核电专业英语词汇

1、1.1. 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 n

2、eutron复合核compound nucleus 1.2. 相关元素与材料1.2.1. 核燃料与增殖材料铀 uranium（U）钚 plutonium（Pu）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 fissil

3、e可裂变的、可裂变物质 fissionable 增殖同位素 fertile isotope核嬗变 nuclear transmutation转化 conversion1.2.2. 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 zirconium锆2/4合金 zircaloy-2/4不锈钢 stainless steel控制材料 control materia

4、l通量展平flux-shaping银 silver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 steel1.3. 核反应及相关术语decay衰变fission裂变fusion聚变nuclear reaction核反应chain reaction链式反应cross section截面microscopic cross section微观截面macroscopic cross section宏观截面abso

5、rbing cross section吸收截面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lemorderate / slow down慢化breeding ratio增殖比burnup燃耗reactivity反应性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

6、（元素）reactivity worth反应性价值慢化剂温度系数 moderator temperature coefficient反应性系数 reactivity coefficient剩余反应性 excess reactivity燃料比功率 fuel specific power倍增因子 multiplication factor有效增殖系数 effective multiplication factor；effective multiplication constant 无限介质增殖系数 infinite multiplication factor； infinite multiplic

7、ation constant 快中子增殖系数 fast fission factor 热中子利用系数 thermal utilization factor 不泄漏几率 nonleakage probability逃脱共振俘获几率 resonance escape probability四因子公式 four-factor formula多普勒增宽 Doppler broadening*总集成中子通量/总积分中子通量 Total Integrated Neutron Flux = Integrated Flux or Fluence (注量) = Neutron density Velocity

8、Time 单位：n/m3 m/s s = n/m2 1.4. 反应堆压水堆 Pressurized Water Reactor (PWR)沸水堆 Boiling Water Reactor (BWR)加拿大重水铀反应堆（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

9、应堆 fast breeder reactor (FBR)轻水堆 Light Water Reactor (LWR)先进反应堆 advanced reactor超临界水反应堆 supercritical water reactor欧洲压水堆（第三代反应堆之一） European Pressurized water Reactor (EPR)（美国）先进压水堆600/1000（第三代(+)反应堆之一） AP(WR)600 / 10001.5. 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

10、架 spacer grid法兰 flange密封环 seal ring阻力塞 plug(上/下)腔室 (upper / lower ) plenum 堆芯，活性区 core反应堆压力容器 Reactor Pressure Vessel (RPV)上封头 upper closure head液压螺栓拉伸机(张紧机) hydraulic stud tensioner 包覆层 clad (碳钢表面的防腐蚀堆焊层)控制棒 control rod控制棒组件 Control Element Assembly (CEA)可燃吸收棒 burnable absorber rod控制棒驱动机构 Control E

11、lement Drive Mechanism (CEDM)变送器 transmitter信号调理 signal regulation吊篮 barrel进/出口接管 inlet / outlet nozzle冷/热端，冷/热腿，冷/热管段 cold / hot leg反应堆堆内构件 reactor vessel internals肿胀 swelling腐蚀 corrode, corrosion侵蚀 erode, erosion氧化 oxidation, oxidize完整性 integrity反应堆冷却剂泵（主泵） Reactor Coolant Pump (RCP)屏蔽泵 canned (mo

12、tor) pump轴封泵 shaft seal pump反应堆冷却剂系统（一回路系统）Reactor Coolant System (RCS)核蒸汽供应系统 Nuclear Steam Supply System (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汽水分离器 moisture separator干燥器（二/三级汽水分离器）steam dryer安全阀 safety valve卸压阀 relief valve溢流阀

13、 overflow valve主蒸汽隔离阀 main steam isolation valve单向阀 check valve止回阀 non-return valve主蒸汽联箱 main steam header 给水调节阀 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 Moisture Separator Reheater (MSR)给水泵 feed (water) pump上充泵 charging pump凝汽器 condenser发电机 (

14、electric) generator安全壳 containment地基，基础 foundation烟道 stack贯穿件 penetration核岛 nuclear island常规岛 conventional island核电厂配套子项 Balance of Plant (BOP)一回路辅助系统 auxiliary system for primary loop化学与容积控制系统（化容系统） Chemical and Volume Control System (CVCS)专设安全设施 Engineered Safety Feature (ESF)余热排出系统 Residual Heat-

15、Removal System (RHRS)应急堆芯冷却系统 Emergency Core Cooling System (ECCS),安注系统Safety Injection (SI) System直接注射系统 direct vessel injection (DVI)换料水箱 Refueling Water Storage Tank (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辅助喷淋 auxiliary spray柴油发电机 Diesel generat

16、or自动保护系统 Automatic Protective System (APS)自动降压系统 automatic depressurization system (ADS)仪控系统 Instrumentation and Control System (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 gland steam system汽轮机旁路管 turbine bypass line 辅助给水泵 auxiliary feedwater pump汽动给水泵 turbine driven feedwater pump 导管conduit冷

17、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 port1.6. 反应堆运行运行 operation运行工况 operating condition操纵员 operator维护 maintenance监督、监视surveillance 监督试样 surveillance specimen辐照监督管 irradiation surveillance capsule辐照监督试样盒 surveillance specimen compartm

18、ent硼浓度 boron concentration稀释 dilution / dilute硼注入boron injection停堆 shutdown紧急停堆 scram / trip停役 outage换料停堆 refueling outage / refueling shutdown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(控制棒等的)插入 insertion(控制棒等的)抽出 withdrawal反应堆调节系统

19、 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 and commissioning冷态试验 cold functional test热态试验 hot functional test(反应堆)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 pow

20、er distribution 轴向功率分布 axial power distribution燃料管理方案fuel management scheme燃料-包壳交互作用fuel-clad interaction effect芯块-包壳交互作用 (PCI) pellet-clad interaction(燃料)栅格、晶格 lattice 1.7. 反应堆安全核安全 nuclear safety安全功能 safety function衰变热 decay heat余热 residual heat空泡系数 void coefficient法律 law法规 regulation / code 联邦管理法

21、规 Code of Federal Regulations (CFR)法案（美） Act导则 guidance安全1/2/3级safety class 1/2/3可靠性 reliability容限，裕量，边界margin堆芯热裕量core thermal margin堵管裕量 tube plugging 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)确定论安全分

22、析 deterministic safety analysis初步安全分析报告 Preliminary Safety Analysis Report (PSAR)最终安全分析报告 Final Safety Analysis Report (FSAR)安全评价报告 safety evaluation report事件 incident事故 accident后果 consequence严重事故 severe accident堆芯损毁 core damage堆芯融化 core meltdown全厂断电 station blackout冷却剂丧失事故（失水事故）Loss-of-coolant Acci

23、dent (LOCA)反应性引入事故 Reactivity Insertion Accident (RIA)未能紧急停堆的预计瞬变 Anticipated Transient 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，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

24、diversity多层屏障 multiple barrier纵深防御 defense in depth潜热latent heat 焓，热函 sensible heat, enthalpy定期安全检查 periodic safety inspection许可证 license监管 regulation核安全准则 nuclear safety criteria三哩岛事故 Three Mile Island (TMI) accident切尔诺贝利事故 Chernobyl accident工作不正常，故障 malfunction失效 failure假设始发事件 postulated initiatin

25、g events事故工况 accident condition严重事故 severe accident事故处理 accident management设计基准事故 design basis accident负荷丧失事故 loss of electrical load accident主给水丧失事故 loss of main feed water accident卡棒事故 stuck rod accident弹棒事故 rod ejection accident堵管裕量 tube plugging margin管道甩摆限制 pipe whip restraint在役检查 inservice ins

26、pection承压热冲击 pressurized thermal shock1.8. 放射性与辐射防护radioactivity放射性scatter散射deflect, deflection折射衍射 diffraction穿透 penetrate, penetration交互作用 interact, interactionionization电离湮灭 annihilate (v.), annihilation (n.)衰减 attenuate(v.), attenuation(n.)projectile入射离子radiation protection辐射防护radiation, ray辐射，射

27、线irradiation辐照，（向外）辐射internal exposure内照射external exposure外照射occupational dose职业照射（剂量）fluence注量cosmic ray宇宙射线x-ray X射线a / b / g 射线 a / b / g rayhealth physics保健物理shielding屏蔽biological shield生物屏蔽剂量 dosedose equivalent剂量当量collective dose集体剂量individual dose个人剂量ingest, ingestion摄入，摄取inhale, inhalation吸入

28、coma昏迷cramp绞痛diarrhea腹泻tremor颤抖vomit呕吐somatic身体的 somatic effect躯体反应radiation sickness辐照病变symptom征兆therapy治疗survivor幸存者activation product活化产物effluent废水natural background天然本底sivert希弗spectrum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 (radioa

29、ctive) waste高放废物low-level (radioactive) waste低放废物1.9. 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 Commission (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In

30、ternational 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1.10. 其它术语1.10.1. 表示方向lateral横向longitudinal纵向radial径向perpendicular to垂直于vertically mounted垂直/立式安装circumferential环向axial轴向periphery周

31、边1.10.2. 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 swellingcavitation气蚀pitting点蚀/孔蚀crevice corrosion缝隙腐蚀erosion冲蚀FAC flow accelerated corrosion流动加速腐蚀wastage耗蚀 (SG tube) dent凹陷，凹痕fatigue疲劳ageing老化degradation降级wear磨损fretting wear微动磨损creep蠕变stress应力strain应变cre

32、ep 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-up welding, surface welding堆焊seal weld密封焊heat affected zone (HAZ) 焊接热影响区1.10.3. 核电工程术语procurement征购site厂址ca

33、ll 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不可更改的合同 subcontract分包合同commitment承诺，任务job site工地，工作现场technical requirement 技术要求技术规格 technical specification non-conformance不符合项delivery交货warehouse仓库construction schedule施工计划Free on Board (FOB) 离岸价

34、格Cost Insurance and Freight (CIF) 到岸价格Engineering, Procurement & Construction EPC合同-设计采购建造power grid电网distribution system输变电系统1.10.4. 其它compound化合物mixture混合物mass质量momentum动量energy能量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

35、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 prestressed reinforced concrete / prestressed concrete钢筋混凝土 reinforced concrete铁钢沙混凝土 Steel shot concret筋，钢筋束 tendon流量分配 flow di

36、stribution电网 power grid业主 utility承包商 contractor分包商 sub-contractor压降 pressure drop压差differential 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 Air Conditioning (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

37、轻，缓解 v. mitigate, n. mitigation公差、容差 allowance间隙，公差 clearance权重因子 weighting factor1.11. 有必要了解的词汇与短语as a rule of thumb根据经验by orders of magnitude以数量级incipient failure早期故障, 初期故障eliminate, elimination消除derive, derivation, deduce, deduction导出，起源mechanism, approach, principle, theory机理，原理susceptible敏感的sus

38、ceptibility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不可渗透的brittle fracture脆性破裂embrittlement脆化toughness韧性ductility延展性第2章 阅读理解题练习2.1. Passage 1As a result reactor designers have paid great attention to the inherent safety of reactors

39、which can be achieved by negative temperature and power coefficients and fail-safe control systems. It can be said with some confidence that present-day thermal reactors are safe in the sense that under no conceivable circumstance can they explode like a bomb, and control systems have been designed

40、which can, in the event of any malfunction on the part of the reactor or its associated plant, automatically and rapidly shut down the reactor, i.e. make it subcritical by a substantial amount, in a very few seconds.1. According to the paragraph, inherent safety of reactors can be achieved by . （C）A

41、. the operators;B. positive temperature and positive power coefficients;C. negative temperature and negative power coefficients;D. passive safety system and positive power coefficients.2. The best title of the passage may probably be . （D）A. fail-safe control system；B. thermal reactor safety and ope

42、ration;C. automatic protective system;D. inherent safety design of reactors.2.2. Passage IIThe biological shield should contain some hydrogen compound to slow down fast neutrons, and be dense enough to attenuate gamma radiation effectively. Concrete satisfies both these requirements fairly well and

43、is suitable for landbase reactors. Barytes (重晶石) concrete, containing the heavy element barium, and steel-shot concrete have been used for biological shields. They are more dense than ordinary concrete, with improved shielding properties, however their higher cost offsets this advantage. The biologi

44、cal shield for a marine reactor, which is usually a fairly compact pressurized water reactor, must satisfy a minimum space and weight requirement. This leads to a shield design which consists typically of alternate layers of water (for fast neutron slowing) and steel (for gamma ray attenuation).3. A

45、ccording to the above passage, is not possible for constructing biological shield? （C）A. steel; B. concrete;C. graphite; D. paraffin wax.4. Which of the following sentences is not true? （D）A. The biological shield is designed mainly to slow down fast neutrons and attenuate gamma radiation.B. The mar

46、ine reactor uses alternative steel and water layers as its biological shield.C. The combination of heavy element concrete and steel bars could improve the shielding properties.D. The biological shield should use hydrogen element to slow down fast neutron and attenuate gamma radiations.2.3. Passage I

47、IIIn order to mitigate the effects of large release of steam (an potentially of radioactivity) in the containment, two full capacity independent safety systems are provided; the reactor building spray system and the reactor building emergency coolers. The systems are designed to provide cool water t

48、o condense discharge steam and to prevent containment pressure from reaching its design limit. Individual systems differ considerably but a typical system may be described as follows; The initial capacity of the systems in removing heat from the containment atmosphere is typically 253GJ/hr.When a co

49、ntainment pressure of 4psig is reached, the emergency coolers of the reactor building are actuated. In their post accident mode, the system consists 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 i

50、s condensed. These coolers alone would be capable of returning the containment pressure to near atmospheric within 24 hr after an accident. When the pressure reaches a level of 10 psig, the second safety system, the reactor building spray system, is automatically actuated. It consists of a pump, pip

51、ing, headers, and spray nozzles arranged uniformly under the containment dome. It can spray borated water into the reactor building at a rate of 11.35m3/min. A sodium hydroxide additive is also provided in the spray water to increase the retention of iodine, and hence, to reduce its concentration in

52、 the containment atmosphere in the event of a sizable breach of fuel cladding.5. Two full capacity independent safety systems are provided for the design purpose of . （A）A. condensing the steam released into the containment when pressure exceeds design limit.B. maintaining the high pressure in the c

53、ontainmentC. discharging large amount of steam D. mitigating the effect of radiation hazard to the containment.6. The reactor building spray system will be actuated automatically . （C）A. after 24 hours after the accident;B. immediately after the accident;C. when the containment pressure reaches a le

54、vel of design limit;D. when the air in the containment is circulated through the heat exchanger. 7. Which of the following statements is INCORRECT? （B）A. The emergency cooler consists of fans and heat exchangers.B. The emergency cooler system can spray borated water into containment.C. All the two s

55、ystem are applied for returning the containment pressure to be blow atmospheric after the accident.D. Sodium hydroxide additive is provided in the spray water to reduce the amount of radioactive fission produces.2.4. Passage IVMany reactor-years of operating experience have shown that it is not 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