核电专业英语学习参考.doc

第1章 应知应会的单词与专业术语1.1. 原子核、核子及相关术语21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 neutron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 fissile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锆合金 zircaloy不锈钢 stainless steel控制材料 control material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 steel奥氏体不锈钢 austenitic stainless steel铁素体不锈钢 ferritic stainless steel马氏体不锈钢 martensitic stainless steel1.3. 核反应及相关术语衰变 decay裂变 fission聚变 fusion核反应 nuclear reaction链式反应 chain reaction截面 cross section微观截面 microscopic cross section宏观截面 macroscopic cross section吸收截面 absorbing cross section散射截面 scattering cross section靶恩 barn缓发中子 delayed neutron瞬发中子 prompt neutron瞬发临界 prompt criticality易裂变的 fissile可裂变的 fissionable慢化 morderate / slow down增殖比 breeding ratio燃耗 burnup反应性 reactivity中子循环 neutron cycle裂变产物 fission product临界 criticality瞬发临界 prompt critical通量 flux氙 xenon碘 iodine锕系（元素）actinide反应性价值 reactivity worth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 multiplication 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 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 Element 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 (motor) 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 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 (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-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 In-containment 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堆芯补水箱 core makeup tank蓄压箱 accumulator机组 unit辅助喷淋 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 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热电偶 thermocouple加热节点热电偶 heated junction thermocouple干簧管开关 reed switch流量限制器 flow restrictor节流孔版 orifice1.6. 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 compartment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 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 power 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积水垢 fouling 去污 cleansing(水的)净化 purify (v), purification (n)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 联邦管理法规 Code of Federal Regulations (CFR)法案（美） Act导则 guidance, guide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 Accident (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 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 initiating 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 inspection承压热冲击 pressurized thermal shock1.8. 放射性与辐射防护放射性 radioactivity散射 scatter折射 deflect, deflection衍射 diffraction穿透 penetrate, penetration交互作用 interact, interaction电离 ionization湮灭 annihilate (v.), annihilation (n.)衰减 attenuate(v.), attenuation(n.)入射离子 projectile辐射防护 radiation protection辐射，射线 radiation, ray辐照，（向外）辐射 irradiation内照射 internal exposure外照射 external exposure职业照射（剂量） occupational dose注量 fluence宇宙射线 cosmic rayX射线 x-raya / b / g 射线 a / b / g ray保健物理 health physics屏蔽 shielding生物屏蔽 biological shield剂量 dose剂量当量 dose equivalent集体剂量 collective dose个人剂量 individual dose摄入，摄取 ingest, ingestion吸入 inhale, inhalation昏迷 coma绞痛 cramp腹泻 diarrhea颤抖 tremor呕吐 vomit身体的 somatic 躯体反应 somatic effect辐照病变 radiation sickness 征兆 symptom治疗 therapy幸存者 survivor活化产物 activation product废水 effluent天然本底 natural background希弗 sivert谱 spectrum雷姆 rem氡 radon合理可行尽量低 as low as reasonably achievable (ALARA)放射性废物处理 radioactive waste disposal高放废物 high-level (radioactive) waste低放废物 low-level (radioactive) waste1.9. 有关机构国际原子能机构 International Atomic Energy Agency (IAEA)美国机械工程师学会 American Society of Mechanical Engineers (ASME)美国核管会 Nuclear Regulatory Commission (NRC/USNRC)美国能源部 Department Of Energy (DOE)世界核电运营者协会 World Association of Nuclear Operators (WANO)国际辐射防护委员会 International Commission on Radiological Protection (ICRP)中国国家原子能机构 China Atomic Energy Authority （CAEA）国家环保总局 State Environment Protection Administration of China1.10. 其它术语1.10.1. 表示方向横向 lateral纵向 longitudinal径向 radial垂直于 perpendicular to垂直/立式安装 vertically mounted环向 circumferential轴向 axial周边 periphery1.10.2. 材料术语腐蚀 corrosion应力腐蚀开裂 stress corrosion cracking断裂 rapture, fracture, break破口 breach肿胀 swelling气蚀 cavitation点蚀/孔蚀 pitting缝隙腐蚀 crevice corrosion冲蚀 erosion流动加速腐蚀FAC flow accelerated corrosion耗蚀 wastage 凹陷，凹痕(SG tube) dent疲劳 fatigue老化 ageing降级 degradation磨损 wear微动磨损 fretting wear蠕变 creep应力 stress应变 strain蠕变强度 creep strength抗拉强度 tensile strength屈服强度 yield strength断裂强度 rapture strength断裂韧性 fracture toughness零延性转变温度nil-ductility transition temperature 基准性能 baseline property热应力 thermal stress辐照肿胀 irradiation swelling焊接 weld堆焊 deposit welding, overlaying, build-up welding, surface welding密封焊 seal weld对接焊 butt weld焊缝 weld seam焊接热影响区 heat affected zone (HAZ)锻造 forge锻件 forging1.10.3. 核电工程术语征购 procurement安装 erection调试 commissioning厂址 site招标 call for bid, call for tender商务标 commercial offer 技术标 technical offer开工 commencement合同 contract 不可更改的合同 firm contract 分包合同 subcontract承诺，任务 commitment工地，工作现场 job site技术要求 technical requirement 技术规格 technical specification不符合项 non-conformance交货 delivery仓库 warehouse施工计划 construction schedule离岸价格 Free on Board (FOB)到岸价格 Cost Insurance and Freight (CIF) EPC合同-设计采购建造，Engineering, Procurement & Construction电网 power grid输变电系统 distribution system 1.10.4. 其它化合物 compound混合物 mixture质量 mass动量 momentum能量 energy势能 potential (energy)动能 kinetic energy惯性 inertia半衰期 half-life平均自由程mean free path燃料循环 fuel cycle热点 hot spot热管因子 hot-channel factor偏离泡核沸腾比 departure from nucleate boiling ratio (DNBR)传热 heat transfer换热器 heat exchanger导热 heat conduction对流 convection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 concrete筋，钢筋束 tendon流量分配 flow distribution电网 power grid公共事业，业主 utility业主 owner承包商 contractor分包商 sub-contractor压降 pressure drop压差differential pressure水位 (water) level水位指示 level indication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根据经验 as a rule of thumb以数量级 by orders of magnitude早期故障, 初期故障 incipient failure 消除 eliminate, elimination导出，起源 derive, derivation, deduce, deduction机理，原理 mechanism, approach, principle, theory敏感的 susceptible 敏感性 susceptibility有毒的 toxic急剧的 acute遗传 inherit遗传性的 hereditary高度 altitude假定，假设 postulate, postulation可渗透的, 有渗透性的 permeable不可渗透的 impermeable脆性破裂 brittle fracture脆化 embrittlement韧性 toughness延展性 ductility1.12. AP1000核电厂相关术语非能动余热导出系统 passive decay heat removal system爆破阀 squib valve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 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 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. 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 operation;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 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 biological 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. According 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 marine 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 IIIIn 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 to 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 containment 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 is 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, piping, 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 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 containmentC. 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 level of design limit;D. when the air in the containment is circulated through the he