. Barytes (重晶石) concrete, containing the heavy element barium, andsteel-shot concrete have been used for biological shields. They are more densethanordinaryconcrete,withimprovedshieldingproperties,howevertheirhigher cost offsets this advantage. The biological shield for a marine reac

43、tor,which is usually a fairly compact pressurized water reactor, must satisfy aminimum space and weight requirement. This leads to a shield design whichconsists typically of alternate layers of water (for fast neutron slowing) and steel (for gamma ray attenuation).Accordingtotheabovepassage,isnotpos

44、sibleconstructing biological shield? Csteel;C.graphite;B.concrete;D.paraffinwax.Whichofthefollowingsentencesisnottrue?DThe biological shield is designed mainly to slow down fast neutrons andattenuate gamma radiation.The marine reactor uses alternative steel and water layers as its biologicalshield.T

45、he combination of heavy element concrete and steel bars could improvethe shielding properties.The biological shield should use hydrogen element to slow down fastneutron and attenuate gamma radiations.Passage IIIInorder to mitigatetheeffectsoflargerelease of steam (an potentially of radioactivity) in

46、 the containment, two full capacity independent safety systemsareprovided;thereactorbuildingspraysystemandthereactorbuildingemergency coolers. The systems are designed to provide cool water to condense discharge steam and to prevent containment pressure from reaching its designlimit.Individualsystem

47、sdifferconsiderablybutatypicalsystemmaydescribed as follows; The initial capacity of the systems in removing heat from thecontainmentatmosphereistypically253GJ/hr.When a containment pressure of 4psig is reached, the emergency coolers of thereactor buildingare actuated.Intheir postaccidentmode, theco

48、nsists of three units each with a fan and an emergency cooler. As the reactor building air is circulated across a tubular heat exchanger, a portion of steam is condensed. These coolersalone would be capable of returning the containmentpressure to near atmospheric within 24 hr after an accident. When

49、 the pressure reaches a level of 10 psig, the second safety system, the reactor building spraysystem, is automatically actuated. It consists of a pump, piping, headers, andspray nozzles arranged uniformly under the containment dome. It can sprayborated water into the reactor building at a rate of 11

50、.35m3/min. A sodiumhydroxide additive is also provided in the spray water to increase the retention ofiodine, and hence, to reduce its concentration in the containment atmosphere in the event of a sizable breach of fuel cladding.Two full capacity independent safety systems are provided for the desig

51、npurposeof. Acondensingthesteamreleasedintothecontainmentwhenexceeds design limit.maintaining the high pressure in the containmentdischarginglargeamountofsteammitigatingtheeffectofradiationhazardtothecontainment.Thereactorbuildingspraysystemwillbeactuatedautomatically. Cafter24hoursaftertheaccident;

52、immediatelyaftertheaccident;when the containment pressure reaches a level of design limit;whentheairinthecontainmentiscirculatedthroughtheheatexchanger.WhichofthefollowingstatementsisINCORRECT?BTheemergencycoolerconsistsoffansandheatexchangers.The emergency cooler system can spray borated water into

53、 containment.Allthetwosystemareappliedforreturningthecontainmentpressuretobe blow atmospheric after the accident.Sodium hydroxide additive is provided in the spray water to reduce theamount of radioactive fission produces.PassageIVMany reactor-years of operating experience have shown that it is not

54、the fission chain reaction in the reactor core that is the most likely source of malfunction and accidents, but the “conventional” components of the power plant such as pumps, valves, switches, relays and parts under stress such as pressure vessel or pipework. Human error on the part of operating an

55、d maintenance staff has also proved to be a rather frequent source of trouble in nuclear power plant.Thesefactorsarenotpeculiartonuclearpowerplant,buttheyassumegreatimportance because of the hazardous nature of nuclear reactors. Designers have to ensure that all systems should as far as possible be

56、fail-safe and redundant, i.e.if one system fails to function correctly, another is available to fulfill the samefunction.As stated above, nuclear reactors cannot explode like nuclear bombs. This primarily because of the fast acting negative thermal feedback due to Dopplerbroadening of the 238U absor

57、ption resonances. In addition in thermalreactorswhere neutrons are moderated, the prompt neutron lifetime Lp isthe order of10-4 second; in a bomb, since the neutrons are unmoderated, the prompt neuron lifetime is of the order of 10 -8 seconds. Finally, reactor fuel consists typically of 2 to 3 perce

58、nt 235U, where as nuclear weapons contain almost pure 239Pu. The neteffect of these difference is that, even in a reactor which is totally out of control andgonepromptcritical,thereactorperiodwillnotbemuchlessthanasecond orso.Inanuclearbomb,theperiodisoftheorderofnanoseconds.According to the text, t

59、he most likely source of troubles in a nuclear comes fromCore of the reactorConventional componentsParts under stressHuman errorThe first sentence of second paragraph “These factors are not peculiar to ”,what does“These factors”mean?Human errorMalfunction of conventional componentsFission chain reac

60、tion in the coreAll of the aboveWhat make the pressurized water reactors can not explode like a nuclear bomb?Doppler broadening of the 238U absorption resonancesThe neutrons are moderatedPWR fuel contains much less fissile isotopes than nuclear bombAll of the above“The net effect of is of the order