核電專業(yè)英語學(xué)習(xí)(必考)

1、第1章應(yīng)知應(yīng)會(huì)的單詞與專業(yè)術(shù)語原子核、核子及相關(guān)術(shù)語質(zhì)子proton屮子 neutron電子 electron核子 nucleon核 nucleus (pi.) nuclei原子atom光子photon正電子positron量子 quantum，quanta (pi.)電子伏特 electron-volt (ev)相關(guān)元素與材料2.1. 核燃料與増殖材料鈾 uranium (u)環(huán) 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、 二氧化鈾 uranium dioxide 濃縮鈾 enriched uranium 貧鈾 depleted uranium兆電子伏特 mega electron-volt (mev)同位素isotope原子序數(shù)atomic number質(zhì)量數(shù) mass number超鈾元素 transuranium element元素周期表periodic table熱屮子 thermal neutron快中子 fast neutron復(fù)合核 compound nucleus碳化鈾 uranium carbide 針.thorium 鋰 lithium錒系元素 actinide element 易裂變的fi

3、ssile可裂變的、可裂變物質(zhì)fissionable 增殖同位素fertile isotope 核嬗變 nuclear transmutation 轉(zhuǎn)化 conversion2.2. 其它核材料及核電廠用材料慢化劑moderator 輕水 light water 熏水 heavy water 石墨 graphite冷卻劑coolant 氦 helium液態(tài)金屬liquid metal 鈉 sodium包殼 cladding鋁 aluminium 鎂 magnesium 務(wù)ft zirconium 錯(cuò)合金zircaloy 不銹鋼 stainless steel控制材料 control mater

4、ial 通 s:展 t flux-shaping 銀 silver銦 indium銅 cadmium可燃毒物 burnable poison 硼 boron 硼酸 boric acid 鋰 lithium 鈹 beryllium核反應(yīng)及相關(guān)術(shù)語哀變decay裂變 fission聚變fusion核反應(yīng) nuclear reaction鏈?zhǔn)椒磻?yīng) chain reaction截而 cross section微觀截 lif microscopic cross section宏觀截而 macroscopic cross section吸收截ill absorbing cross section散射截面

5、scattering cross section靶恩barn緩發(fā)屮子 delayed neutron 瞬發(fā)屮子 prompt neutron 瞬發(fā)臨界 prompt criticality 易裂變的fissile 可裂變的fissionable '慢化 morderate / slow down 增殖比 breeding ratio 燃耗bum up反應(yīng)性 reactivity屮子循環(huán)neutron cycle裂變產(chǎn)物 fission product 臨界 criticality 瞬發(fā)臨界 prompt critical 通量flux m xenon反應(yīng)堆乏燃料spent fuel因科

6、鎳，因康inconel不銹鋼 stainless steel奧氏體不銹鋼 austenitic stainless steel 鐵素體不銹鋼 ferritic stainless steel 馬氏體不銹鋼 martensitic stainless steel碘 iodine錒系（元素）actinide反應(yīng)性價(jià)位reactivity worth慢 化 劑 溫 度 系 數(shù) moderator temperature coefficient 反應(yīng)性系數(shù) reactivity coefficient 剩余反應(yīng)性 excess reactivity 燃料比功率 fuel specific power

7、倍增因子 multiplication factor 有效增殖系數(shù) effective multiplication factor； effective multiplication constant 無限介質(zhì)增殖系數(shù)infinite multiplication factor； infinite multiplication constant 快中子i曾殖系數(shù)fast fission factor 熱中子利用系數(shù) thermal utilization factor不泄漏幾率 nonleakage probability 逃脫共振俘獲幾率 resonance escape probabili

8、ty四因子公式 four-factor formula 多普勒增寬 doppler broadening *總集成屮子通量/總積分屮子通量total integrated neutron flux = integrated flux or fluence （'注量）=neutron density x velocity x time 單位：n/m' m/s s = n/m2壓水堆 pressurized water reactor （pwr）沸水堆 boiling water reactor (bwr)加拿大重水鈾反應(yīng)堆(坎杜堆)canadian deuterium and u

9、ranium reactor (candu) / pressurized heavy water reactor (phwr)英國7氣冷堆(美諾克斯堆)british gas-cooled magnox reactor 高溫氣，冷堆 high temperature gas-cooled reactor (htgr)快屮子增殖反應(yīng)堆fast breeder reactor (fbr)較水堆 light water reactor (lwr)先進(jìn)反應(yīng)堆a(bǔ)dvanced reactor 超臨界水反應(yīng)堆 supercritical water reactor歐洲壓水堆(第三代反應(yīng)堆之一)europe

10、an pressurized water reactor (epr)(美國)先進(jìn)壓水堆600/1000 (第三代(+)反應(yīng)堆之一)ap(wr)600/ 1000核電廠部件、設(shè)備與系統(tǒng)燃料芯塊fuel pellet燃料元件fuel element燃料棒fuel rod燃料組件fuel assembly定位格架spacer grid法蘭flange密封環(huán)seal ring阻力塞plug(上/下)腔室(upper / lower ) plenum 堆芯，活性區(qū)core反應(yīng)堆壓力容器reactor pressure vessel (rpv)上封頭 upper closure head液壓螺栓拉伸機(jī)(張

11、緊機(jī))hydraulic stud tensioner包覆層clad (碳鋼表面的防腐蝕堆焊層) 控制棒 control rod控制棒組件 control element assembly (cea)可燃吸收棒 burnable absorber rod 控制棒驅(qū)動(dòng)機(jī)構(gòu)control element drive mechanism (cedm)變送器 transmitter恰號(hào)調(diào)理 signal regulation吊籃barrel進(jìn)/出 口接管 inlet / outlet nozzle冷/熱端，冷/熱腿，冷/熱管段cold/hot leg 反應(yīng)堆堆內(nèi)構(gòu)件 reactor vessel in

12、ternals 腫脹 swelling腐蝕 corrode, corrosion侵蝕 erode, erosion氧化 oxidation, oxidize完整性integrity反應(yīng)堆冷卻劑粟(i粟)reactor coolant pump (rcp)屏蔽泵 canned (motor) pump軸封泉 shaft seal pump反應(yīng)堆冷卻劑系統(tǒng)(一回路系統(tǒng))reactor coolant system (rcs)核蒸汽供應(yīng)系統(tǒng)nuclear steam supply system (nsss)一回路 primary loop/circuit 冋路系統(tǒng)/主冋路系統(tǒng)primary syst

13、em 二回路 secondary loop 穩(wěn)壓器 pressurizer (prz)波動(dòng)管surge line汽水分離器 moisture separator干操器(二/三級(jí)汽水分離器)steam dryer安全閥 safety valve卸壓閥 relief valve溢流閥 overflow valve主蒸汽隔離閥 main steam isolation valve單向閥 check valve止冋閥 non-return valve主蒸汽聯(lián)箱 main steam header給水調(diào)w 閥 feed regulating valve 蒸汽發(fā)生器 steam generator (sg

14、)主蒸汽管 main steam line (msl)汽輪機(jī) steam turbine汽水分離再熱器 moisture separator reheater (msr)給水泵 feed (water) pump上充粟 charging pump凝汽器condenser發(fā)電機(jī)(electric) generator安全殼 containment地基，基礎(chǔ)foundation煙道slack貫穿件 penetration核島 nuclear island常規(guī)島 conventional island核電)配套子項(xiàng) balance of plant (bop)一回路輔助系統(tǒng) auxiliary sy

15、stem for primary loop化學(xué)與容積控制系統(tǒng)(化容系統(tǒng))chemical and volume control system (cvcs)專設(shè)安全設(shè)施 engineered safety feature (esf)余熱排出系統(tǒng) residual heat-removal system (rhrs)應(yīng)急堆芯冷卻系統(tǒng)emergency core cooling system (eccs),安注系統(tǒng) safety injection (si) system 直接注射系統(tǒng) direct vessel injection (dv1)換料水箱 in-containment refuelin

16、g water storage tank (irwst)反應(yīng)堆運(yùn)行運(yùn)行 operation運(yùn) jr工況 operating condition操縱員operator (乏)燃料貯存水池(spent) fuel storage pool 燃料裝卸系統(tǒng)fuel handling system 堆芯補(bǔ)水箱 core makeup tank 蓄壓箱 accumulator機(jī)組unit輔助噴淋 auxiliary spray柴油發(fā)電機(jī)diesel generator向動(dòng)保右1 系統(tǒng) automatic protective system (aps)自動(dòng)降壓系統(tǒng) automatic depressuriz

17、ation system (ads)儀控系統(tǒng) instrumentation and control system (i & c system)開關(guān)設(shè)備，開關(guān)杞switch gear 蒸汽軸封系統(tǒng)，壓蓋蒸汽密封系統(tǒng)gland steam system汽輪機(jī)旁路管turbine bypass line 輔助給水聚 auxiliary feedwater pump 汽動(dòng)給水泉 turbine driven feedwater pump 導(dǎo)管 conduit冷凝水聚 condensate pump冷凝水增壓聚 condensate booster pump 水潤滑軸承 water lubri

18、cated bearing 人孔man way檢修孑l accessory port熱電偶 thermocouple加熱節(jié)點(diǎn)熱電偶 heated junctionthermocouple干簧管7t關(guān) reed switch流量限制器flow restrictor節(jié)流孔版orifice維護(hù) maintenance監(jiān)齊、監(jiān)視 surveillance 監(jiān)督試樣 surveillance specimen福照監(jiān)督管 irradiation surveillance capsule 福照監(jiān)督試樣盒surveillance specimen compartment硼濃度 boron concentrat

19、ion稀釋 dilution / dilute硼注入 boron injection停堆 shutdown緊急停堆scram / trip停役outage換料停堆 refueling outage / refuelingshutdown換料refuel卸料 discharge倒料 shuffling滿功率運(yùn)行 full power operation負(fù)荷跟蹤 load following甩負(fù)荷 load shedding, load rejection(控制棒等的)插入insertion(控制棒等的)抽出withdrawal反座堆調(diào)節(jié)系統(tǒng) reactor regulating system(r

20、rs)(蒸汽發(fā)生器)排污、下泄blowdown反應(yīng)堆安全核安全 nuclear safety安全功能 safety function衰變熱decay heat余熱 residual heat空泡系數(shù) void coefficient法律law法規(guī) regulation / code聯(lián)邦宵理法規(guī) code of federal regulations (cfr)法案(美)act導(dǎo)貝ij guidance, guide安全 1/2/3 級(jí) safety class 1/2/3可龍性 reliability界限，裕量，邊界margin堆芯熱裕量 core thermal margin規(guī)程 proce

21、dure技術(shù)規(guī)格 technical specification瞬態(tài)，瞬變transient安裝調(diào)試 installation and commissioning 冷態(tài)試驗(yàn) cold functional test 熱態(tài)試驗(yàn) hot functional test (反應(yīng)堆)啟動(dòng)試驗(yàn)(reactor) start up test 退役 decommissioning 主控室 main control room 方位角偏差azimuthal tilt 徑向功率分布 radial power distribution 軸向功率分布 axial power distribution 燃料管理方案 f

22、uel management scheme 燃料-包殼交互作用fuel-clad interaction effect芯塊-包殼交互作用(pci) pellet-clad interaction(燃料)柵格、晶格lattice積水 fouling去污 cleansing(水的)凈化 purify (v)，purification (n)堵管裕量 tube plugging margin運(yùn)行女全裕us: operating margin標(biāo)準(zhǔn)，準(zhǔn)則criterion，復(fù)數(shù)形式:criteria 概率安企分析 probabilistic safety analysis (psa)概率風(fēng)險(xiǎn)分析 pro

23、babilistic risk analysis (pra)確定論安金分析 deterministic safety analysis初步安全分析報(bào)告preliminary safety analysis report (psar)最終安全分析報(bào)告final safety analysis report (fsar)安企評(píng)價(jià)報(bào)告 safety evaluation report 事件 incident事故 accident后果 consequence嚴(yán)重事故 severe accident堆芯損毀core damage堆芯融化 core meltdown全j 斷電 station blacko

24、ut冷卻劑喪失事故(失水事故)loss-of-coolant accident (loca)反應(yīng)性引入事故 reactivity insertion accident (ria)未能緊急停堆的預(yù)計(jì)瞬變anticipated transient without scram (atws)失電 loss of power失流 loss of flow先漏后破 leak before break (lbb)故障安全，失效保護(hù)fail-safe 單一故障準(zhǔn)則 single-failure criterion 共因故障 common cause failure 固有安全性inherent safety 非

25、能動(dòng)安全passive safety 冗余性 redundancy 多樣性diversity多層屏障 multiple barrier縱深防御 defense in depth潛熱 latent heat放射性與輻射防護(hù)放射性 radioactivity散射 scatter折射 deflect, deflection衍射 diffraction穿透 penetrate，penetration交互作用 interact，interaction電離 ionization湮滅 annihilate (v.)，annihilation (n.)衰減 attenuate(v.)，attenuation(

26、n.)入射離子projectile輻射防護(hù) radiation protection福射，射線 radiation, ray輻照，(向外)福射irradiation 熔，熱函 sensible heat, enthalpy定期安全檢查 periodic safety inspection 許可證license 監(jiān)/管 regulation核安全準(zhǔn)則 nuclear safety criteria三哩島事故 three mile island (tmi)accident切爾諾貝利事故chernobyl accident 工作不正常，故障malfunction 失效 failure假設(shè)始發(fā)事件 p

27、ostulated initiating events 事古女工況 accident condition 嚴(yán)重事故 severe accident 事故處理 accident management 設(shè)計(jì)基準(zhǔn)事故 design basis accident 負(fù)荷喪失事故 loss of electricalloadaccident主給水喪失事故 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 管道甩擺限制pipe whip res

28、traint 在役檢查 inservice inspection 承壓招q中擊 pressurized thermal shock內(nèi)照射 internal exposure外照射 external exposure職業(yè)照射(劑量)occupational dose注量 fluence與7胃身寸會(huì)cosmic rayx射線x-raya/ys/射線 a! p! /ray保健物理 health physics屏蔽 shielding生物屏蔽 biological shield劑量dose劑量3量 dose equivalent集體劑量 collective dose個(gè)人劑量 individual d

29、ose 攝入，攝取 ingest，ingestion 吸入 inhale，inhalation g迷 coma絞痛cramp腹'汚 diarrhea顫抖tremor卩區(qū)吐vomit身體的somatic軀體反皮 somatic effect 輻照病變 radiation sickness 征9匕 symptom治療 therapy幸存者survivor活化產(chǎn)物 activation product廢水 effluent天然本底 natural background希弗si vert譜 spectrum雷姆remm radon合理可行盡量低 as low as reasonably ach

30、ievable (alara)放射性廢物處理 radioactive waste disposal 高放廢物 high-level (radioactive) waste 低放廢物 low-level (radioactive) waste有關(guān)機(jī)構(gòu)國際原子能機(jī)構(gòu) international atomic energy agency (iaea)美國機(jī)械工程師學(xué)會(huì) american society of mechanical engineers (asme)美國核管會(huì) nuclear regulatory commission (nrc/usnrc)美國能源部 department of ene

31、rgy (doe)世界核電運(yùn)營者協(xié)會(huì) world association of nuclear operators (wano)m際輻射防護(hù)委員會(huì) international commission on radiological protection (icrp) 中國國家原子能機(jī)構(gòu) china atomic energy authority (caea)國家環(huán)保總局 state environment protection administration of china其它術(shù)語表示方向橫向 lateral縱向 longitudinal徑向radial垂立于 perpendicular to材

32、料術(shù)語腐蝕 corrosion應(yīng)力腐蝕開裂 stress corrosion cracking 斷裂 rapture, fracture，break 破口 breach腫脹 swelling氣蝕 cavitation點(diǎn)蝕/孔蝕pitting垂直/立式安裝vertically mounted l4 circumferential軸向axial周邊 periphery縫隙腐蝕 crevice corrosion沖蝕 erosion流動(dòng)加速腐蝕fac flow acceleratedcorrosion棘蝕 wastage凹陷，凹娘(sg tube) dent疲勞 fatigue老化ageing降級(jí)

33、degradation磨損wear微動(dòng)磨損fretting wear蠟變creep應(yīng)力stress泣變strain蠕變強(qiáng)度 creep strength抗拉強(qiáng)度 tensile strength屈服強(qiáng)度 yield strength斷裂強(qiáng)度 rapture strength斷裂朗性 fracture toughness零延性轉(zhuǎn)變溫度 nil-ductility transition核電工程術(shù)語征購 procurement安裝 erection調(diào)試 commissioning廠址site招標(biāo) call for bid，call for tender商務(wù)標(biāo) commercial offer技術(shù)標(biāo)

34、technical offerjpl commencement合同 contract不可更改的合同firm contract分包合同subcontract承諾，任務(wù)commitmentt地，丁.作現(xiàn)場job site其它化合物compound混合物mixturej貢量mass動(dòng)momentum能量energy勢(shì)能 potential (energy)動(dòng)能 kinetic energy慣性 inertia半衰期half-life平均自由程mean free path燃料循環(huán)fuel cycle temperature基準(zhǔn)性能 baseline property熱應(yīng)力 thermal stress

35、輻照腫脹 irradiation swelling焊接weld堆焊 deposit welding，overlaying, build-upwelding, surface welding密封焊seal weld對(duì)接焊butt weld捍縫 weld seam煌接熱影響區(qū) heat affected zone (haz)鍛造forge 鍛件 forging技術(shù)要求 technical requirement技術(shù)規(guī)格 technical specification non-conformance交貨 delivery倉痺 warehouse工計(jì)劃 construction schedule離岸價(jià)

36、格 free on board (fob)到岸價(jià)格 cost insurance and freight (cif) epc合同設(shè)計(jì)采購建造，engineering, procurement & construction電網(wǎng) power grid輸變電系統(tǒng) distribution system熱點(diǎn) hot spot熱管因子 hot-channel factor偏離池核沸騰比departure from nucleate boiling ratio (dnbr)傳熱 heat transfer換熱器 heat exchanger導(dǎo)熱 heat conduction對(duì)流 convecti

37、on熱福射 thermal / heat radiation干度 quality蒸汽steam預(yù)應(yīng)力鋼筋混凝土 prestressed reinforcedconcrete / prestressed concrete鋼筋泥凝土 reinforced concrete鐵鋼沙混凝土 steel shot concrete筋，鋼筋束tendon流m分配 flow distribution電網(wǎng) power grid公共事業(yè)，業(yè)主utility業(yè)主owner承包商 contractor分包商 sub-contractor壓降 pressure drop壓差 differential pressure水

38、位(water) level水位指示 level indication有必要了解的詞匯與短語根據(jù)經(jīng)驗(yàn) as a rule of thumb以數(shù) w:級(jí) by orders of magnitude早期故障，初期故障incipient failure十肖除 eliminate，elimination導(dǎo)出，起源 derive, derivation，deduce，deduction機(jī)理，原理 mechanism，approach，principle, theory敏感的 susceptible敏感性 susceptibility有毒的toxicap1000核電廠相關(guān)術(shù)語規(guī)定，條款；保障；裝備pro

39、vision 地震 earthquake 地震的seismic 嫩風(fēng) tornado暖通空調(diào) heating, ventilation and air conditioning (hvac)熱阱 heat sink 惰轉(zhuǎn) coastdown 惰轉(zhuǎn)流量 coastdown flow 功率失常激增，功率漂移power excursion 減輕，緩角軍 v. mitigate, n. mitigation 公差、容差allowance 間隙，公差clearance 權(quán)重因子 weighting factor急劇的acute遺傳 inherit遺傳性的hereditary高度 altitude假定，假

40、設(shè) postulate, postulation nj漆透的，有滲透性的permeable 不可滲透的impermeable 脆性破裂 brittle fracture 脆化 embrittlement初性 toughness延展性ductilityii:能動(dòng)余熱導(dǎo)山系統(tǒng) passive decay heat removal system 爆破閥 squib valve第2章閱讀理解題練習(xí)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