核电专业英语学习(必考)

1、第1章应知应会的单词与专业术语原子核、核子及相关术语质子proton屮子 neutron电子 electron核子 nucleon核 nucleus (pi.) nuclei原子atom光子photon正电子positron量子 quantum，quanta (pi.)电子伏特 electron-volt (ev)相关元素与材料2.1. 核燃料与増殖材料铀 uranium (u)环 plutonium (pu)気，車氯 deuterium，heavy hydrogen 氣 tritium浞合氧化物燃料(mox燃料)mixed (uranium and plutonium) oxide fuel

2、 二氧化铀 uranium dioxide 浓缩铀 enriched uranium 贫铀 depleted uranium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热屮子 thermal neutron快中子 fast neutron复合核 compound nucleus碳化铀 uranium carbide 针.thorium 锂 lithium锕系元素 actinide element 易裂变的fi

3、ssile可裂变的、可裂变物质fissionable 增殖同位素fertile isotope 核嬗变 nuclear transmutation 转化 conversion2.2. 其它核材料及核电厂用材料慢化剂moderator 轻水 light water 熏水 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 务ft zirconium 错合金zircaloy 不锈钢 stainless steel控制材料 control mater

4、ial 通 s:展 t flux-shaping 银 silver铟 indium铜 cadmium可燃毒物 burnable poison 硼 boron 硼酸 boric acid 锂 lithium 铍 beryllium核反应及相关术语哀变decay裂变 fission聚变fusion核反应 nuclear reaction链式反应 chain reaction截而 cross section微观截 lif microscopic cross section宏观截而 macroscopic cross section吸收截ill absorbing cross section散射截面

5、scattering cross section靶恩barn缓发屮子 delayed neutron 瞬发屮子 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bum up反应性 reactivity屮子循环neutron cycle裂变产物 fission product 临界 criticality 瞬发临界 prompt critical 通量flux m xenon反应堆乏燃料spent fuel因科

6、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 steel碘 iodine锕系（元素）actinide反应性价位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

7、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i曾殖系数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 probabili

8、ty四因子公式 four-factor formula 多普勒增宽 doppler broadening *总集成屮子通量/总积分屮子通量total integrated neutron flux = integrated flux or fluence （'注量）=neutron density x velocity x time 单位：n/m' m/s s = n/m2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 u

9、ranium reactor (candu) / pressurized heavy water reactor (phwr)英国7气冷堆(美诺克斯堆)british gas-cooled magnox reactor 高温气，冷堆 high temperature gas-cooled reactor (htgr)快屮子增殖反应堆fast breeder reactor (fbr)较水堆 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)europe

10、an pressurized water reactor (epr)(美国)先进压水堆600/1000 (第三代(+)反应堆之一)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 / 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

11、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恰号调理 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 in

12、ternals 肿胀 swelling腐蚀 corrode, corrosion侵蚀 erode, erosion氧化 oxidation, oxidize完整性integrity反应堆冷却剂粟(i粟)reactor coolant pump (rcp)屏蔽泵 canned (motor) pump轴封泉 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 冋路系统/主冋路系统primary syst

13、em 二回路 secondary loop 稳压器 pressurizer (prz)波动管surge line汽水分离器 moisture separator干操器(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止冋阀 non-return valve主蒸汽联箱 main steam header给水调w 阀 feed regulating valve 蒸汽发生器 steam generator (sg

14、)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上充粟 charging pump凝汽器condenser发电机(electric) generator安全壳 containment地基，基础foundation烟道slack贯穿件 penetration核岛 nuclear island常规岛 conventional island核电)配套子项 balance of plant (bop)一回路辅助系统 auxiliary sy

15、stem 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 (dv1)换料水箱 in-containment refuelin

16、g water storage tank (irwst)反应堆运行运行 operation运 jr工况 operating condition操纵员operator (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向动保右1 系统 automatic protective system (aps)自动降压系统 automatic depressuriz

17、ation system (ads)仪控系统 instrumentation and control system (i & c system)开关设备，开关杞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 辅助给水聚 auxiliary feedwater pump 汽动给水泉 turbine driven feedwater pump 导管 conduit冷凝水聚 condensate pump冷凝水增压聚 condensate booster pump 水润滑轴承 water lubri

18、cated bearing 人孔man way检修孑l accessory port热电偶 thermocouple加热节点热电偶 heated junctionthermocouple干簧管7t关 reed switch流量限制器flow restrictor节流孔版orifice维护 maintenance监齊、监视 surveillance 监督试样 surveillance specimen福照监督管 irradiation surveillance capsule 福照监督试样盒surveillance specimen compartment硼浓度 boron concentrat

19、ion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 / refuelingshutdown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反座堆调节系统 reactor regulating system(r

20、rs)(蒸汽发生器)排污、下泄blowdown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联邦宵理法规 code of federal regulations (cfr)法案(美)act导贝ij guidance, guide安全 1/2/3 级 safety class 1/2/3可龍性 reliability界限，裕量，边界margin堆芯热裕量 core thermal margin规程 proce

21、dure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 f

22、uel 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 fouling去污 cleansing(水的)净化 purify (v)，purification (n)堵管裕量 tube plugging margin运行女全裕us: operating margin标准，准则criterion，复数形式:criteria 概率安企分析 probabilistic safety analysis (psa)概率风险分析 pro

23、babilistic risk analysis (pra)确定论安金分析 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)安企评价报告 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j 断电 station blacko

24、ut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

25、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(

26、n.)入射离子projectile辐射防护 radiation protection福射，射线 radiation, ray辐照，(向外)福射irradiation 熔，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 p

27、ostulated initiating events 事古女工况 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 electricalloadaccident主给水丧失事故 loss of mainfeedwater accident 卡棒事故 stuck rod accident 弾棒事故 rod ejection accident 堵管裕量 tube plugging margin 管道甩摆限制pipe whip res

28、traint 在役检查 inservice inspection 承压招q中击 pressurized thermal shock内照射 internal exposure外照射 external exposure职业照射(剂量)occupational dose注量 fluence与7胃身寸会cosmic rayx射线x-raya/ys/射线 a! p! /ray保健物理 health physics屏蔽 shielding生物屏蔽 biological shield剂量dose剂量3量 dose equivalent集体剂量 collective dose个人剂量 individual d

29、ose 摄入，摄取 ingest，ingestion 吸入 inhale，inhalation g迷 coma绞痛cramp腹'汚 diarrhea颤抖tremor卩区吐vomit身体的somatic躯体反皮 somatic effect 辐照病变 radiation sickness 征9匕 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si vert谱 spectrum雷姆remm radon合理可行尽量低 as low as reasonably ach

30、ievable (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) waste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 ene

31、rgy (doe)世界核电运营者协会 world association of nuclear operators (wano)m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 china其它术语表示方向横向 lateral纵向 longitudinal径向radial垂立于 perpendicular to材

32、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垂直/立式安装vertically mounted l4 circumferential轴向axial周边 periphery缝隙腐蚀 crevice corrosion冲蚀 erosion流动加速腐蚀fac flow acceleratedcorrosion棘蚀 wastage凹陷，凹娘(sg tube) dent疲劳 fatigue老化ageing降级

33、degradation磨损wear微动磨损fretting wear蠟变creep应力stress泣变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断裂朗性 fracture toughness零延性转变温度 nil-ductility transition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

34、technical offerjpl commencement合同 contract不可更改的合同firm contract分包合同subcontract承诺，任务commitmentt地，丁.作现场job site其它化合物compound混合物mixturej贡量mass动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 temperature基准性能 baseline property热应力 thermal stress

35、辐照肿胀 irradiation swelling焊接weld堆焊 deposit welding，overlaying, build-upwelding, surface welding密封焊seal weld对接焊butt weld捍缝 weld seam煌接热影响区 heat affected zone (haz)锻造forge 锻件 forging技术要求 technical requirement技术规格 technical specification non-conformance交货 delivery仓痺 warehouse工计划 construction schedule离岸价

36、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输變电系统 distribution system热点 hot spot热管因子 hot-channel factor偏离池核沸腾比departure from nucleate boiling ratio (dnbr)传热 heat transfer换热器 heat exchanger导热 heat conduction对流 convecti

37、on热福射 thermal / heat radiation干度 quality蒸汽steam预应力钢筋混凝土 prestressed reinforcedconcrete / prestressed concrete钢筋泥凝土 reinforced concrete铁钢沙混凝土 steel shot concrete筋，钢筋束tendon流m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

38、位(water) level水位指示 level indication有必要了解的词汇与短语根据经验 as a rule of thumb以数 w:级 by orders of magnitude早期故障，初期故障incipient failure十肖除 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toxicap1000核电厂相关术语规定，条款；保障；装备pro

39、vision 地震 earthquake 地震的seismic 嫩风 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，缓角军 v. mitigate, n. mitigation 公差、容差allowance 间隙，公差clearance 权重因子 weighting factor急剧的acute遗传 inherit遗传性的hereditary高度 altitude假定，假

40、设 postulate, postulation nj漆透的，有渗透性的permeable 不可滲透的impermeable 脆性破裂 brittle fracture 脆化 embrittlement初性 toughness延展性ductilityii:能动余热导山系统 passive decay heat removal system 爆破阀 squib valve第2章阅读理解题练习passage 1as a result reactor designers have paid great attention to the inherent safetyof reactors which

41、 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

42、 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.1.1. according to the paragraph, inherent safety of reactors can be achievedbya> the op

43、erators;a. positive temperature and positive power coefficients;b. negative temperature and negative power coefficients;d> passive safety system and positive power coefficients.1.2. the best title of the passage may probably be.a> fail-safe control system ；be thermal reactor safety and operati

44、on;automatic protective system;c. inherent safety design of reactors.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

45、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 fo

46、r 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).1.3. according to

47、the above passage, is not possible forconstructing biological shield?a> steel;b. concrete;1.4. which of the following sentences is not true? the biological shield is designed mainly to slow down fast neutrons and attenuate gamma radiation.be the marine reactor uses alternative steel and water lay

48、ers as its biological shield.a. the combination of heavy element concrete and steel bars could improve the shielding properties.1. the biological shield should use hydrogen element to slow down fast neutron and attenuate gamma radiations.passage iiiin order to mitigate the effects of large release o

49、f 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

50、 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 emerge

51、ncy 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

52、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 t

53、he containment dome. it can spray borated water into the reactor building at a rate of ll35m3/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 bre

54、ach of fuel cladding.1.5. two full capacity independent safety systems are provided for the designpurpose ofa> condensing the steam released into the containment when pressureexceeds design limitbe maintaining the high pressure in the containmentc. discharging large amount of steamde mitigating t

55、he effect of radiation hazard to the containment.1.6. the reactor building spray system will be actuatedautomatically .a. after 24 hours after the accident; immediately after the accident;c. when the containment pressure reaches a level of design limit;(1) when the air in the containment is circulat

56、ed through the heat exchanger.1.7. which of the following statements is incorrect? 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 system are applied for returning the containment pressure to be bl

57、ow atmospheric after the accident.de sodium hydroxide additive is provided in the spray water to reduce the amount of radioactive fission produces.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 an