UNIT 16 STEAM GENETATOR 核电厂蒸汽发生器
电蒸汽发生器构造原理
电蒸汽发生器构造原理电蒸汽发生器（Electric Steam Generator）是一种通过电能转化为热能来产生蒸汽的装置。
该设备结构简单、方便使用，是工业生产中常用的一种加热设备。
该设备由发生器本体、电热元件、自控装置、水位控制系统以及安全保护装置等部分组成。
下面将逐一介绍各个部分的构造原理。
1. 发生器本体发生器本体通常由压力容器和管道系统组成，其主要功能是负责蒸汽的生成和输送。
容器一般采用碳钢或不锈钢制造，容器内部配有加热管和蒸汽排放管，加热管位于容器底部，蒸汽排放管位于容器顶部。
这种排放方式使得蒸汽在产生后能够自然排出，从而保证了设备的安全性。
2. 电热元件电热元件即加热管，其作用是将电能转化为热能，将水加热至沸点，从而产生蒸汽。
加热管材料多为不锈钢或红铜，其长度和直径根据设备需求进行选择。
在电热元件的选择方面，需要考虑到电压、功率、电流等因素。
这些因素必须合理匹配，才能保证设备的正常工作，并且不会造成设备过热、过载等危险情况。
3. 自控装置自控装置主要是为了实现设备的自动化控制，其构成包括温度控制器、压力控制器、时间控制器等。
这些控制器能够自动调节加热功率、保持压力、控制时间等。
温度控制器通过测量水温来控制加热管的温度，保证水的温度控制在一定范围内。
压力控制器通过调节加热功率和蒸汽排放流量来控制设备的蒸汽压力。
时间控制器则可以配合其他控制器完成时间的计量和控制。
4. 水位控制系统水位控制系统是电蒸汽发生器中一个十分重要的系统。
其作用是在设备工作中，对水位进行自动调节，确保水位的稳定和设备的安全性。
水位控制系统通常包括水位检测部分、液位控制阀和液位控制器。
水位检测传感器一般安装在发生器底部，用于感应水位的高低，从而控制液位控制阀的开闭状态，以控制设备的水位。
5. 安全保护装置安全保护装置是保障电蒸汽发生器操作安全的重要环节。
其主要包括过热保护、缺水保护、超压保护和漏电保护等。
过热保护装置是针对设备过热的情况，可以自动断开电源，避免设备因温度过高而损坏。
核电站中的蒸汽发生器工作原理
核电站中的蒸汽发生器工作原理核电站是一种利用核能产生电能的设施，而其中的蒸汽发生器则是核电站中至关重要的设备之一。
蒸汽发生器起着将热能转化为电能的关键作用。
本文将详细介绍蒸汽发生器的工作原理，包括其结构组成和工作流程。
一、蒸汽发生器的结构组成蒸汽发生器由水管和煤气道组成，其中水管是实现核能转化为热能的关键部分。
蒸汽发生器通常由数百根细长的水管组成，这些水管位于煤气道内部。
水管由导热性能较好的金属材料制成，如不锈钢或钼等。
而煤气道则是一种用于流动热能的通道，其设计结构可以确保煤气能充分与水接触，以实现热能的传递。
二、蒸汽发生器的工作流程蒸汽发生器的工作原理可以简单描述为以下几个步骤：加热、蒸发和分离。
1. 加热阶段：核电站中通常使用核裂变产生的热能来加热蒸汽发生器。
燃料经过裂变产生的高温气体或冷却液通过煤气道，从而传递热能给水管。
当热能传递到水管时，水中的液态水被加热，温度逐渐升高。
2. 蒸发阶段：当水管内的水受热后，水中的液态水逐渐转化为蒸汽。
水管中的热能将水中的分子加速，使水分子间的相互作用减弱，从而形成蒸汽。
3. 分离阶段：蒸汽发生器中的分离器可确保水蒸汽和剩余水分离。
蒸汽上升，经过分离器后被分离，而剩余的水会继续循环流动，重新进入煤气道接受热能。
蒸汽发生器的工作原理是通过加热水管内的水，使水转化为蒸汽，并将蒸汽与剩余的水分离。
这些蒸汽最终用于驱动涡轮机发电，将热能转化为电能。
总之，蒸汽发生器在核电站中扮演着至关重要的角色，其工作原理是将核能转化为热能，再将热能转化为电能。
通过合理的结构组成和流程设计，蒸汽发生器实现了高效能量转化，为核电站的电力产生提供了坚实的基础。
【字数：419】。
电厂常用术语中英文对照
电厂常用术语中英文对照电力术语中英文对照目录一、集控运行常用设备和术语缩写 (2)（一）锅炉部分 (2)（二）汽机部分 (4)（三）DEH部分 (5)（四）电气部分 (6)（五）系统分类 (6)（六）阀门 (7)（七）其它 (8)二、电厂术语——锅炉部分 (10)三、电厂术语——汽轮机部分 (27)四、电厂术语——电气专业 (59)五、电厂术语——电厂化学 (87)六、电厂术语——仪表与控制 (106)七、电厂术语——燃料 (126)八、电厂术语——综合管理部分 (136)九、电厂术语——脱硫 (165)一、集控运行常用设备和术语缩写（一）锅炉部分1、通用及煤粉炉FDF (forced draft fan)——送风机IDF (induced draft fan)——引风机PAF (primary air fan)——一次风机SAF (seal air fan)——密封风机DETF (flame detector fan)——火检风机APH (air preheater)——空气预热器DRUM (drum)——汽包ECON (economizer)——省煤器SH (superheater)——过热器CSH (ceiling superheater)——顶棚过热器PSH (platen superheater)——屏式过热器RSH (radiation superheater)——辐射过热器LSH (low temperature superheater)——低温过热器HSH (high temperature superheater)——高温过热器RH (reheater) ——再热器LRH (low temperature reheater)——低温再热器HRH (high temperature reheater)——高温再热器PRH (platen temperature reheater)——屏式再热器CB (coal bin)——煤仓SCB(side coal bin)——侧煤仓MILL (mill)——磨煤机FEED (coal feeder)——给煤机PCC (pulverized-coal collector)——细粉分离器MILLS (mill separator)——粗粉分离器PEF (powder exhaust fan)——排粉风机PCF(pulverized coal feeder)——给粉机HPA (heat primary air )——热一次风CPA (cold primary air )——冷一次风SECA (secondary air)——二次风TA (tertiary air)——三次风SA (seal air)——密封风AR (air register)——风门OILP (oil pistol)——油枪IGNT (ignition) ——点火枪FULP (fuel pump)——燃油泵FLTK (flash tank)——扩容器FURN(furnace) ——煤粉炉炉膛2、流化床锅炉HPCB（high-pressure centrifugal blower）——高压流化风机CFBB（Circulating Fluidized-bed Boiler）——循环流化床炉膛CYCS（cyclone separator）——旋风分离器UBF(U-type back-feeder) ——U形返料器ASHC(ash cooler) ——冷渣器3、余热锅炉CVB(convection bank) ——对流管束SWS(steam/water separator) ——汽水分离器WJP（Water jet pump）——射水泵WH(water heater) ——热水器EVP(evaporator) ——蒸发器OEJ（oil ejector）——注油器OFT（oil filter）——滤油器OCL（oil cooler）——冷油器窑头余热锅炉AQCB(此处AQC指air quenching cooler，为篦冷机，不是窑头的意思，但行业习惯称窑头余热炉为AQC炉) 窑尾余热锅炉SPB(此处SP指suspension preheater，为悬浮预热器，不是窑尾的意思，但行业习惯称窑尾余热炉为SP炉) （二）汽机部分HP (high pressure cylinder) ——高压缸IP (intermediate pressure cylinder) ——中压缸LP (low pressure cylinder) ——低压缸DEA (deaerator) ——除氧器COND (condenser) ——凝汽器HPH (high pressure heater) ——高压加热器LPH (low pressure heater) ——低压加热器SSH (shaft seal heater) ——轴封加热器MFP (motor-driven feed pump) ——电动给水泵SFP (steam feed pump) ——汽动给水泵V ACP (vacuum pump) ——真空泵CEP (Condensate extraction pump) ——凝结水泵DRNP (drain pump) ——疏水泵CIRP (circulating pump) ——循环泵LIFTP (lift pump) ——顶轴油泵LUBOP (lubricating oil pump) ——润滑油泵DCOP——直流润滑油泵ACOP——交流润滑油泵HPOP——高压启动油泵MAINOP——主油泵EHP——EH油泵OTANK (oil tank) ——油箱WTANK (water tank) ——水箱HEADER——联箱SSF (shaft seal fan) ——轴封风机IFF (induced-fume fan) ——排烟风机AIRCMP(air compressing engine) ——空气压缩机（三）DEH 部分TV——高压缸主汽门GV——高压缸调节门RV——中压缸主汽门IV——中压缸调节门LV——低压缸调节门（四）电气部分GEN (generator) ——发电机XFORM (transformer) ——变压器BUS (bus bar) ——母线BRK (circuit breaker) ——断路器SWITCH (isolating switch) ——隔离开关EXCT (exciter) ——励磁机PEXCT (pilot exciter) ——副励磁机（五）系统分类feed water system ——给水系统water-steam system ——汽水系统desuperheater system ——减温水系统combustion system ——燃烧系统extraction steam system ——抽汽系统heat supply system ——热网系统lubricating oil system——润滑油系统fuel oil system——燃油系统soot blower system——吹灰系统ignition system——点火系统powder manufacturing system——制粉系统drain system——疏水系统wind-fume system——风烟系统blowdown system——排污系统condensate system——凝结水系统deaerator system——除氧器系统turbine body——汽轮机本体by-pass system——旁路系统cooling water system——冷却水系统circulation water system——循环水系统vacuum system——真空系统（六）阀门shutoff valve——截止阀check valve——单向阀motorized valve——电动阀magnetic valve——电磁阀pneumatic positioner valve——气动阀flapper valve——挡板阀steam converter valve——减温减压阀fast valve——快关阀blow down valve——吹扫阀blow down valve——排污阀（七）其它CCS(coordinated control system) ——协调控制系统SIS(supervision & information system) ——监控信息系统MIS(management information system) ——管理信息系统BF(MODE)(borler follow mode) ——锅炉跟随方式TF(MODE)(turbine follow mode) ——汽轮机跟随方式CCS(MODE)(coordinated control mode) ——协调控制方式Manual Mode——手动方式BASE MODE——基本（手动）方式ULD(unit load demand) ——机组负荷指令ADS(automatic dispatch system) ——自动调度系统UM(unit master) ——单元机组主控制器BM&TM(boiler master & turbine master) ——锅炉主控制器和汽轮机主控制器BCS(boiler control system) ——锅炉控制系统TCS(turbine control system) ——汽轮机控制系统RB(run back) ——负荷返回RD(run down) ——强迫降负荷（迫降负荷）RU(run up) ——强迫升负荷（迫升负荷）FCB(fast cut back) ——快速减负荷AGC(automatic generation control) ——自动发电控制MFT(master fuel trip) ——主燃料跳闸CP MODE(constan pressure mode) ——定压方式VP MODE(variable pressure mode) ——滑压方式MCR(maximum continuous rating) ——最大连续出力ECR(economic continuous rating)——经济连续出力B-MCR(boiler maximum continuous rating) ——锅炉最大连续出力T-MCR(turbine maximum continuous rating) ——汽轮机最大连续出力MCS(modulating control system) ——模拟量控制系统FSSS(furnace safeguard supervisory system) ——炉膛安全监控系统BMS(burner management system) ——燃烧器管理系统SCS(sequential control system) ——顺序控制系统ECS(electric control system) ——电气控制系统DEH(digital electric-hydraulic control system) ——数字电液控制系统OPC(over speed control) ——超速控制AST(autostop trip) ——自动停机遮断ETS(emergence trip systems) ——危急遮断系统ATC(automatic turbine control) ——自动汽轮机程序控制TSI(turbine supervisory instrumentation) ——汽轮机监视系统PLC(programmable logic controller) ——可编程逻辑控制器SCR（selective catalytic reduction）——选择性催化还原法二、电厂术语——锅炉部分1．临界压力锅炉supercritical pressure boiler2. 亚临界压力锅炉subcritical pressure boiler3. 超高压锅炉super-high pressure boiler4. 蒸汽锅炉steam boiler5. 蒸汽发生器steam generator6. 液态排渣锅炉wet bottom boiler7. 固态排渣锅炉dry bottom boiler8. 燃煤锅炉coal-fired boiler9. 燃气锅炉Gas-fired boiler10.燃油锅炉oil-fired boiler11.自然循环锅炉natural circulation boiler12.汽包（锅筒）锅炉drum boiler13.强制循环锅炉controlled circulation boiler14.直流锅炉once-through boiler15.复合循环锅炉combined circulation boiler16.旋风炉cyclone furnace boiler17.沸腾炉fluidized bed combustion(FBC)boiler18.循环硫化床circulating fluidized bed combustion(FBC)boiler19.增压循环硫化床锅炉pressurized circulating fluidized bed combustion(PCFBC) boiler20.链条锅炉chain-grate boiler21.热水锅炉hot-water boiler22.废热（余热）锅炉water-heat boiler, heat recover steam generator(HRSG)23.启动锅炉start-up boiler24.厂用锅炉auxiliary boiler25.垃圾焚烧锅炉refuse-fired boiler, refuse incinerator27.露天锅炉outdoor boiler28.单炉膛锅炉single furnace boiler29.双炉膛锅炉twin furnace boiler30.W火焰锅炉W-flame boiler, vertical-fired boiler31.L火焰锅炉L-shape furnace boiler32.塔式锅炉tower boiler33.箱式锅炉box-type boiler34．炉墙furnace wall35. 汽包（锅筒）drum36.封头head37.汽包封头drum end plate, drum head38.下降管downcomer39.集中下降管centralized downcomer40.分散下降管distributed downcomer41.上升管riser42.管束（排）tube bundle43.管屏tube platen44.省煤器管economizer tube45.过热器管superheated tube46.再热器管reheater tube47.蛇形管coil48.吊挂管supporting tube49.引入管inlet pipe50.引出管outlet pipe51.饱和蒸汽管saturated steam pipe52.水冷壁管water wall tube53.鳍片管finned tube, fin tube, gilled tube54.内螺纹管rifled tube, grooved tube55.吸潮管moisture absorption piping56.水冷壁water wall57.膜式水冷壁membrane wall58.内螺纹水冷壁rifled tube water wall59.联箱header60.集汽联箱steam header61.卫燃带bailey wall, refractory belt62包墙管（包覆管）wall enclosure tube63.防渣管（弗斯顿管）slag screen, feston tube64.锅炉本体boiler proper65.锅炉机组boiler unit66.锅炉构架boiler structure67.炉膛boiler framework68.燃烧器furnace69.直流式燃烧器direct-flow burner70.旋流式燃烧器turbulent burner71.低NOX燃烧器low NOX burner72.摇摆式燃烧器tilting burner73.缝隙式燃烧器split burner74.燃烧室combustion chamber75.油枪oil gun torch76.风门damper77.一次风primary air78.二次风secondary air79.三次风tertiary air80.煤粉管道pulverized coal piping81.管板tube plate82.沸点boiling temperature83.过热器superheater84.前屏过热器front platen superheater85.后屏过热器rear plate superheater86.对流过热器convection superheater87.辐射过热器radiant superheater88.屏式过热器plate superheater89.顶棚过热器ceiling superheater90.包墙过热器wall enclosure superheater91.前包墙过热器front wall enclosure superheater92.后包墙过热器rear wall enclosure superheater93.侧包墙过热器side wall enclosure superheater94.吹灰器soot blower95.转动式吹灰器rotary soot bolwer96.伸缩式吹灰器retractable soot blower97.受热面积heating surface area, heat absorption area98.炉膛容积furnace volume99.炉膛热负荷furnace heat release rate, furnace heating absorption rate 100.汽水分离器steam separator, moisture separator101.起动分离器starting separator102.再循环管recirculating piping103.暖风器steam air heater104.再热器reheater105.再热器冷段primary reheater106.再热器热段final reheater107.顶棚ceiling108.省煤器economizer109.管式省煤器tube economizer110.管式空气预热器tubular air preheater111.回转式（再生式）空气预热器regenerative air preheater, rotary air preheater112.板式空气预热器plate air preheater113.空气预热器air preheater114.三分仓空气预热器trisector regenerative air preheater115.漏风系数air leakage coefficient116.漏风率air leakage ratio117.漏风系统air leakage system118.漏风试验air leakage test119.安全门safety valve120.安全门开启压力opening pressure of safety valve121.安全门回座压力safety valve reseating pressure122.安全门压力整定试验pressure setting test of safety valve 123.安全门动作压力safety valve operating pressure124.饱和蒸汽安全门saturated steam safety valve125. 过热蒸汽安全门superheated steam safety valve126.再热蒸汽安全门reheated steam safety valve127.防暴门explosion vent128.检查孔inspection hole129.事故喷水阀emergency water spray valve130.汽包事故放水阀emergency drum drain valve 131.三通阀three-way valve132.反冲洗阀back wash valve133.取样阀sampling valve134.插板gate135.给水大旁路门feedwater overall bypass valve 136.给水小旁路门feedwater individual bypass valve 137.大板梁plate girder, upper beam138.外护板outer casing139.锅炉排污blowdown140.定期排污扩容器intermittent blowdown flash tank 141.连续排污扩容器continuous blowdown flash tank 142.灰斗ash hopper143.冷灰斗bottom ash hopper, furnace hopper144.混合器mixer145.齿圈（大牙轮）ring gear, geared ring146.空调器air conditioner147.空气压缩机air compressor148.给煤机coal feeder149.皮带式给煤机belt coal feeder150.刮板式给煤机scraper coal feeder151.叶轮式给煤机paddle coal feeder152.给粉机pulverizer coal feeder153.磨煤机coal pulverizer, coal mill154.钢球磨煤机tube mill155.中速辊式磨煤机roller mill, bowl mill, disk roll mill 156.双进双出钢求磨煤机double inlet and outlet tube mill 157.中速磨煤机medium speed mill158.风扇磨煤机beater wheel mill, beater mill159.排粉风机pulverized coal exhauster160.一次风机primary air fan161. 烟气再循环风机gas recirculation fan162.送风机forced draft fan, force fan163.引风机induced draft fan, induced fan164.离心风机centrifugal fan165.轴流风机axial-flow fan166.双速风机double speed fan167.轴流静叶可调风机adjustable static-blade axial-flow fan fixed pitch axial-flow fan168.轴流动叶可调风机adjustable moving-blade axial-flow fan variable pitch axial-flow fan169.原煤斗raw coal bunker, raw coal silo170.煤粉仓pulverized coal bunker171.输粉机pulverized coal conveyer172.刮板输粉机scraper pulverized coal conveyer 173.螺旋输粉机pulverized coal screw conveyer174.粗粉分离器classifier175.细粉分离器（旋风分离器）cyclone separator 176.锁气器air lock, flap177.减速机speed reduce178.看火孔observation hole179.人孔门man hole180.重油泵heavy oil pump181.重油加热器heavy oil heater182.汽-汽热交换器biflux183.煤气罐gas tank184.膨胀补偿节expansion joint185.直吹式制粉系统direct firing pulverizing system 186.中贮式制粉系统bin storage type pulverizing system 187.锅炉效率boiler efficiency188.锅炉热力计算boiler thermodynamic calculation 189.锅炉空气动力计算boiler aerodynamic calculation 190.锅炉水循环计算boiler water circulation calculation 191.锅炉水力计算boiler hydrodynamic calculation 192.锅炉强度计算boiler strength calculation193.锅炉热平衡boiler heat balance calculation 194.正平衡法direct balance method195.反平衡法indirect balance method196.过剩空气系数excess air coefficient197.排烟温度flue gas temperature198.单位蒸量specific evaporation199.低温腐蚀low temperature corrosion200.高温腐蚀high temperature corrosion201.结渣lagging202.结垢腐蚀deposit corrosion203.飞灰磨损fly ash erosion204炉膛负压furnace draft205.最高允许温度maximum permissible temperature 206.炉膛正压furnace pressure207.水循环water circulation208.循环倍率circulation ratio209.除尘器dust collector, precipitator210.静电除尘器electrostatic precipitator211.整流装置rectifying device212.锤打装置rapping gear213.含尘浓度dust loading concentration214.煤灰细度dust fineness。
压水堆蒸汽发生器热交换管的在役涡流检查（二篇）
压水堆蒸汽发生器热交换管的在役涡流检查压水堆蒸汽发生器（steam generator）是核电站中至关重要的一个组件，用于将核反应堆产生的热能转化为蒸汽，从而驱动涡轮发电机发电。
而蒸汽发生器中的热交换管（heat exchanger tube）是实现热能传递的关键部分。
因此，在役涡流检查（in-service eddy current inspection）是对热交换管的可靠性和安全性进行评估的重要手段。
本文将就压水堆蒸汽发生器热交换管的在役涡流检查进行详细介绍和探讨。
一、引言压水堆蒸汽发生器是核反应堆与涡轮发电机之间的热交换设备，它起到了将核反应堆产生的热能转换为蒸汽的重要作用。
蒸汽发生器中的热交换管是核反应堆冷却剂和锅炉水之间热传递的关键部分。
由于蒸汽发生器处于高温、高压和辐射环境中，热交换管存在一定的风险和损伤。
因此，在该设备运行的过程中进行定期的在役涡流检查对于保证核电站的运行安全具有重要意义。
二、在役涡流检查的原理和技术在役涡流检查是一种通过电磁感应原理来检测热交换管壁腐蚀、疲劳裂纹等缺陷的方法。
它利用涡流探头（eddy current probe）发射交流电磁场进入热交换管内部，当电磁场遇到管道壁上的缺陷时，会发生电磁感应现象，进而引起敏感线圈检测到的信号变化。
通过分析信号的变化，可以确定管道壁上的缺陷位置、类型和尺寸。
在役涡流检查可以对热交换管的外壁和内壁进行检测，能够较为准确地评估热交换管的健康状态。
三、在役涡流检查的应用案例在役涡流检查已经在压水堆蒸汽发生器中得到广泛应用。
以下将介绍几个应用案例，以说明在役涡流检查的实际效果。
1. 腐蚀缺陷检测在压水堆蒸汽发生器运行过程中，热交换管壁可能会出现腐蚀现象。
这种腐蚀可能是由于介质腐蚀、水质问题或管道材料缺陷引起的。
通过在役涡流检查，可以对腐蚀缺陷进行精确检测，并评估其对设备安全性的影响程度。
基于涡流检测结果，可以采取相应的维修和防护措施，确保设备的安全运行。
核电 专 业 英 语 词 汇
1.1. 原子核、元素及材料中子neutron核nucleus （复数）nuclei 硼boron 硼酸boric acid可燃毒物burnable poison 硼浓度boron concentration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 1.2. 术语1.2.1.工况衰变decay裂变fission燃耗burnup反应性reactivity裂变产物fission product临界criticality换料周期fuel cycle运行工况operating condition 停堆shutdown满功率运行full power operation 瞬态，瞬变transient衰变热decay heat余热residual heat厂用电house load次临界subcritical超临界supercritical慢化剂moderator冷却剂coolant溶剂solvent反射层reflector1.2.2.设备稳压器pressurizer (PRZ)蒸汽发生器Steam Generator (SG)屏蔽泵canned (motor) pump反应堆压力容器Reactor Pressure Vessel (RPV)包壳cladding安全壳containment堆芯，活性区core燃料棒fuel rod燃料组件fuel assembly控制棒control rod控制棒组件Control Element Assembly (CEA)控制棒驱动机构Control Element Drive Mechanism (CEDM) 柴油发电机diesel generator1.3. 系统压水堆Pressurized Water Reactor (PWR)反应堆冷却剂泵（主泵）Reactor Coolant Pump (RCP)反应堆冷却剂系统（一回路系统）Reactor Coolant System (RCS)一回路系统/主回路系统primary system一/二回路primary/secondary loop非能动余热导出系统passive decay heat removal system自动降压系统automatic depressurization system (ADS)化学与容积控制系统（化容系统）Chemical and V olume Control System 专设安全设施Engineered Safety Feature (ESF)余热排出系统Residual Heat-Removal System应急堆芯冷却系统Emergency Core Cooling System安注系统Safety Injection (SI) System非能动安全系统passive safety system设冷水component cooling water非能动堆芯冷却系统passive core cooling system1.4. 事故运行安全裕量operating margin冷却剂丧失事故（失水事故）Loss-of-coolant Accident (LOCA)假设始发事件postulated initiating events 事故工况accident condition单一故障准则single-failure criterion共因故障common cause failure纵深防御defense in depth 设计基准事故design basis accident 固有安全性inherent safety冗余性redundancy多样性diversity完整性integrity多层屏障multiple barrier放射性radioactivity海啸tsunami屏蔽shielding核安全准则nuclear safety criteria 1.5. 方向横向lateral纵向longitudinal 径向radial 垂直/立式安装vertically mounted 环向circumferential轴向axial1.6. 腐蚀腐蚀corrode, corrosion 气蚀cavitation点蚀/孔蚀pitting缝隙腐蚀crevice corrosion 冲蚀erosion老化ageing磨损wear蠕变creep 应力stress应变strain辐照肿胀irradiation swelling1.7. 阀门波动管surge line安全阀safety valve卸压阀relief valve爆破阀squib valve主蒸汽隔离阀main steam isolation valve。
蒸汽发生器水位控制失效原因及改进建议
蒸汽发生器水位控制失效原因及改进建议
文 / 生态环境部东北核与辐射安全监督站李菲菲宋琼
摘要:本文介绍了压水堆核电厂蒸汽发生器水位控制系 统 ，并以蒸汽发生器水位失控引发的跳堆事件为例,分析了 S G 水位失控的原因并提出了相应的改进建议。
关键词:蒸汽发生器水位控制控制失效
蒸 汽 发 生 器 (Steam Generator,SG) 是 核 电 厂 一 、二回路 的 热 交 换 设 备 ，它 将 一 回 路 冷 却 剂 中 的 热 丨 带 出 ，传给二回 路 给 水 ，使其产生饱和蒸汽推动汽轮机做功。S G 水位控制 系统是将S G 的水位维持在整定值附近，防止蒸汽湿度太大 或 堆 芯 冷 却 不 足 影 响 核 电 厂 安 全 、稳 定 运 行 。 — 、S G 水位控制系统介绍
参考文献： m 张波，张振华，陈方强，等.基于运行事件研究蒸汽发生器水 位异常的手动干预[)].科技视界，2〇18(28).
(上 接 第 1 1 5 页)
如 图 3 所 示 ，3 月 8 日无功波动有2 次 ，且 都 接 近 0,检 查脱网风机停机事件，也验证了猜想，如 表 2 所 示 。
表 2 脱网风机停机情况
SG 水位控制系统由给水阀水位Байду номын сангаас节系统和给水泵转 速调节系统共同组成。
核专业英语词汇
核电厂专业英语词汇人工的artificial化学键chemical bond化合物compound上标superscript下标subscript放射性的radioactive加权平均weighted mean质量mass单位，机组unit质量亏损mass defect结合能binding energy动能kinetic energy势能potential, potential energy排斥repulsion吸引attraction轰击bombardment发射（出）emission (n.), emit (v.)能级energy level裂变fission 聚变fusion衰变decay核反应nuclear reaction链式反应chain reaction辐射，射线radiation可裂变的fissionable易裂变的fissile碎片fragment激发excite静电的electrostatic（二）放射性相互作用interaction摄入ingest吸入inhale动能kinetic energy势能potential (energy)量子quantum屏蔽shielding正电子positron加速器accelerator放射性radioactivity湮灭annihilation光电效应photoelectric effect（三）核反应衰减attenuation放大amplification弹性的elastic非弹性的inelastic宏观截面macroscopic cross section微观截面microscopic cross section转变，转化transmutation扩散diffusion热核反应堆thermonuclear reactor（四）核材料燃料fuel燃料芯块fuel pellet慢化剂moderator冷却剂coolant包壳cladding 控制棒control rod密度density热导率，传热系数thermal conductivity比热specific heat粘性viscosity饱和saturation热力性质，热物性thermodynamic property反应性reactivity升华sublime金属间化合物inter-metallic compound裂变产物fission product裂变碎片fission fragment腐蚀产物corrosion product冷轧cold pressing烧结sintering开裂crack蠕变creep高温气冷堆High Temperature Gas-cooled Reactor (HTGR)（中子）通量展平flux-shaping（五）核反应堆理论自持的链式反应self-sustaining chain reaction燃料循环fuel cycle临界(a) critical次临界(a) subcritical超临界(a) supercritical临界(n) criticality临界尺寸critical size共振resonance弹性散射碰撞elastic scattering collision热中子利用系数thermal utilization factor慢化slow down换料(v) refuel快中子增殖反应堆，快堆Fast Breeding Reactor (FBR)堆芯，活性区core再生区blanket半透膜semi-permeable membrane旋转spin (过去分词：spun)热中子反应堆，热堆thermal reactor快堆fast reactor（十）压水反应堆压水反应堆，压水堆Pressurized Water Reactor (PWR)蒸汽发生器steam generator一次侧primary side二次侧secondary side发电机electrical generator, generator燃料芯块fuel pellet包壳cladding堆芯core给水泵feed(water) pump反应堆（压力）容器reactor vessel, pressure vessel硼酸boric acid化学补偿控制chemical shim control堆坑reactor pit气密的airtight再生区blanket用户，业主，业界utility卖主，供应商vendor, supplier制造商manufacturer 多重屏障multiple barriers纵深防御defense in depth冗余性redundancy多样性diversity独立性independence包容contain安全级safety class失效failure安全功能safety function反应堆冷却剂系统Reactor Coolant System (RCS)在役检查inservice inspection汽水分离器moisture separator干燥器steam dryer堆内构件reactor internals反应堆冷却剂泵，主泵reactor coolant pump (RCP), main pump稳压器pressurizer波动管surge line剖视图sectional view一次冷却剂primary coolant主蒸汽main steam反应性引入reactivity insertion浓度concentration信号调理signal conditioning反应堆紧急停堆reactor trip汽机脱扣turbine trip可靠性reliability 规范，法规code燃耗burnup（十一）反应堆容器与堆内构件监视surveillance样品，试样specimen安装mount临界值，限值threshold （机）接合，啮合，对位engage凸缘，凸起部，轮毂boss逐渐变细的tapered圆顶dome围板shroud（十二）反应堆堆芯与燃料可燃吸收棒burnable absorber rod固有安全性inherent safety非能动安全passive safety能动安全active safety套管，套筒sleeve定位格架spacer grid星形架，蜘蛛spider（十三）压水堆冷却剂系统主要设备U形管蒸汽发生器U-tube steam generator核供汽系统Nuclear Steam Supply System (NSSS)一次系统primary system 二次系统secondary system主蒸汽main steam汽轮机，透平机械turbine给水与凝汽系统feed and condensate system热管段，热腿hot leg冷管段，冷腿cold leg堵管裕量tube plugging margin在¼¼情况下in the event of换热器heat exchanger (HX)节热器，省煤器economiz给水feedwater一次进口水室inlet plenum一次进口接管primary inlet nozzle一次出口水室outlet plenum一次出口接管primary outlet nozzle管板tubesheet喷放；（SG）排污blowdown上升段riser下降段downcomer满功率full power (FP)额定功率rated power额定负荷rated load化学和容积控制系统Chemical and Volume Control System (CVCS)加热，升温heatup冷却，降温cooldown喷淋管线spray line辅助喷淋管线auxiliary spray line上充泵charging pump 上充charge下泄letdown水位water level, level备用的backup过压保护overpressure protection安全壳内换料水箱In-containment Refueling Water Storage Tank (IRWST)换料水箱Refueling Water Storage Tank (RWST)安全阀safety valve卸压阀relief valve全厂断电station blackout (SBO)（蒸汽）干度quality空泡份额void fraction热冲击thermal shock急冷，骤冷quench（十四）压水堆系统与安全壳裂变碎片fission fragment轻水反应堆Light Water Reactor (LWR)热机thermal engine原动机prime mover反馈feedback一（次）回路primary loop二（次）回路secondary loop核电厂配套子项Balance of Plant (BOP)一次压力边界primary pressure boundary隔离阀isolation valve失效failure故障fault, malfuction卡诺效率Carnot efficiency热机效率engine efficiency高温热源，热库hot reservoir低温热源cold reservoir摩擦friction余热排出系统ResidualHeat-Removal System (RHRS)换料(n) refueling应急堆芯冷却系统Emergency Core- Cooling System (ECCS)补水与排水feed and bleed专设安全设施Engineered Safety Feature (ESF)设备冷却水系统Component Cooling System止回阀non-return valve蓄压箱accumulator电动阀motor-driven valve气动阀pneumatic valve安注泵safety injection pump安全壳containment钢筋混凝土reinforced concrete预应力钢筋混凝土prestressed reinforced concrete英制压力单位psi = pounds per square inch 英制压力单位（表压）psig = pounds per square inch gauge环形的annular 潜热latent heat显热sensible heat启动startup飞射物，导弹missile蒸汽管线steamline安全壳地坑containment sump（十六）主蒸汽、给水与凝汽系统机组unit负荷load主蒸汽集管main steam header给水联箱feedwater header给水回热循环regenerative feed heating cycle磨损wear污垢，结垢fouling装量inventory蒸汽（旁路）排放steam dump冷凝器排放condenser steam dump大气排放atmospheric steam dump除氧器排放deoxidizer steam dump电缆electric cable辅助给水系统auxiliary feedwater system压差differential pressure, pressure differential, pressure difference增压泵booster pump增压boost pressure吸入口suction凝汽器condenser凝汽器热阱condenser hotwell给水流量调节阀feed regulating valve给水调节旁通阀feed regulating bypass valve疏水drain阶跃变化step change线性（斜坡）变化ramp change溢流阀overflow valve工艺汽process steam紧急停堆trip; scram停堆shutdown停堆，停堆期outrage手动地manually自动地automatically质量流率mass flow rate关断阀shutoff valve（十七）核电厂运行运行因子operation factor负荷因子load factor使用因子，运行因子service factor可利用因子availability技术规范technical specification稳压器汽空间建立draw a pressure steam bubble未能紧急停堆的预计瞬变Anticipated Transient Without Scram (ATWS)未能紧急停堆的预计瞬变Anticipated Transient Without Trip (ATWT)失电loss of power失流loss of flow辅助喷淋auxiliary spray采样sampling（十九）核安全核安全nuclear safety过热overheating破裂rupture置信度confidence负温度系数negative temperature coefficient 事故accident堆年reactor-year快堆fast reactor热堆thermal reactor失效安全fail safe三哩岛事故Three Mile Island accident (TMI accident)切尔诺贝利事故Chernobyl accident设计基准事故Design Basis Accident (DBA)严重事故severe accident熔融meltdown多普勒展宽Doppler broadening反应性引入事故Reactivity Insertion Accident (RIA)冷却剂丧失事故，失水事故Loss-Of-Coolant Accident (LOCA)自动保护系统Automatic Protective System (APS)瞬发临界prompt critical蒸汽发生器传热管破裂Steam Generator Tube Rapture (SGTR)确定性安全分析deterministic safety analysis概率安全分析Probabilistic Safety Assessment (PSA)。
核电专业英语词汇
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 neutron复合核compound nucleus1.2. 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2/4合金zircaloy-2/4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 1.3. 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absorbing 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（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 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 V essel (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 V olume 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 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 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 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lattice1.7. 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radioactivity放射性scatter散射deflect, deflection折射衍射diffraction穿透penetrate, penetration交互作用interact, interaction ionization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α/β/γ射线α/β/γrayhealth 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radon as low as reasonably achievable (ALARA) 合理可行尽量低radioactive waste disposal放射性废物处理high-level (radioactive) 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 (W ANO) 世界核电运营者协会International 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creep 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call 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 specificationnon-conformance不符合项delivery交货warehouse仓库construction schedule施工计划Free on Board (FOB) 离岸价格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 distribution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 (HV AC)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 factor 1.11. 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susceptibility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 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 systemsare 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 steamD. 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 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 system are applied for returning the containment pressure tobe 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 stress such as pressure vessel or pipework. Human error on the part of operating and maintenance staff has also proved to be a rather frequent source of trouble in nuclear power plant.These factors are not peculiar to nuclear power plant, but they assume great importance because of the hazardous nature of nuclear reactors. Designers have to ensure that all systems should as far as possible be fail-safe and redundant, i.e. if one system fails to function correctly, another is available to fulfill the same function.As stated above, nuclear reactors cannot explode like nuclear bombs. This primarily because of the fast acting negative thermal feedback due to Doppler broadening of the 238U absorption resonances. In addition in thermal reactors where neutrons are moderated, the prompt neutron lifetime Lp is the order of 10-4 second; in a bomb, since the neutrons are unmoderated, the prompt neuron lifetime is of the order of 10-8 seconds. Finally, reactor fuel consists typically of 2 to 3 percent 235U, where as nuclear weapons contain almost pure 239Pu. The net effect of these difference is that, even in a reactor which is totally out of control and gone prompt critical, the reactor period will not be much less than a second or so. In a nuclear bomb, the period is of the order of nanoseconds.(1)According to the text, the most likely source of troubles in a nuclear comes fromA.Core of the reactorB.Conventional componentsC.Parts under stressD.Human error(2)The first sentence of second paragraph “These factors are not peculiar to …”,what does “These factors” mean?A.Human errorB.Malfunction of conventional componentsC.Fission chain reaction in the coreD.All of the above(3)What make the pressurized water reactors can not explode like a nuclear bomb?A.Doppler broadening of the 238U absorption resonancesB.The neutrons are moderatedC.PWR fuel contains much less fissile isotopes than nuclear bombD.All of the above(4)The last two sentences “The net effect of … is of the order of nanoseconds.” Givea comparison about the reactor period, what does the author most likely toexpress?A.The reactor period is too short comparing with a nuclear bombB.The 239Pu in a nuclear bomb is more easily to go prompt criticalityC.The nuclear reactor can not generate large amount of heat as a nuclear bombdoes within very short time, therefore nuclear reactor can not explode.D.The author wants to give us a reference about the data of the reactor periodtime.2.5. Passage VThe primary functions of the control rod drive mechanisms (CRDM) are to insert or withdraw rod cluster control assemblies and gray rod control assembles into or from the core to control average core temperature at a designed speed. A schematic diagram of CRDM is given in Fig 1. Control rod withdrawal one step involves six actions.1) Moveable Gripper Coil B-on.The latch-locking plunger rises andswings the movable gripper latchesinto the drive rod assembly groove. Asmall axial clearance exists betweenthe latch teeth and the drive rod.2) Stationary Gripper Coil A-off.The force of gravity, acting upon thedrive rod assembly and attachedcontrol rod, causes the stationarygripper and plunger to movedownward 1/16 inch, transferring theload of the drive rod assembly andattached control rod to the movablegripper latches. The plungerFig 1. Control rod drive mechanism continues to move downward andswings the stationary gripper latches out of the drive rod assembly groove.3) Lift Coil C-on. The 5/8-inch gap between the movable gripper pole and the lift pole closes, and the drive rod assembly rises one step length.4) Stationary Gripper Coil A-on. The plunger rises and rises the gap below the stationary gripper pole. The three links, pinned to the plunger, swing the stationary gripper latches into a drive rod assembly groove. The latches contact the drive rod assembly and lift it a small fraction of an inch. The small vertical drive rod assembly movement transfers the drive rod assembly load from the movable gripper latches to the stationary gripper latches.5) Movable Gripper Coil –off. The latch-locking plunger separates from the movable gripper pole under the force of a spring and gravity. Three links, pinned to the plunger, swing the three movable gripper latches out of the drive rod assembly groove.6) Lift Coil C –off. The gap between the movable gripper pole and the life pole opens. The movable gripper latches drop 5/8 inch to a position adjacent to a drive rod assemble groove.Repetition of the above six actions will make another step of withdrawal movement of control rod.(1)According to the text, the most likely source of troubles in a nuclear comes fromA.Core of the reactorB.Conventional componentsC.Parts under stressD.Human error(2)According to the text, the most likely source of troubles in a nuclear comes fromA.Core of the reactorB.Conventional componentsC.Parts under stressD.Human error第3章句子翻译－举例3.1. Which 从句(1)The atoms of all elements, which at one time were thought to be thefundamental particles of nature, consist of numbers of three more fundamental particles-protons, neutrons and electrons. 曾经被认为是自然界中基础粒子的原子是由多个更基础的粒子组成－质子、中子和电子。
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UNIT 16 STEAM GENETATOR
蒸汽发生器
1.The steam generators are vertical, shell and U-tube heat exchan
gers where energy from the hot pressurized reactor coolant is t ransferred to the secondary coolant to produce dry, saturated s team.
蒸汽发生器为立式U型管热交换器。
在此，一回路高温高压的能量传递给二次侧的流体，产生干燥、饱和的蒸汽。
2.The dry saturated steam produced is used to operate the main t
urbine and auxiliaries in the production of electricity.
干燥饱和的蒸汽用于汽机和辅助系统的用汽，最终产生电力。
3.The steam generator design requirements are to produce saturat
ed steam with less than 0.5percent moisture by weight.
SG设计要求其二次侧产生的蒸汽湿度小于0.5%。
4.The tubesheet and the heat transfer tubes form the boundary be
tween the radioactive primary system and the non-radioactive se condary system.
强放射性的一次侧和无放射性的二次侧的隔离是通过传热管和管板实现。
5.Reactor coolant enters the steam generator consists of the inle
t nozzle. Flows through the inlet chamber, U tubes, outlet cham ber and leaves it from outlet nozzle.
主冷却剂先流经入口管，然后进入到入口水室，经U型传热管到出口水室，最后通过出口管离开SG。
6.The secondary side of the steam generator consists of the feed
water and steam nozzles, the tube bundle and supports, the tub
e bundle wrapper, primary and secondary moisture separators and
appropriate instrumentation and blowdown penetration.
二次侧由以下部件组成：给水和蒸汽管，传热管及其支撑件，管束围筒，
一、二级汽水分离器，相关的仪表，排污管组成。
7.The lower shell is the evaporator containing the tube bundle a
nd the upper shell is the steam drum containing the steam separ ating and drying equipment.
壳体的下部为含有传热管的蒸发器，上部是汽水分离和蒸汽干燥的蒸汽室。
8.The steam generator operates as a natural circulation boiler.
SG是自然循环式的锅炉。
9.In order to support and align the steam generator tubes and pr
event flow induced movement, tube support plates are provided.
为了固定SG传热管和防止流动导致的移动，安装有管子支撑板。
10.The blowdown line is provided to remove corrosion products whi
ch would concentrate at the tubesheet.
排污管线的设置用于排出腐蚀产物，腐蚀产物会在管板处沉积。
11.Nuclear power plants are equipped with N-16 detector on the st
eam line for indicating U-tube leakage.
在SG的二次侧主蒸汽管道旁设置有N-16放射性探测仪，用于检测U型管是否存在泄漏。
12.There are two types of steam generator level indication: wide r
ange and narrow range.
SG水位指示有两种类型：宽量程和窄量程。