1、精選優(yōu)質(zhì)文檔-傾情為你奉上1.1. 原子核、核子及相關(guān)術(shù)語(yǔ)專心-專注-專業(yè)質(zhì)子 proton中子 neutron電子 electron核子 nucleon核 nucleus （pl.）nuclei原子 atom光子 photon正電子 positron量子 quantum, quanta (pl.)電子伏特 electron-volt (eV)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熱中子 ther

2、mal neutron快中子 fast neutron復(fù)合核compound nucleus 1.2. 相關(guān)元素與材料1.2.1. 核燃料與增殖材料鈾 uranium（U）钚 plutonium（Pu）氘，重氫 deuterium，heavy hydrogen氚 tritium混合氧化物燃料（MOX燃料）Mixed (Uranium and Plutonium) OXide fuel二氧化鈾 uranium dioxide濃縮鈾 enriched uranium貧鈾 depleted uranium碳化鈾 uranium carbide釷 thorium鋰 lithium錒系元素 actini

3、de element易裂變的 fissile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 conversion1.2.2. 其它核材料及核電廠用材料慢化劑 moderator輕水 light water重水 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鋯 zirconium鋯2/4合金 zircaloy-2/4不銹鋼 stainless stee

4、l控制材料 control material通量展平flux-shaping銀 silver銦 indium鎘 cadmium可燃毒物 burnable poison硼 boron硼酸 boric acid鋰 lithium鈹 beryllium乏燃料 spent fuel因科鎳，因康 INCONEL不銹鋼 stainless steel1.3. 核反應(yīng)及相關(guān)術(shù)語(yǔ)decay衰變fission裂變fusion聚變nuclear reaction核反應(yīng)chain reaction鏈?zhǔn)椒磻?yīng)cross section截面microscopic cross section微觀截面macroscopic

5、cross section宏觀截面absorbing cross section吸收截面scattering cross section散射截面barn靶恩delayed neutron緩發(fā)中子prompt neutron瞬發(fā)中子prompt criticality瞬發(fā)臨界fissile易裂變的fissionab可裂變的lemorderate / slow down慢化breeding ratio增殖比burnup燃耗reactivity反應(yīng)性neutron cycle中子循環(huán)fission product裂變產(chǎn)物criticality臨界prompt critical瞬發(fā)臨界flux通量xe

6、non氙iodine碘actinide錒系（元素）reactivity worth反應(yīng)性價(jià)值慢化劑溫度系數(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倍增因子 multiplication factor有效增殖系數(shù) effective multiplication factor；effective mu

7、ltiplication constant 無(wú)限介質(zhì)增殖系數(shù) infinite multiplication factor； infinite multiplication constant 快中子增殖系數(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 probability四因子公式 four-factor formula多普勒增寬 Doppler broadening*總集成中子通量/總積分中子通量 Total Inte

8、grated Neutron Flux = Integrated Flux or Fluence (注量) = Neutron density ´ Velocity ´ Time 單位：n/m3× m/s × s = n/m2 1.4. 反應(yīng)堆壓水堆 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 Uranium reactor (CANDU) / pressurized heavy water react

9、or (PHWR)英國(guó)氣冷堆（美諾克斯堆）British gas-cooled Magnox reactor高溫氣冷堆 high temperature gas-cooled reactor (HTGR)快中子增殖反應(yīng)堆 fast breeder reactor (FBR)輕水堆 Light Water Reactor (LWR)先進(jìn)反應(yīng)堆 advanced 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） European Pressurized water Reactor (EPR)（美國(guó)）先進(jìn)壓水堆600/1000（第三代

10、(+)反應(yīng)堆之一） AP(WR)600 / 10001.5. 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)(張緊機(jī)) hydraulic stud tensioner 包覆層 clad

11、(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信號(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 internals腫脹 swelling腐蝕 corrode, corr

12、osion侵蝕 erode, erosion氧化 oxidation, oxidize完整性 integrity反應(yīng)堆冷卻劑泵（主泵） Reactor Coolant Pump (RCP)屏蔽泵 canned (motor) pump軸封泵 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一回路系統(tǒng)/主回路系統(tǒng) primary system二回路 secondary loop穩(wěn)壓器 pressur

13、izer (PRZ)波動(dòng)管 surge line汽水分離器 moisture separator干燥器（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止回閥 non-return valve主蒸汽聯(lián)箱 main steam header 給水調(diào)節(jié)閥 feed regulating valve蒸汽發(fā)生器 Steam Generator (SG)主蒸汽管 Main Steam Line (MSL)汽輪機(jī) st

14、eam turbine汽水分離再熱器 Moisture Separator Reheater (MSR)給水泵 feed (water) pump上充泵 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 stack貫穿件 penetration核島 nuclear island常規(guī)島 conventional island核電廠配套子項(xiàng) Balance of Plant (BOP)一回路輔助系統(tǒng) auxiliary system for primary loop化學(xué)與容積控制系

15、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 (DVI)換料水箱 Refueling Water Storage Tank (IRWST)(乏)燃料貯存水池 (spent

16、) fuel storage pool燃料裝卸系統(tǒng) fuel handling system蓄壓箱 accumulator機(jī)組 unit輔助噴淋 auxiliary spray柴油發(fā)電機(jī) Diesel generator自動(dòng)保護(hù)系統(tǒng) Automatic Protective System (APS)自動(dòng)降壓系統(tǒng) automatic depressurization system (ADS)儀控系統(tǒng) Instrumentation and Control System (I & C system)開關(guān)設(shè)備，開關(guān)柜 switch gear 蒸汽軸封系統(tǒng)，壓蓋蒸汽密封系統(tǒng) gland ste

17、am system汽輪機(jī)旁路管 turbine bypass line 輔助給水泵 auxiliary feedwater pump汽動(dòng)給水泵 turbine driven feedwater pump 導(dǎo)管conduit冷凝水泵condensate pump 冷凝水增壓泵 condensate booster pump水潤(rùn)滑軸承 water lubricated bearing 人孔 man way檢修孔 accessory port1.6. 反應(yīng)堆運(yùn)行運(yùn)行 operation運(yùn)行工況 operating condition操縱員 operator維護(hù) maintenance監(jiān)督、監(jiān)視sur

18、veillance 監(jiān)督試樣 surveillance specimen輻照監(jiān)督管 irradiation surveillance capsule輻照監(jiān)督試樣盒 surveillance specimen compartment硼濃度 boron concentration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 / refueling shutdown換料 refuel卸料  discharge倒料

19、60;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反應(yīng)堆調(diào)節(jié)系統(tǒng) Reactor Regulating System (RRS)(蒸汽發(fā)生器)排污、下泄 blowdown規(guī)程 procedure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  

20、;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fuel management scheme燃料-包殼交互作用fuel-clad interaction effect芯塊-包殼交互作用

21、(PCI) pellet-clad interaction(燃料)柵格、晶格 lattice 1.7. 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)邦管理法規(guī) Code of Federal Regulations (CFR)法案（美） Act導(dǎo)則 guidance安全1/2/3級(jí)safety class 1/2/3可靠性 reliability容限，裕量，邊界margin

22、堆芯熱裕量core thermal margin堵管裕量 tube plugging margin運(yùn)行安全裕量 operating margin標(biāo)準(zhǔn)，準(zhǔn)則 criterion，復(fù)數(shù)形式: criteria概率安全分析 Probabilistic Safety Analysis (PSA)概率風(fēng)險(xiǎn)分析 Probabilistic Risk Analysis (PRA)確定論安全分析 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 Analysi

23、s Report (FSAR)安全評(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全廠斷電 station blackout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

24、 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 焓，熱函 sensible heat, enthalpy定期安全檢查 periodic s

25、afety 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 postulated initiating events事故工況 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

26、loss of electrical load accident主給水喪失事故 loss of main feed water accident卡棒事故 stuck rod accident彈棒事故 rod ejection accident堵管裕量 tube plugging margin管道甩擺限制 pipe whip restraint在役檢查 inservice inspection承壓熱沖擊 pressurized thermal shock1.8. 放射性與輻射防護(hù)radioactivity放射性scatter散射deflect, deflection折射衍射 diffractio

27、n穿透 penetrate, penetration交互作用 interact, interactionionization電離湮滅 annihilate (v.), annihilation (n.)衰減 attenuate(v.), attenuation(n.)projectile入射離子radiation protection輻射防護(hù)radiation, ray輻射，射線irradiation輻照，（向外）輻射internal exposure內(nèi)照射external exposure外照射occupational dose職業(yè)照射（劑量）fluence注量cosmic ray宇宙射線x

28、-ray X射線a / b / g 射線 a / b / g rayhealth physics保健物理shielding屏蔽biological shield生物屏蔽劑量 dosedose equivalent劑量當(dāng)量collective dose集體劑量individual dose個(gè)人劑量ingest, ingestion攝入，攝取inhale, inhalation吸入coma昏迷cramp絞痛diarrhea腹瀉tremor顫抖vomit嘔吐somatic身體的 somatic effect軀體反應(yīng)radiation sickness輻照病變symptom征兆therapy治療sur

29、vivor幸存者activation product活化產(chǎn)物effluent廢水natural background天然本底sivert希弗spectrum譜雷姆 rem氡 radonas low as reasonably achievable (ALARA) 合理可行盡量低radioactive waste disposal放射性廢物處理high-level (radioactive) waste高放廢物low-level (radioactive) waste低放廢物1.9. 有關(guān)機(jī)構(gòu)International Atomic Energy Agency (IAEA) 國(guó)際原子能機(jī)構(gòu)Ame

30、rican Society of Mechanical Engineers (ASME) 美國(guó)機(jī)械工程師學(xué)會(huì)Nuclear Regulatory Commission (NRC/USNRC) 美國(guó)核管會(huì)Department Of Energy (DOE) 美國(guó)能源部World Association of Nuclear Operators (WANO) 世界核電運(yùn)營(yíng)者協(xié)會(huì)International Commission on Radiological Protection (ICRP) 國(guó)際輻射防護(hù)委員會(huì)China Atomic Energy Authority （CAEA）中國(guó)國(guó)家原子能機(jī)

31、構(gòu)State Environment Protection Administration of China國(guó)家環(huán)保總局1.10. 其它術(shù)語(yǔ)1.10.1. 表示方向lateral橫向longitudinal縱向radial徑向perpendicular to垂直于vertically mounted垂直/立式安裝circumferential環(huán)向axial軸向periphery周邊1.10.2. 材料失效術(shù)語(yǔ)corrosion腐蝕stress corrosion cracking應(yīng)力腐蝕開裂rapture, fracture, break斷裂breach破口腫脹 swellingcavitati

32、on氣蝕pitting點(diǎn)蝕/孔蝕crevice corrosion縫隙腐蝕erosion沖蝕FAC flow accelerated corrosion流動(dòng)加速腐蝕wastage耗蝕 (SG tube) dent凹陷，凹痕fatigue疲勞ageing老化degradation降級(jí)wear磨損fretting wear微動(dòng)磨損creep蠕變stress應(yīng)力strain應(yīng)變creep strength蠕變強(qiáng)度tensile strength抗拉強(qiáng)度yield strength屈服強(qiáng)度rapture strength斷裂強(qiáng)度nil-ductility transition temperature零

33、延性轉(zhuǎn)變溫度 thermal stress熱應(yīng)力irradiation swelling輻照腫脹deposit welding, overlaying, build-up welding, surface welding堆焊seal weld密封焊heat affected zone (HAZ) 焊接熱影響區(qū)1.10.3. 核電工程術(shù)語(yǔ)procurement征購(gòu)site廠址call for bid, call for tender招標(biāo)commercial offer商務(wù)標(biāo) technical offer技術(shù)標(biāo)commencement開工contract合同firm contract不可更改的合

34、同 subcontract分包合同commitment承諾，任務(wù)job site工地，工作現(xiàn)場(chǎng)technical requirement 技術(shù)要求技術(shù)規(guī)格 technical specification non-conformance不符合項(xiàng)delivery交貨warehouse倉(cāng)庫(kù)construction schedule施工計(jì)劃Free on Board (FOB) 離岸價(jià)格Cost Insurance and Freight (CIF) 到岸價(jià)格Engineering, Procurement & Construction EPC合同-設(shè)計(jì)采購(gòu)建造power grid電網(wǎng)dist

35、ribution system輸變電系統(tǒng)1.10.4. 其它c(diǎn)ompound化合物mixture混合物mass質(zhì)量momentum動(dòng)量energy能量potential (energy) 勢(shì)能kinetic energy動(dòng)能inertia慣性half-life半衰期mean free path平均自由程fuel cycle燃料循環(huán)hot spot熱點(diǎn)hot-channel factor熱管因子departure from nucleate boiling ratio (DNBR) 偏離泡核沸騰比heat transfer傳熱heat exchanger換熱器heat conduction導(dǎo)熱c

36、onvection對(duì)流熱輻射 thermal / heat radiation干度 quality蒸汽 steam預(yù)應(yīng)力鋼筋混凝土 prestressed reinforced concrete / prestressed concrete鋼筋混凝土 reinforced concrete鐵鋼沙混凝土 Steel shot concret筋，鋼筋束 tendon流量分配 flow distribution電網(wǎng) power grid業(yè)主 utility承包商 contractor分包商 sub-contractor壓降 pressure drop壓差differential pressure水位

37、 (water) level規(guī)定，條款；保障；裝備 provision地震 earthquake地震的 seismic颶風(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，緩解 v. mitigate, n. mitigation公差、容差 allowance間隙，公差 clearance權(quán)重因子 weighting factor1.11. 有必要了解的詞匯與短語(yǔ)as a ru

38、le of thumb根據(jù)經(jīng)驗(yàn)by orders of magnitude以數(shù)量級(jí)incipient failure早期故障, 初期故障eliminate, elimination消除derive, derivation, deduce, deduction導(dǎo)出，起源mechanism, approach, principle, theory機(jī)理，原理susceptible敏感的susceptibility敏感性toxic有毒的acute急劇的inherit遺傳hereditary遺傳性的altitude高度postulate, postulation假定，假設(shè)permeable可滲透的, 有

39、滲透性的impermeable不可滲透的brittle fracture脆性破裂embrittlement脆化toughness韌性ductility延展性第2章 閱讀理解題練習(xí)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

40、 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, automatical

41、ly 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 negati

42、ve 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

43、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-

44、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

45、 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. concret

46、e;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 e

47、lement 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 cont

48、ainment, 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

49、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 the

50、ir 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 atmospheri

51、c 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

52、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 indepen

53、dent 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 contain

54、ment.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 heat exchanger. 7. Which

55、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 system are applied for returning the containment pressure to be blow atmospheric after the accident.D. Sodi

56、um 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 p