Reactor Safety.............................................................................

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有关核的英语作文

有关核的英语作文Title: The Importance of Nuclear Energy: A Comprehensive Overview。

In the modern era, energy plays a pivotal role in sustaining economic development, technological advancement, and improving the quality of life for billions worldwide. Among the various sources of energy, nuclear power stands out as a significant contributor. This essay delves into the multifaceted aspects of nuclear energy, exploring its benefits, challenges, and future prospects.Firstly, nuclear energy offers unparalleled energy density. Unlike fossil fuels, which release harmful greenhouse gases during combustion, nuclear power generates electricity through controlled nuclear reactions, emitting minimal greenhouse gases. This characteristic makes nuclear energy a crucial component in mitigating climate change and reducing air pollution, thereby safeguarding environmental sustainability.Moreover, nuclear power provides a reliable and stable source of electricity. Nuclear plants operate continuously, irrespective of weather conditions or fluctuations in fuel supply, ensuring a consistent power output. Thisreliability is particularly valuable in meeting the baseload demand for electricity, complementing intermittent renewable energy sources like solar and wind.Furthermore, nuclear energy contributes to energy security by diversifying the energy mix. With finite reserves of fossil fuels and growing geopolitical tensions surrounding their extraction and transportation, nuclear power offers a domestically producible and geopolitically independent energy source. This reduces reliance on imports and enhances energy independence for nations worldwide.Despite its numerous advantages, nuclear energy is not without challenges. Safety concerns, such as the risk of nuclear accidents and the disposal of radioactive waste, remain significant issues. However, advancements in reactor design, stringent safety regulations, and improved wastemanagement techniques have substantially mitigated these risks over the years.Another challenge is the high upfront capital costs associated with nuclear power plants. Building and commissioning a nuclear facility require substantial investments and lengthy regulatory approvals, deterring some investors and policymakers. Nevertheless, the long-term economic benefits, including low operational costs and stable electricity prices, often outweigh the initialcapital expenditure.Additionally, public perception and societal acceptance of nuclear energy vary widely. While some view it as aclean and reliable energy source, others harbor concerns regarding safety, proliferation of nuclear weapons, and environmental impacts. Addressing these perceptions through transparent communication, public engagement, and education is crucial in fostering broader acceptance of nuclear power.Looking ahead, nuclear energy holds immense potentialin addressing global energy challenges. Advanced reactortechnologies, such as small modular reactors (SMRs) and next-generation designs, promise enhanced safety features, increased efficiency, and reduced proliferation risks. Moreover, ongoing research in nuclear fusion offers the tantalizing possibility of virtually limitless, clean energy in the future.In conclusion, nuclear energy occupies a vital position in the global energy landscape, offering a potent combination of reliability, sustainability, and security. While challenges persist, ongoing technological advancements and informed policymaking can unlock the full potential of nuclear power in shaping a more sustainable and prosperous future for generations to come.。

反应堆堆型名词术语精品集合

反应堆堆型名词术语精品集合，我发的不容易过来看看啊1.1 （核）反应堆(nuclear) reactor 能维持可控自持链式核裂变反应的装置。

注释：更广泛的意义上讲，反应堆这一术语应覆盖裂变堆、聚变堆、裂变聚变混合堆，但一般情况下仅指裂变堆。

1.2 动力（反应）堆power reactor 用于发电、推进和供热等用途的反应堆。

1.3 供热（反应）堆heating reactor 用于向居民和（或）工业设施等供热的反应堆。

1.4 研究（反应）堆research reactor 主要作基础研究或应用研究用的反应堆，例如：a. 高通量反应堆b. 脉冲反应堆c. 材料试验反应堆d. 零功率反应堆1.5 生产（反应）堆production reactor 主要用于生产易裂变材料的反应堆。

除另有说明外，通常指生产钚的反应堆。

1.6 增殖（反应）堆breeder reactor 转换比大于1的反应堆。

1.7 空间反应堆space reactor 将核裂变反应产生的能量转换成电能作为航天飞行器电源的一种核反应堆。

1.8 微型中子源反应堆miniature neutron source reactor 用高浓金属铀作燃料元件，金属铍作反射层，轻水慢化，自然对流冷却的一种作中子源用袖珍式核反应堆，可用于中子活化分析及少量研究用短寿命示踪同位素的制备。

1.9 零功率（反应）堆临界装置zero－power reactor；zero－energy reactor critical assembly 设计在极低功率下运行，不需要专门设置冷却剂系统的反应堆。

1.10 脉冲（反应）堆pulsed reactor 用于产生短持续时间、强中子脉冲的反应堆。

1.11 实验（反应）堆experimental reactor 主要为取得设计或研制一座反应堆或一种堆型所需的堆物理或堆工程数据而运行的反应堆。

1.12 示范（反应）堆demonstration reactor 为证明某种反应堆在技术上的可行性和研究其经济潜力而设计的反应堆。

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_核反应堆安全分析_课程建设的实践探索_李小华 (1)

“核反应堆安全分析” ( 以下简称 “反应堆安全分析”) 课程的前身是 1998 年 9 月 “中南工学院 ( 南华大学前身之一) ” 面向核工程与核技术专业开设的核电厂控制与安全课程 ( 总 32 学时) 。该课程分别于 2009 年和 2011 年更名为核反应堆安全与运行 ( 总 48 学时) 、核反应堆安全分析 ( 总 48 学时) ，经过老、中、青三代老师孜孜不倦地建设，已形成了完整的教学体系，积累了丰富的教学经验; 现为南华大学核反应堆工程、核工程与核技术专业的专业必修课 ·92·
·91·
HIGHEＲ EDUCATION OF SCIENCES
2014 年第 5 期 ( 总第 117 期)
始终坚守核类专业人才培养的前沿阵地，先后被中国核工业集团公司授予 “ ‘十五’ ‘十一五’ 期间为核工业培养和输送人才 ‘突出贡献奖’”。［2］在中国核电政策由 “适度发展” 调整为 “积极发展 ”，核能与核技术事业迎来了一个新发展的大好形势下，南华大学利用其前身 “中南工学院” 和 “核工业第六研究所” 在核类专业高级人才培养和科学研究的历史积淀，经湖南省教育厅批准 ( 湘教通［2007］74 号) ，在中央财政支持地方高校发展专项资金、湖南省重点学科 ( 核技术及应用) 、国防科工委重点建设专业 ( 核工程与核技术) 、国防紧缺专业 ( 核技术、核化工与核燃料循环) 和国家第一类特色专业 ( 核工程与核技术) 等建设资金的资助下，于 2007 年在原 “核工程与核技术” 专业的基础上，新开设了核反应堆工程、核技术、辐射防护与环境工程、核物理、核安全工程、核化工与核燃料工程 6 个核类专业，并于同年 9 月开始面向全国招生。南华大学核类专业高级人才培养规模由 2000 年招收 80 人逐渐增加到 2013 年的 355 人。在核类专业高级人才培养规模的扩大、专业类别增加、专业建设取得丰硕成果的背景下，为了适应核类专业高级人才培养的要求，南华大学核反应堆物理分析、核反应堆热工分析、核反应堆安全分析等核工程类专业课程性质、地位也发生了改变; 新增设了压水堆核电厂的运行、核电厂概率安全评价、先进核能概述等一批专业课程; 开展了核反应堆物理课程设计、核反应堆工程课程设计的实践教学工作，加强了对学生实践能力的培养。

常用安全工程专业英汉词汇

常用安全工程专业英汉词汇为了便于一些同学使用英文撰写安全领域的论文和阅读安全领域的英文参考资料，下面给出了一些常见的安全领域中英文专业词汇。

安全Safety安全边界Safety limits安全辩证法Safety dialectic安全标志Safety sign安全标准Safety standards安全玻璃Safety glass安全操作规程Safety regulations for operations安全车Security vehicle安全成本Safety cost安全措施Safety measures安全带(飞行器) Safety belts(aircraft)安全带Safety belts安全灯Safety lamps安全等级Safety level安全电气工程Safety electric engineering安全调度(电力系统) Security dispatching(electrical power systems)安全度Degree of safety安全对策Safety countermeasures安全阀Relief valves安全法规Safety laws and regulations安全法学Safety jurisprudence安全防护Safety protection安全防护照明Protective lighting安全风险Safe risk安全工程Safety engineering安全工程技术人员Technical personnel of safety engineering安全工程师Safety engineer安全工作Safety work安全工作体系Safetywork system安全观Safety outlook安全管理Safety management安全管理Safetymanagement安全管理体系Safety administration system安全规程Safety regulation安全航速Safe ship speed安全极限Safety margins安全计量Safety measurements安全计量学Safety metrology安全技术Safety techniques安全监测Safety monitoring安全监察Safety supervision安全监控Safety supervising安全监控系统Safety monitoring system安全检测与监控技术Safety detection & monitoring-controlling technique 安全检查Safety inspection安全检查表Safety check lists安全健康产品Health and safety production安全鉴定Safety appraisal安全教育Safety education安全教育学Safety pedagogy安全经济效益Safety cost effectiveness安全经济学Safety economics安全考核Safety check assessment安全科学Safety science安全科学技术Safety technique安全壳(反应堆) Containments(reactors)安全壳系统Containment systems安全可靠性Safety reliability安全控制技术Safety control technology安全控制论Safety cybernetics安全离合器Overload clutches安全立法Safety legislation安全联锁系统Safety interlocking system安全联轴器Safety couplings安全伦理学Safety ethics安全美学Safety aesthetics安全模拟与安全仿真学Safety simulation & imitation 安全模式Safety pattern安全培训Safety training安全评价Safety assessment安全气囊Safety gasbag安全墙Safety walls安全人机界面Safetyman-machine interface安全人体工程Safety livelihood engineering work安全人体学Safety livelihood science安全人因工程学Safety human factors engineering安全认证Safety approval and certification安全三级教育Three degree safety education安全设备Safety equipment安全设备工程Safety equipment engineering work安全设备机电学Safety equipment electro-mechanics 安全设备卫生学Safety equipment hygienic安全设备学Safety guard science安全设计Safety design安全社会工程Safety social engineering work安全社会学Safety sociology安全审核员Safety auditor安全生产Safety production安全生理学Safety physiology安全生育Safety fertility安全史Safety history安全事故Safe accidents安全事故罪Crime of safety accident安全试验Safety experiment安全疏散Evacuation安全素质Safety disposition安全体系学Science of safety system安全统计Safety statistics安全头罩Hood安全投入Safety investment安全危害因素Hazardous elements安全唯物论Safety materialism安全委员会Safety committee安全文化Safety culture安全系数Safety factor安全系统Safety system安全系统分析Safety system analysis安全系统工程Safety systematic engineering work 安全系统学Safety systematology安全线迹缝纫机Safety stitch sewingmachines安全香料Safety flavoring安全销Shear pin安全心理学Safety psychology安全信号Safety signals安全信息Safety information安全信息工程Security in information technology 安全信息论Safety information theory安全行为Safe behavior安全性Nature of safety安全性理论Safety theory安全性约束Safety restrain安全宣传Safety propaganda安全训练Safety training安全烟Safe cigarettes安全仪表Safety instruments安全意识Safety consciousness安全因素Safety elements安全隐患Safety potential安全用电Electric safety安全阈值Safe threshold value安全员Safety personnel安全运筹学Safety operation research安全运输Safety transportation安全栅栏Safety barrier安全炸药Safety explosives安全哲学Safety philosophy安全执法Safety law enforcement安全质量隐患Safety quality potential安全中介组织Intermediary organization of safety 安全装置Safety devices安全自组织Safety self-organizing安全组织Safety organization靶场安全Range safety搬运安全Carrying safety保安矿柱Safety pillars保护装置Protection devices保险机构(引信) Safety and arming devices保险装置Physical protection devices报警设备Warning equipment报警系统Warning systems爆破安全Shotfiring safety爆破安全仪表Safety blasting instruments爆炸安全工程Explosion safety engineering本质安全Intrinsic safety本质安全电路Intrinsically safety circuit部门安全工程Industrial safety engineering产品安全性能Safety functions充气安全装备Inflatable devices船舶安全Ship safety导弹安全Guided missile safety低压安全阀Low-pressure safety valve地下生保系统Underground life support systems 电力安全Power system safety电气安全Electrical safety电子防盗器Electron theft proof instrument短路事故Short circuit accidents堆安全研究所Institute for reactor safety反应堆安全Reactor safety反应堆安全保险装置Reactor safety fuses防爆Explosion-proofing防爆试验Explosion-proof tests防尘工程Dust control engineering防毒Anti-toxin防毒工程Industrial poisoning control engineering防高温High temprature prevention防护设备Safeguard防火Fire safety防火堤Fire bank防冷To be protected from cold防热Solar heat protection防暑Heat stroke prevention防尾旋系统Anti-spin systems放射性Radioactivity放映安全技术Safety techniques of film projection飞机安全装备Air emergency apparatus飞机防火Aircraft fire protection飞行安全Air safety飞行安全装备Flight safety devices风险评价与失效分析Risk assessment and failure analysis 辐射防护Radiation protection辐射分解Radiolysis辐射屏蔽Radiation shielding辐射危害Radiation hazards妇女劳动保护Protection of women labour force高低温防护High and low temperature protection高温作业Hotwork个人飞行安全装备Personal flight safety fitting个体保护用品Individual protection articles个体防护装备Personal protection equipments工厂安全Factory safety工程事故Engineering accidents工伤事故Industrial accident工业安全Industrial safety工业防尘Industrial dust suppression工业防毒Industrial gas defense工业通风Industrial ventilation工业灾害控制Control of industrial disaster工业照明Industrial lighting公共安全Public safety共同安全署(美国) Mutual Security Agency (U. S. )故障保险Fail safe锅炉安全Boiler safety锅炉爆炸事故Boiler explosion accidents锅炉事故Boiler breakdowns国际海上人命安全公约International convention for safety of life at sea 国家安全法National security law过卷保护装置Over winding safety gears航空安全Aviation safety航天安全Aerospace safety航天救生Space security航天器屏蔽Spacecraft shielding航行安全Voyage safety核安全Nuclear safety核安全保障Nuclear safeguard核安全保障规章Nuclear safeguard regulations核防护Nuclear protection厚板焊接式高压容器Thick platewelded high pressure vessels化工安全Chemical engineering safety火灾事故Fire accident激光安全Laser safety激光安全标准Laser safety standard激光危害Laserhazard激光眼睛防护Laser eye protection集体安全体系Collective security system计算机安全Computer safety家庭安全Family safety监测保护系统Surveillance protection system降温Falling temperature交通安全教育Traffic safety education交通运输安全Traffic safety结构安全度Structure safety金融安全区Financial safety zone井下安全阀Subsurface safety valve警报Alarm静态安全分析(电力系统安全分析)Electrostatic safety analysis救护Medical aid救生设备Rescue equipment救生装置Survival devices矿山安全Mine safety矿山安全仪器Coalmine safety apparatus矿业安全配备公司(美国)Mine Safety Appliances Company矿用安全型Mine permissible type劳保服装Safety and industrial costume劳保条例Labour insurance regulations劳动安全Labour safety劳动保护Labour protection劳动合同Labour contract劳动条件Labour conditions联合国安全理事会United Nations Security Council流星防护Meteoroid protection漏风Air leakage旅游安全Tourist safety美国公路安全研究所Highway Safety Research Institute (U. S. )美国国家安全委员会The National Security Council (U. S. )美国劳动部职业安全与卫生局Occupational Safety and Health Administration (Department of Labor, U. S. A. )美国全国公路交通安全管理局National Highway Traffic Safety Administration 逆电晕Corona quenching欧安会(1975) European Security Conference (1975)欧洲集体安全体系European collective security system欧洲青年安全会议European Youth Security Conference匹兹堡采矿安全研究中心Pittsburgh Mining and Safety Research Center (PMSRC)破损安全设计方法Fail-safe designmethods企业安全Enterprise safety起重安全Lifting safety汽轮机事故Steam turbine accidents潜在危险Potential hazards驱进速度Migration velocity全球海上遇险与安全系统Global maritime distress and safety system缺水事故Water deficiency emergence (or accident)绕带式高压容器Band wrapped high pressure vessels热曝露Heat exposure热套式高压容器Multiwall high pressure vessels人为失误Man-made faults日美安全条约(1951)SecurityTreaty between the U. S. and Japan (1951)日美共同合作和安全和约(1960)Treaty of Mutual Cooperation and Security between the U. S. and Japan伤亡率Rate of casualty伤亡事故Casualty accidents烧毁事故Burn up accidents设备安全Equipment safety设备事故Equipment accident社区安全Community safety渗毒Toxin leaching生产噪声与振动控制Control of occupational noise & vibration生活安全Living safety生态安全Ecological safety失速警告系统Stall-warning systems食品安全Food safety事故Accident事故处理Accident handling事故分析Accident analysis事故类别Accident type事故模型Accident model事故频率Accident frequency事故树分析Accident tree analysis事故损失Accident loss事故统计Accident statistics事故预防Accidentprevention事故致因理论Accident-causing theory适航性Air worthiness适毁性Crashworthiness水雷保险器Mine safety seitchs苏必利尔湖矿山安全委员会Mines Safety Council Lake Superior 太平洋安全银行Security Pacific Bank提升安全装置Lifting safety features天然放射性Natural radioactivity听力保护Hearing protection通风与空调工程Ventilation engineering & air conditioning通信安全Communication safety头部保护Head protection危害公共安全罪Offences againstpublic security危急保安器Emergency protector危险辨识Hazard identific危险等级Danger level危险评估Risk assessment危险性Risk危险源Dangerous source危险源控制Dangerous source control微流星屏蔽Micrometeoroid shielding违章作业Operation against rules未成年工保护Protection of underage employee温度报警器Temperature alarm系统安全分析System safety analysis系统安全工程System safety engineering系统安全性System safety系统安全学System safety science消防工程Fire-fighting engineering消费安全Consumption safety信息安全Information safety行车安全Driving safety压力容器安全Pressure vessel safety压力释放Pressure relief亚洲集体安全体系Asian collective security system烟温Fume temperature眼部保护Eye protection异常气压防护Protection of anomalous barometric pressure易燃物品Inflammable article应急对策Emergency countermeasures英国矿山安全研究所Safety in Mines Research Establishment有害作业Harmful work再入屏蔽Reentry shielding职业安全卫生Occupational health and safety职业安全卫生标准Occupational health and safety standards职业安全卫生体系Occupational health and safety management system职业危害Occupational hazard重大危险源Major hazard sources主动安全性Active safety自动保护停机Automatic safety stop作业环境卫生Work environment hygiene座椅背带Seat harness上述词汇选自以下来源，部分词汇做了一些修改。

华龙一号机组MSLB事故下反应堆安全性仿真分析

3. China Nuclear Operation Technology Corporation LTD., Wuhan,430223,China）
Abstract：Relying on the data of The Third-generation Nuclear Power Unit HPR1000, reactor safety after MSLB accident of HPR1000 unit under the thermal shutdown condition was simulated and analyzed, and the unit's key parameters under the accident were obtained. The simulation results showed that under the thermal shutdown condition the MSLB accident occurred when the boron concentration of primary circuit was low, and a set of control rod components with the highest negative reactivity were stuck in the fully withdrawn position, the reactor core would return to criticality, after a series of main reactor protection actions and special safety facilities, the reactor would eventually shut down.

反应堆安全分析英文缩写

ABWR advanced boiling water reactor 先进沸水堆APWR advanced pressurized water reactor 先进压水堆AP advance passive plant 先进非能动电厂ADS accelerator driven system加速器驱动机构AFP auxiliary feedwater pump 辅助给水泵ATWS anticipated transient without screen 未能停堆的预计瞬变ANSI American national standards Institute 美国标准协会BDBA beyond design basic accident 超设计基准事故BOL beginning of life 寿期初CEFR china experimental fast reactor 中国实验快堆CSS containment spray system 安全壳喷淋系统CVCS chemical and volume control system 化容控制系统CSRDM control and safety rod drive mechanism 控制棒安全棒驱动机构CHF critical heat flux 临界热流密度DHX direct heat exchanger直接热交换器DBA design basic accident 设计基准事故DOE department of energy 美国能源部DCH direct containment heating 直接安全壳加热DNBR departure from nuclear boiling ratio 偏离泡核沸腾比ESD emergency shutdown device 紧急停堆仪器ECCS emergency core cooling system 应急堆芯冷却系统EPR European pressurized reactor 欧洲压水堆ESS emergency shutdown system 紧急停堆系统EFS emergency feedwater system 应急给水系统ESF emergency safety features 专设安全设施EPRI the electric power research institute 美国电力研究会EOL end of life 寿期末EFPD effective full power days 有效满功率天数EM evaluation model 评价模型EFW emergency feed water 紧急供水GFR gas-cooled fast reactor 气冷快堆HEM homogeneous equilibrium model 均相平衡模型HPIS high pressure injection system 高温安注系统HTGR high-temperature gas-cooled reactor 高温气冷堆HTTR high-temperature test reactor 高温工程试验堆IFR integral fast reactor 整体快堆IHX integral heat exchanger 中间热交换器INSAG International nuclear safety 国际核安全咨询IDCOR industry degraded core rule making 工业退役堆芯规则LFR lead-cooled fast reactor 铅冷快堆LPIS low pressure injection system 低压安注系统LOCA loss of coolant accident 失水事故LOFA loss of flow accident 失流事故LOFW loss of boilen feed water 丧失蒸汽发生器给水LOOP loss of offsite power 热阱丧失事故MHTGR modular high-temperature gas-cooled reactor 模块化高温气冷堆MSR molten salt reactor 熔盐堆MSIV main steam isolation value 主蒸汽管道隔离阀MSLB main steam line break 主蒸汽管道破裂NRC nuclear regulatory commission 美国核管会PBMR pebble bed modular reactor 球床模块式反应堆PCRV prestressed concrete reactor vessel 预应力混凝土反应堆容器PIUS process inherent ultimate safety 过程固有最终安全堆PRA probabilistic risk assessment 概率风险评价PSA probabilistic safety assessment 概率安全评价PFBR prototype fast breeder reactor 快中子增殖堆RCS reactor coolant system 反应堆冷却系统RCP reactor coolant pump 反应堆冷却剂泵POH reactor outlet header 反应堆出口集管RIH reactor inlet header 反应堆入口集管RHR residual heat removal 余热排出系统RELAP reactor excursion and leak analysis program 反应堆泄漏分析程序RSS reactor safety study 反应堆安全研究RIA reactivity insertion accident 反应堆引入事故SBLOCA small break loss of coolant accident 小破口失水事故SARP severe accident research program 严重事故研究项目SFR sodium-cooled fast reactor 钠冷快堆SIR safe integral reactor 固有安全堆SCWR super-critical-water reactor 超临界水冷堆SPX super-phoenix reactor 超级凤凰堆SGTR steam generator tube rupture 蒸汽发生器传热管道破裂事故SGCC state grid corporation of china 国家电网公司THTR thorium high-temperature nuclear reactor 钍高温气冷堆VHTR very-high-temperature reactor 超高温气冷堆。

压水堆失水事故最佳估算方法研究

压水堆失水事故最佳估算方法研究林诚格;刘志弢n;赵瑞昌【摘要】传统使用的失水事故分析模型和方法被公认是极度保守的,它带来不必要的过量裕度,限制了运行核电厂和新建核电厂的功率提高,并限制了运行的灵活性.最佳估算方法的发展和应用为消除这些不必要的限制提供了可能.本文介绍了压水堆失水事故最佳估算方法的进展;叙述了最佳估算方法及评价方法,特别是不确定性分析方法,介绍了目前已获使用的最佳估算程序.【期刊名称】《核安全》【年(卷),期】2010(000)001【总页数】12页(P1-12)【关键词】失水事故;最佳估算;不确定性分析;CSAU;ASTRUM【作者】林诚格;刘志弢n;赵瑞昌【作者单位】国家核安全局,北京,100035;国家核电技术公司,北京,100190;国家核电技术公司,北京,100190【正文语种】中文冷却剂丧失事故(Lost of coolant accident,简称LOCA),是指反应堆冷却剂流失速率超过正常补给系统补给能力的事故,对轻水堆,也叫做失水事故。

一回路一根管道或辅助系统的管道破裂,一回路或辅助系统管道上的阀门意外打开或不能关闭,输送一回路介质的泵的轴封或阀杆泄漏等,均可能引起失水事故。

失水事故是轻水堆核电厂最重要的设计基准事故之一。

发生失水事故,意味着堆芯内冷却条件恶化,堆芯内积蓄的大量热量和裂变产物的衰变热无法导出,其后果甚至可能导致轻水堆核电厂纵深防御体系的四道屏障——元件芯块、包壳、一次压力边界和安全壳功能全部丧失。

失水事故的后果随着破口的大小、位置和装置的初始状态的不同而不同,在AP600/ AP1000的事故分析中,凡破口总截面等于或大于1.0 ft2(合0.09 m2),即定义为大破口;而破口总截面小于 1.0 ft2,则定义为小破口[1]。

AP600/AP1000失水事故的发展阶段如下(如图 1所示)：◦喷放(Blowdown)阶段,从发生破口、紧急停堆、触发CMT和安注箱注水到堆芯、直到喷放结束。

安全工程专业英语

安全工程专业英语作业Unite SixteenThe History of Nuclear Power Plant Safety Safety has been an important consideration from the very beginning of the development of nuclear reactors. On December 2 , 1942 ,when the first atomic reactor was brought to criticality, Enrico Fermi had already made safety an important part of the experiment. In addition to a shutoff rod, other emergency procedures for shutting down the pile were prepared in advance.Fermi also considered the safety aspects of reactor operation. Shortly before the reactor was expected to reach criticality, Fermi noted the mounting tension of the crew. To make sure that the operation was carried out in a calm and considered manner, he directed that experiment be shut down and that all adjourn fou lunch. With such leadership in safety at the very beginning, it is no wonder that the operation of reactions to date has such an impressive track record.译：从核反应堆发展的初期开始，安全始终被放在一个非常重要的方面。

Materials challenges in nuclear energy

Materials challenges in nuclear energyS.J.Zinkle a ,⇑,G.S.Was baOak Ridge National Laboratory,P.O.Box 2008,Oak Ridge,TN 37831,USAbNuclear Engineering and Radiological Sciences Department,University of Michigan,Ann Arbor,MI 48109,USAAbstractNuclear power currently provides about 13%of electrical power worldwide,and has emerged as a reliable baseload source of elec-tricity.A number of materials challenges must be successfully resolved for nuclear energy to continue to make further improvements in reliability,safety and economics.The operating environment for materials in current and proposed future nuclear energy systems is summarized,along with a description of materials used for the main operating components.Materials challenges associated with power uprates and extensions of the operating lifetimes of reactors are described.The three major materials challenges for the current and next generation of water-cooled ﬁssion reactors are centered on two structural materials aging degradation issues (corrosion and stress corrosion cracking of structural materials and neutron-induced embrittlement of reactor pressure vessels),along with improved fuel system reliability and accident tolerance issues.The major corrosion and stress corrosion cracking degradation mechanisms for light-water reactors are reviewed.The materials degradation issues for the Zr alloy-clad UO 2fuel system currently utilized in the majority of commercial nuclear power plants are discussed for normal and oﬀ-normal operating conditions.Looking to proposed future (Gen-eration IV)ﬁssion and fusion energy systems,there are ﬁve key bulk radiation degradation eﬀects (low temperature radiation hardening and embrittlement;radiation-induced and -modiﬁed solute segregation and phase stability;irradiation creep;void swelling;and high-temperature helium embrittlement)and a multitude of corrosion and stress corrosion cracking eﬀects (including irradiation-assisted phe-nomena)that can have a major impact on the performance of structural materials.Ó2012Acta Materialia Inc.Published by Elsevier Ltd.All rights reserved.Keywords:Nuclear materials;Radiation eﬀects;Stress corrosion cracking;Structural alloys (steels and nickel base);Nuclear fuels1.IntroductionAccess to reliable,sustainable and aﬀordable energy is viewed as crucial to worldwide economic prosperity and stability [1,2].Nuclear ﬁssion energy has emerged over the past 40years to become a reliable baseload source of clean and economical electrical energy.As of 2011,there were 435nuclear reactors in operation worldwide,produc-ing 370GW e of electricity [3].Another 108units or 108GW e are forthcoming (under construction or on order),for a total of 543units and 478GW e of electrical capacity.The largest producer of power from nuclear energy is the USA,with 104commercial reactors licensed to operate at 65sites,producing a total of 103GW e ofelectricity.These provided just under 20%of the nation’s total electric energy generation and more than 30%of worldwide nuclear generating capacity.Worldwide,nuclear energy provides about 13%of the electrical demand [1].Given that nuclear power has very low carbon emission [2]and that energy generation currently accounts for 66%of worldwide greenhouse gas emissions [4],nuclear energy is considered an important resource in managing atmospheric greenhouse gases and associated climate change [1].The core of a nuclear reactor presents an exceptionally harsh environment for materials due to the combination of high temperature,high stresses,a chemically aggressive coolant and intense radiation ﬂuxes.Many of the features that make reactors attractive from a physics perspective (e.g.high speciﬁc power,self-sustaining reaction)exert high operational burdens on structural materials.For example,1359-6454/$36.00Ó2012Acta Materialia Inc.Published by Elsevier Ltd.All rights reserved./10.1016/j.actamat.2012.11.004⇑Corresponding author.Tel.:+18655765785.E-mail address:zinklesj@ (S.J.Zinkle)./locate/actamatAvailable online atActa Materialia 61(2013)735–758the recoverable energy from each235Uﬁssion reaction is $200MeV,which is about eight orders of magnitude per atom higher than typical chemical reactions.As a result, typical power densities in commercial nuclear reactor cores are$50–75MW th mÀ3,which is nearly two orders of mag-nitude higher than the average power density in the boiler furnace of a large-scale coal power plant.This intense pro-duction of heat is accompanied by the generation of ener-getic neutrons(which serve to sustain theﬁssion reaction) and gamma radiation,which can degrade materials by dis-placement damage and radiolysis processes,respectively. Recent activities to extend the operating lifetime of current water reactors,to develop advancedﬁssion reactor con-cepts with greater functionality and capability,and the coming emergence of fusion energy represent even greater demands on materials[5–8].1.1.Types of nuclearﬁssion reactorsThe predominant reactor design worldwide is the pres-surized water reactor(PWR),accounting for two-thirds of the installed capacity,followed by boiling water reactors (BWRs)at21%and heavy-water reactors at14%of installed capacity,respectively(Table1)[3].All of these water-cooled reactors use ceramic fuel pellets consisting of UO2or otherﬁssile actinide oxides to generate heat. The ceramic pellets are stacked inside of long Zr alloy tubes (fuel cladding)that transfer the nuclear heat toﬂowing water coolant and serve as the primary barrier containing the volatile radioactiveﬁssion byproducts.The remaining 5%of installed nuclear energy comes from gas-cooled reac-tors,graphite-moderated reactors and liquid metal cooled reactors(Table1).The vast majority of the reactors listed in Table1are classiﬁed as Generation II reactors[9],which were designed in the1960s and predominantly achieved initial commercial operation from the1970s through the1990s.These reactors are distinguished from Generation I designs(1950s-60s), which were early commercial prototype and demonstration reactors,and Generation III reactors,designed in the1990s to incorporate signiﬁcant advances in safety and economics [9].Generation III reactor construction for the past decade has been centered in Asia,with a few units recently built in Europe.The current generation of light-water reactors (LWRs),Generation III+,include still further advance-ment in economics and safety,such as passive heat removal systems.There are a total of108Generation III and Generation III+reactors on order or under construction around the world,and of those,89are PWRs.Given the high representation of PWRs and BWRs in the world’sﬂeet,materials issues in these two types of reac-tors are of greatest interest.And of the many materials in a reactor,those that experience the most extreme conditions (stress,corrosion,and radiation)are most important for maintaining plant safety and reliability.Fig.1shows a schematic of the major components in the primary and secondary circuits of a PWR[10].Pressurized water ($15.5MPa)in the primary circuit enters the reactor core at$275°C,picks up heat from the reactor core with a core exit temperature of$325°C,and transfers the heat across the U-tubes in the steam generator to water at a lower pressure.This water turns to steam that powers the tur-bine,and is condensed and recirculated.Fig.1also lists the alloys used throughout the primary and secondary cir-cuits,all of which are in contact with high-temperature water and are subject to signiﬁcant mechanical stress. Alloys inside(and including)the reactor vessel are also subject to varying levels of radiation,which produces displacement damage and radiolytic decomposition of the coolant water.Major pressure boundary components (reactor pressure vessel,pressurizer,steam generator, steam lines,turbine and condenser)are made of either low carbon or low alloy steel.Austenitic stainless steels (Types304,304L,316,316L,321,347)dominate the core structural materials,as well as serving for cladding(308SS and309SS)on the inside surface of the reactor pressure vessel and pressurizer.Higher strength components such as springs and fasteners are made of nickel-base alloys. Vessel penetrations and steam generator tubes are made of nickel-base alloy690(previously alloy600,which was found to provide insuﬃcient resistance to stress corrosion cracking).Condenser tubes are generally made of titanium or stainless steel.The selection of nickel-base alloys and austenitic stainless steels for core internals and the steam generator tubes is driven by the need for good aqueous corrosion resistance at high temperatures.These alloys have low corrosion rates due to the formation of chro-mium-bearing spinels that form adherent,high-density protective surface layers that grow very slowly at operating temperatures.Table1Power reactors by type,worldwide[3].Reactor type#Units Net MW e#Units Net MW e#Units Net MW e(in operation)(forthcoming)(total)Pressurized light-water reactors(PWR)267246555.18993,014356339569.1 Boiling light-water reactors(BWR)8478320.6680569086376.6 Gas-cooled reactors,all models178732.01200188932.0 Heavy-water reactors,all models5125610.0851125930722.0 Graphite-moderated reactors,all models1510219.0001510219.0 Liquid-metal-cooled reactors,all models1560.0410*******.0 Totals435369996.7108107,896543477894.7 736S.J.Zinkle,G.S.Was/Acta Materialia61(2013)735–758The main diﬀerence between PWRs and BWRs is that the latter consists of a single water circuit designed for boil-ing to occur in the core with steamﬂowing directly to the turbine,which eliminates the steam generator and pressur-izer found in the PWR.The operating temperatures are comparable for both reactor types($300°C),with compa-rable stress and radiation environments.As such,most of the structural alloys are very similar between the two reac-tor types.The main diﬀerence is in the zirconium alloys used as fuel rod cladding,with BWR fuel cladding opti-mized for corrosion resistance in higher oxygen potentials and PWR fuel cladding optimized for resistance to hydro-gen absorption in the low potential environment of the core.Typical zirconium alloy cladding materials used in BWR and PWR reactors are summarized in Table2. Diﬀerences in oxygen potential result in signiﬁcant impacts on the stress corrosion degradation of materials through-out the water circuit in both reactor types,as will be discussed in Section2.1.The last reactor design that is in signiﬁcant use world-wide is the pressurized heavy water reactor(PHWR),the most prevalent version being the CANDU(CANadian Deuterium Uranium)reactor.This reactor uses heavy water as the moderator and primary coolant,transferring heat to light water via a steam generator.The key charac-teristic of this reactor is the use of deuterium as a modera-tor,for which neutron absorption is low enough to permit the use of natural(unenriched)uranium,thus bypassing the need for expensive enrichment facilities.A major diﬀer-ence in materials in this system vs.LWRs is the use of Zr–Nb pressure tubes that house the Zircaloy-clad fuel and the high pressure D2O.These tubesﬁt into Zircaloy-4calan-dria tubes that pass through a thin walled stainless steel calandria vessel,which also contains the lowtemperature Table2Summary of typical commercial zirconium alloys used as cladding in PWRs and BWRs.Reactor type Zr alloy composition Thermomechanical treatmentBWR Zircaloy-2(1.5%Sn–0.15%Fe–0.1%Cr–0.05%Ni)RecrystallizedPWR Zircaloy-4(1.5%Sn–0.2%Fe–0.1%Cr)Cold-worked and stress relief anneal PWR ZIRLO(1–2%Nb–1%Sn–0.1%Fe)Quench and temper/stress relief anneal PWR M5(1%Nb)RecrystallizedD2O moderator.Thus,zirconium alloys play a larger role as pressure boundary materials in PHWRs than they do in LWRs.Most reactors in the USA and elsewhere in the world were completed in the1970s and1980s,and today the aver-age age of theﬂeet is over30years.Fig.2shows the world-wide distribution of nuclear power plants classiﬁed by years of commercial operation[11].Since the original license period in the USA is40years,many reactor opera-tors are seeking license renewal to allow them to operate the plants for an additional20years.To date,73of the 104operating commercial reactors in the USA have received license extensions with another13applications under review,and a key question is how long can these plants be safely,reliably and economically operated.The limiting factor is whether critical materials can continue to maintain their integrity beyond60years[5].These mate-rials include reactor components,concrete,cables and bur-ied piping.So the lifetime of the current reactorﬂeet is ultimately governed by the performance of materials.1.2.Major materials degradation modes in nuclear energy systemsIn addition to satisfying standard materials design crite-ria based on tensile properties,thermal creep,cyclic fatigue and creep-fatigue,structural materials for current and pro-posed future nuclear energy systems must provide adequate resistance to two additional overarching environmentalThere areﬁve key bulk radiation degradation eﬀects (low temperature radiation hardening and embrittlement; radiation-induced and-modiﬁed solute segregation and phase stability(including amorphization);irradiation creep;void swelling;and high-temperature helium embrit-tlement)[8,12–16],and a multitude of corrosion and stress corrosion cracking eﬀects in water-cooled reactors[13,17–22]and proposed advanced reactors utilizing other cool-ants[23–26](including irradiation-assisted phenomena) that can have a huge impact on the performance of struc-tural materials in nuclear energy systems.The amount of radiation damage produced in materials from exposure to neutrons created by the nuclear energy reactions is quanti-ﬁed by the international standardized parameter[27,28]of displacements per atom(dpa);a displacement damage value of1dpa means that,on average,each atom has been displaced from its lattice site once.Neutron irradiation can produce pronounced hardening at low and intermediate irradiation temperatures due the production of high densities of nanoscale defect clusters (dislocation loops,helium bubbles,etc.),which serve as obstacles to dislocation motion.This hardening is generally accompanied by a reduction in tensile elongation and frac-ture toughness.The radiation hardening and reductions in elongation and fracture toughness typically emerge at dam-age levels above$0.1dpa and are generally most pro-nounced for homologous irradiation temperatures below 0.35T M,where T M is the absolute melting temperature [26,29–35].Fig.3shows an example of the eﬀect of moder-ate neutron displacement damage levels on the engineering stress–strain curve for austenitic stainless steel[36]and a8–9%Cr-tempered martensitic steel[35]at250°C.Both materials exhibit signiﬁcant radiation-induced increases in yield and ultimate tensile stress,large reductions in elonga-tion(particularly uniform elongation)and decreased strain hardening capacity.The reductions in elongation and strain hardening capacity have been attributed toﬂow localization(e.g.dislocation channeling)[37–44]and strain hardening exhaustion[29–31]mechanisms.In addition to the decreased elongation,neutron irradiation at low tem-perature also generally produces a decrease in fracture toughness.Fig.4summarizes some of the fracture tough-ness data for Types304and316austenitic stainless steels following irradiation at LWR-relevant conditions near 250–350°C[32,36,45–48].The fracture toughness decreases rapidly with increasing irradiation dose,and approaches a value near50MPa m1/2after5–10dpa.The reduction in fracture toughness can be of particular concern for body-centered cubic materials such as ferritic/martensitic steels if the ductile to brittle transition temperature is shifted to temperatures above cold or warm standby temperatures. The potential for neutron radiation-induced embrittlement of reactor pressure vessel steels has been intensively inves-tigated due to its importance for public safety[49].At intermediate temperatures(homologous tempera-tures>0.3T M),the increased mobility of the radiation defects produces a diverse range of potential microstruc-Age distribution of the world’s commercial nuclear power reactorsDecember2011[11].738S.J.Zinkle,G.S.Was/Acta Materialia61(2013)735–758precipitation in austenitic stainless steel for temperaturesas low as300°C[50].Void swelling(due to nucleation and growth of the supersaturation of vacancies produced by irradiation)is characterized by an initial low-swelling transient regime at low doses(during the void nucleation and initial growth phase),followed by a steady-state swell-ing regime where the volumetric swelling increase is pro-Fig.5.Precipitate phases observed in Type316austenitic stainless steel after neutron irradiation as a function of temperature and dose.Partially shaded data points at temperatures<400°C denote the presence of c phase and solid data points are for either G and related phases or an unidentiﬁed phase[50].portional to the dose [12,16,53–55].Typical post-transient steady-state swelling rates in irradiated metals are $0.2–1%dpa À1,which would produce unacceptable volumetric swelling in structural components exposed to high neutron doses.Therefore,research has focused on identifying mech-anisms that extend the low-swelling transient regime and delay the onset of the steady-state swelling regime [55,56].Irradiation creep [12,53,57–60]and irradiation growth [58–61]can cause substantial dimensional changes in addi-tion to changes due to void swelling.Irradiation growth is mainly an issue in anisotropic crystallographic systems,such as hexagonal close-packed materials;for this phenom-enon,volume is conserved but pronounced anisotropic expansion in one crystallographic direction (and shrinkage in another direction)can occur due to preferential nucle-ation of defect clusters,such as dislocation loops,on cer-tain crystallographic habit planes.Materials for nuclear energy systems that exhibit irradiation growth include graphite and pure metals or alloys based on zirconium and beryllium.The amount of deformation from irradia-tion creep is typically proportional to the applied stress and irradiation exposure,with a steady-state creep compli-ance coeﬃcient of 0.5to 1Â10À6MPa À1dpa À1for ferriticing temperature of materials in nuclear energy systems to temperatures signiﬁcantly lower than what would be estab-lished by thermal creep strength considerations.2.Materials challenges in current commercial ﬁssion reactors2.1.Operating environment for materials in existing LWRs Materials in LWRs are exposed to a variety of condi-tions.In the following,the operating environment for nor-mal,extended life and transient conditions are ed fuel disposition issues,while important,are not discussed in this paper.2.1.1.LWR materials under normal operating conditions Core materials include both fuel materials and structural components.The fuel consists of UO 2pellets in the shape of right circular cylinders with length and diameter of approximately 1cm each,loaded into 3–4m long zirco-nium alloy fuel tubes (cladding),which are grouped into fuel assemblies containing control rods or blades.In BWRs,the assemblies generally contain approximately 740S.J.Zinkle,G.S.Was /Acta Materialia 61(2013)735–758control rods are distributed throughout the square lattice and are connected to each other to form a control rod clus-ter,as shown in Fig.8.In both cases,control rods consist of stainless steel tubesﬁlled with boron carbide for neutron absorption.There is no channel box around a PWR assem-bly,so cross-ﬂow of water between assemblies is possible. The PWR and BWR cores are typically operated nonstop for18–24months between refueling operations.Low and intermediate burn-up fuel assemblies are typically moved to diﬀerent positions in the core during refueling outages to provide optimized fuel management,with a total core residence period of3–4fuel cycles(i.e.a third to a quarter of the fuel assemblies are removed each refueling cycle) until they achieve typical cumulative burn-up levels of $40–60GW days per metric ton of uranium(GWd MTUÀ1),corresponding toﬁssions in$4.2–6.4%of the original uranium atoms.Non-fuel core components consist of major structures such as the core shroud(BWR)or the baﬄe–former assem-bly(PWR),and smaller components such as bolts,springs, support pins and clips.The core shroud in a BWR is a cylindrical barrel,open at both ends,that surrounds the fuel assemblies.Water from the condenser mixes with water recirculated from the core between the shroud near the top of the vessel and is channeled down the annulusic stainless steel or nickel-base nozzles in the reactor head (PWR)or bottom(BWR),and the RPV.The RPV serves as both a pressure barrier and a con-tainment barrier for the radioactiveﬁssion products pro-duced during the nuclearﬁssion reaction,and thus plays a key role in reactor safety.The RPV is typically con-structed from carbon and low alloy ferritic steels with1–2%Mn,0.5–1%Ni,$0.5%Mo and0.15–0.4%Si[67], and has a typical wall thickness of$20cm.Older LWR pressure vessels were constructed from rolled plates that were welded to form a large cylinder,whereas newer vessels are formed from ring forgings in order to eliminate welds in the vessel“beltline”region closest to the center of the reac-tor core.The top and bottom heads are usually constructed from low alloy steel forgings,and are welded to the central cylindrical vessel(or bolted and gasketed in the case of the upper head).The internal surface of the RPV is typically clad with5–10mm of an austenitic stainless steel to pro-vide corrosion compatibility with the reactor coolant.Mul-tiple penetrations for coolantﬂow and instrumentation are made through the pressure vessel.The fast neutronﬂux is three to four orders of magnitude lower at the RPV com-pared to core internal structures[67],but it is still of suﬃ-cient intensity to cause radiation hardening,which could lead to fracture toughness embrittlement.It is important to maintain adequate levels of fracture toughness for a wide variety of operational conditions,including normal operation,cold shutdown for refueling and other mainte-nance,and postulated transient accident scenarios such as pressurized thermal shock in PWRs that would introduce cold water into the reactor vessel while the vessel is at oper-ating pressure and temperature(creating large thermal stresses and potential for crack propagation).Materials utilized in LWR cores must withstand simul-taneous application of mechanical stress,neutron irradia-tion and corrosion due to hot water or steam(see rows1 and2of Table3).Temperatures of core components are in the range275–288°C in BWRs and290–320°C in PWRs.The BWR environment is characterized by an elec-trochemical potential(ECP)in the range of150mV rela-tive to the standard hydrogen electrode,or150mV SHE, due to a combination of boiling of the water in the core and radiolysis.PWRs operate at a lower potential (<À500mV SHE)by virtue of the addition of hydrogen at a level of35cc of H2per kg of water($3ppm)to scavenge radiolysis products and lower the corrosion potential. PWR primary water also contains1000ppm B as boric acid(H3BO3)added for reactivity control and2–4ppm Li as LiOH added for pH control.The lower ECP is better for both corrosion and stress corrosion cracking of core materials and is possible in a PWR due to the lack of boil-ing.In addition to controlling pH,boron impacts the for-mation of solid corrosion products(CRUD)and corrosion of fuel cladding,as well as reactivity control of the reactor,and is brieﬂy described in Section2.2.Stresses on fuel and core components come from a variety of sources,including thermal expansion,high velocity waterS.J.Zinkle,G.S.Was/Acta Materialia61(2013)735–758741ﬂow,residual stresses due to welding,and stresses due to radiation-induced volume expansion or distortion.The unique environmental element of a reactor core is radiation.Fission results in several diﬀerent types of radia-tion that aﬀect materials in diﬀerent ways.Principal radia-tion types contributing to material degradation are the ﬁssion products,neutrons and gamma rays.Fission prod-ucts consist of high-energy($100MeV)elements of sizable mass(generally between90and150atomic mass units)that result directly from theﬁssion process.These elements are created as highly charged ions that deposit their energy within10l m of their origin.As such,except for those that are born within this distance of the fuel pellet surface,ﬁs-sion product damage is conﬁned to the fuel.Theﬁssion process releases both neutrons and gammas.Neutrons are created with an energy of$2MeV and slow down via collisions with the coolant and structural components.Neutrons are the primary source of radiation damage to core materials and fuel cladding and assembly components.Typical displacement damage exposures to the fuel cladding(replaced every$5years)are about 15dpa.The cumulative displacement damage in core inter-nal structures can approach80dpa after40years.The dis-placement damage rate decreases rapidly with increasing distance from the core due to neutron moderation(lower neutron energy resulting from energy loss via collisions with the coolant and core materials);the displacement damage levels in the RPV wall for a PWR are typically $0.05dpa after40years of operation,and the correspond-ing damage in a BWR vessel wall can be up to an order of magnitude lower.This displacement damage can result in signiﬁcant temperature-and dose-dependent changes to the microstructure(formation of dislocation loops,precip-itate formation/dissolution,void formation,radiation-induced segregation,etc.)[16],which aﬀects mechanical properties(strength/hardness,ductility,fracture toughness and embrittlement,creep,fatigue).When combined with the environment,high temperature and stress,additional modes of degradation occur such as irradiation-assisted stress corrosion cracking,corrosion fatigue and environ-mentally enhanced fracture toughness degradation.The gamma radiationﬁeld is intense and extends through-out the core,aided by(n,c)reactions in structural compo-nents.While atom displacement by gamma rays is of minor consequence,the main importance of gamma rays is in their heating and changes to water chemistry.Gamma heating can elevate temperatures in thicker components close to the fuel (such as baﬄe–former plates and bolts)by as much as 60°C above the water temperature.Gamma rays also induce radiolysis of the water and create a number of radicals that elevate the corrosion potential in the core.Corrosion poten-tial is the critical element governing stress corrosion cracking of core materials at elevated temperature.Beyond the materials contained within the reactor ves-sel,the major components aﬀected by the water chemistry environment include piping,turbine rotors and blades,the condenser and,in PWRs,the pressurizer and steam gener-ator.Historically,the main materials degradation prob-lems have been intergranular stress corrosion cracking (IGSCC)of BWR piping and of steam generator tubes and in vessel penetrations in PWRs.IGSCC of BWR pipes and steam lines made of304stainless steel was due to a combination of weld-induced residual stresses and sensiti-zation of grain boundaries caused by heat treatment of high carbon steels in the temperature region in which chro-mium carbides formed rapidly on the boundaries,depleting them of chromium and making them susceptible to attack. IGSCC of Alloy600occurred in steam generators,on both the primary and secondary sides,and was driven by a sus-ceptible microstructure and the creation of crevices on the secondary side in which crevice chemistry was favorable for intergranular attack.2.1.2.Life extension and power upratesDue to the initial high capital cost for construction of nuclear power plants relative to the cost of the fuel and other operating expenses,the levelized cost of electricity for LWRs is dominated by the amortized original cost of construction; the annualized costs associated with the fuel and operating and maintenance costs in a new nuclear power plant are esti-mated to contribute about20%of the levelized cost of nuclear electricity[68].This factor,along with the high capac-ity factor of LWRs demonstrated during the past decade,has led to signiﬁcant interest in extending the operational licenses of nuclear power plants beyond their initial term(typically 40years).Extension of reactor operating licenses for an addi-tional20years means that reactor components will be required to maintain their integrity for a period that is50% longer than the initial40-year license.This increase in opera-tional life introduces a wide range of potential materials aging issues that must be considered as part of the renewal license process[5,69].While the eﬀect of increased irradiation expo-sure is dependent on the component,the increase in operating life by50%means that displacement damage at the bottom of the top guide in a BWR may be>50dpa,while the shroud will acquire a damage level100times lower.High-ﬂuence components such as baﬄe bolts will reach damage levels exceeding100dpa.Fig.9shows a rough approximation of theﬂuence(damage)levels associated with various compo-nent failures(top)in both BWRs and PWRs or with micro-structure/property changes(bottom)and the impact of a20-year increase in operating lifetime.Life extension will increase the maximum expected damage level on the components receiving the highestﬂuence,and it will also elevate the dam-age level on the balance of components proportionately. Additional life extensions beyond20years are also being con-templated and theﬂuence(damage)level coinciding with three20-year life extensions is shown for comparison.In addition to life extension activities,a second approach to leveraging the existing capital assets of a nuclear power plant is to make modiﬁcations to the operating parameters (e.g.coolantﬂow rate)and/or changes to existing equip-ment(e.g.turbines)that enable high power levels to be achieved.These power uprate requests require detailedS.J.Zinkle,G.S.Was/Acta Materialia61(2013)735–758743。

英汉核电站分类词汇

英汉核电站分类词汇（上海728工程研究设计院提供）江苏省技术资料翻译复制公司编印一九八四年四月目录一、规范及标准 (3)1. 技术文件名称 (3)2. 规范及标准用语 (4)二、系统及设备名称 (5)1. 一回路系统（主、辅） (5)2. 主系统设备 (7)3. 主系统设备的重要部件 (7)（1）.反应堆容器（压力壳） (7)（2）.蒸汽发生器 (8)（3）.堆内构件 (10)（4）.燃料组件及燃料 (10)（5）.稳压器及卸压箱 (11)4. 辅助设备 (11)（1）.阀门 (11)（2）.管道和管件 (12)（3）.容器和离子交换 (13)（4）.热交换器 (14)（5）.其它 (14)三、运行及安全分析 (15)1. 运行、操作 (15)2. 安全分析 (16)四、机械设备的材料、制造及检修 (18)1. 材料 (18)2. 检验方法及应用 (18)3. 缺陷名称 (19)4. 焊接及加工 (20)五、力学及强度 (21)六、物理，剂量及屏蔽 (22)七、电气及控制 (22)八、土建,结构及公用设施 (23)1. 土建 (23)2. 结构 (24)3. 给排水 (24)4. 暖通 (25)一、规范及标准1.技术文件名称applicable document 适用文件a p p l i e d d o c u m e n t应用文件active 能动（的）active component 能动设备（或部件）allowance 裕量（一般指尺寸、加工）ap p ro v e批准；审定；审核a u d i t审计code 规范（如ASME）；程序（如计算机）code of Federal Regulation 联邦管理法规code of practice 实施法规（IAEA）code case 法规案例(ASME) criterion (criteria) 准则conceptual design 方案设计certification （合格）证（明）书check 校对；校核customer(user) 使用单位（用户）detail design 施工设计division 篇d i v ers i t y 多样性evaluation评定；评价，评估；计算ergonomics 人类工程学fin al des ign施工设计guide 导则guide drawing 指导图instruction 说明书identification 鉴定；鉴别；标志inactive 非能动（的）；非活性的passive 非能动（的）inspection 在役检查location 部位；位置；地点measure 措施；设施；测量manufacturer 承造厂；制造厂margin 裕量（一般物理、热工）；裕度（不宜称余量）manual 手册；说明书on site 现场observe 遵守；遵照preliminary design 初步设计program 大纲；规划；程序（计算机）part 部分public 公众provision 预防；措施（或设施）；条款prepare 编制；制订purchaser 订货单位；买方qualification 评定（资格或质量）；合格证明；资格审查rate 比率；流量；等；级rating 额定值；（额定）功率；特值regulating position (staff position) 管理机关观点revise 校核；审核review 复核；评论s t an d ard标准（A STM）single failure criteria 单一故障准则specifications 技术条件；说明书；（设备）规格section(volume) 卷subsection 分卷surveillance 监督s i t e厂址s i t i n g选址tolerance 公差；容差vender 供货单位；卖方verification 验证working drawing 施工图2.规范及标准用语accident 事故barrier 屏障basis of design 设计（或订货）依据class 级category 类别chemical(or mechanical) requirement 化学或机械性能要求component 设备；部件commissioning 调试运行；投入运行；入役design basis accident(or earthquake) （DBA、DBE）设计基准事故（或地震）是指LOCA+earthquake decommissioning 退役event 事件engineered safety features 专设安全设施failure 故障；事故；损坏function 功能；作用general requirement 总要求bid 招标tender 投标grade 等（级）isolation 隔离interface 交接（处），相互关系item 项目，物件，物项item important to safety 安全重要事项normal operating conditions 正常运行工况outage 停役philosophy 主导思想；原理principle 原则；原理protection 保护；防护physical separation 实体分隔performance 性能rule 规则reference 基准；参考safeguard 保卫（防止人为破坏）shield 屏蔽separation 分隔supplementary(or additional) requirement 补充（附加）要求structure 建筑物；构筑物scheme 方案；原理图；流程图；简图二、系统及设备名称1.一回路系统（主、辅）auxiliary feed water system 辅助给水系统auxiliary building 辅助厂房boron recycle (and water make-up ) system 硼回收系统；硼回系统circuit 回路（热工、水力、电路）cold leg 冷端chemical and volume control system(cvcs) 化学和容积控制系统；化容系统component cooling (water) system(cos) 设备冷却水系统containment spray system 安全壳喷淋系统containment dehydrogen recombiner system 安全壳消氢系统containment isolation system 安全壳隔离系统containment reactor coolant drain system 安全壳疏排水系统chemical laboratory 化学分析室charging 上充；充注charging pump 上充泵containment building 安全壳厂房decontamination system 排污系统excess letdown 过量下泄fuel handling building 燃料装卸厂房gaseous waste system 废气处理系统hot leg 热端inlet 入口independence between redundant standby(on site) power sources and between their distribution 多重备用（就地）电源之间和他们的配电系统之间的独立性liquid waste system 废液处理系统letdown 下泄loop 环路moderator 慢化剂nuclear island 核岛N S S S核蒸汽供应系统Outlet 出口shut down 停闭（电站）；停堆（反应堆）preoperational testing of redundant on site electric power systems to verity power load group assignments 验证现场多重电力系统负荷适当分配的运行前试验reactor coolant 反应堆冷却剂reactor coolant system (RCS) 反应堆冷却及系统；主系统reactor coolant pump (RCP) 反应堆冷却剂泵；主泵RCP seal water injection system 主泵轴封水系统（简称轴封系统）residual heat removal system (RHRS) 停堆冷却系统redundancy 多重度；冗余removal from service 停役sampling system 取样系统spent fuel pool cooling (and treatment) system 乏燃料池冷却（净化）系统；乏燃料系统shutdown cooling system 停冷系统（简称）spray ring 喷淋环管spent resin collection system 废树脂收集系统steam generator (SG) 蒸汽发生器S.G blow down system 蒸汽发生器排污系统steam dump system 主蒸汽排放系统safety class 安全等级safety class Ⅰ安全一级safety classification 安全分级scram 事故停堆safety injection system (SIS) 安全注射系统（简称安注系统）the primary circuit 一回路；主回路the primary system 一回路系统2.主系统设备control rod drive mechanism (CRDM) 控制棒驱动机构containment liners 安全壳衬里in-core instrumentation 堆内测量pressurizer 稳压器pressure relief tank 卸压箱reactor pressure vessel (PV) 反应堆压力容器（简称压力壳）（不宜简称压力容器，以免与一般压力容器混淆）reactor coolant pump (RCP) 主泵reactor coolant pipe 反应堆冷却剂管道reactor internals (RI) 堆内构件steam generator 蒸汽发生器source (or power) range 源（或功率）量程system integrity 系统完整性3.主系统设备的重要部件（1）.反应堆容器（压力壳）center disc 球冠closure head 顶盖；封头closure studs 顶盖螺丝core shell 筒身段；筒体irradiation surveillance capsule 辐照监督管inlet and outlet of coolant 冷却剂入口和出口lifting device 吊具lower plenum 下腔室lower head ,bottom head 下封头lower core support structure 堆芯下部支承结构moderator 慢化剂nozzle belt 接管带nozzle support ring, nozzle shell course 接管段o-ring O形（密封）环positioning pin, alignment pin 定位销reactor cavity 反应堆堆腔reactor pit 反应堆堆坑stud tensioner （双头）螺栓拉伸器seal ring 密封环shipping skid 运输托架Support ledge 支承台肩（或凸耳）Support ring 支承台Thermal shield 热屏（蔽）（堆内构件）thermal barrier 热屏（主泵）upper plenum 上腔室upper head , top head 下封头upper core support structure 堆芯上部支撑结构vessel shell ring , vessel shell course 容器筒体段（2）.蒸汽发生器Anti-vibration bar 防振条(架) All volatile (water ) treatment (A VT) 全挥发(水)处理Broached hole 纹孔Channel head 水室(一回路封头) Chevron plate 波纹板Carryover (or entrainment) moisture 夹带水分Shroud 围筒; 套筒; 护环(汽轮机叶片) Crud 泥渣Crevice corrosion 缝隙腐蚀Corrosion inhibition 缓蚀剂D r y o u t烧干Down comer 下降通道Erosion 冲刷(腐蚀) Explosive plugging 爆炸堵管Egg crate grid 蛋框式(管子)支撑架Flow distribution baffle 流量分配挡板Flow distribution plate 流量分配板Fouling coefficient 污垢系数Feed water ring 给水环管Frottage 微振磨损Heat transfer tube 传热管Impurity concentration 杂质浓度Lattice, array 栅格(管棒布置) Lane block 夹道，堵塞块Magnetite 四氧化三铁Partition plate （水室）隔板Peening 喷丸（处理）Pitch 间距（管棒）；节距（螺纹，齿轮）Pickling 酸洗Phosphate wastage 磷酸盐耗蚀Phosphate treatment 磷酸盐（水）处理Quarter foil 四叶型Rolling or expansion tube 胀管Roller expanded area 机械胀接区Steam or moisture separator 汽水分离器（一般指粗分离器）Swirl vane separator 旋叶式分离器；离心式分离器Steam drier 细分离器；（蒸汽）干燥器Steam quality 蒸汽干度Sludge ,slurry 淤渣，泥浆Slurry lancing 淤渣冲洗S c c应力腐蚀裂纹Secondary chemistry 二回路水质（处理）Tube sheet 管板Transition (cone) （锥形）过渡段Trunnion 吊耳；耳轴Tub e bundl e 管束Tube support plate 管子支撑板Tu b e t h i n n i n g管壁减薄Tube denting 传热管压凹Tu b e p l u g(g i n g)堵管u-t u b e U形传热管U-bend region U形弯曲管Wrapper 一次侧接管Sand blasting 分隔板A、primary side 一次侧1)channel head 水室2)tube sheet 管板3)primary nozzle 一次侧接管4)divider plate 分隔板5)primary nozzle safe ends 一次侧接管安全端B、secondary side 二次侧1)shell (barrels) 筒体2)transition cone 过渡段（过渡锥体）3)upper head 上封头4)nozzles 接管B、expansion 胀接1)mechanical expansion 机械胀接2)hydraulic expansion 液压胀接3)roller expansion 滚胀4)t ack ex p ans io n定位胀5)full depth tube expansion 管子全深度胀接（3）.堆内构件Anchor ring 固定环Core barrel 堆芯吊蓝Core baffle 堆芯围板Hold down spring 压紧弹簧Thimble guide tube 导向套管（堆内测量）（4）.燃料组件及燃料Clad , cladding （燃料棒）包壳；堆焊层（如control of stainless steel weld cladding of low-alloy steel components ）Collapsing 倒塌End plug 端塞Fuel assembly 燃料组件Fuel element 燃料棒（不宜称燃料元件，因概念不明确，亦不宜称燃料组件）Fuel rod 燃料棒Fuel pellet 燃料芯块Fuel cladding 燃料包壳(第13页缺失)follower 随动器，随动件flaring and deflaring tool 扩口缩口工具（控制棒驱动机构内）lifting yoke 提升磁轭magnetic jack 磁力提升器pressure housing 承压（套）筒（或）壳protective sleeve 保护套筒rod withdrawal (or drop) 提（或落）棒rod travel housing 棒行程指示套管retainer sleeve 固定套；夹持套筒rod position indicating system 棒位指示系统spider assembly 星形架；蛛状架stepping drive 步进驱动stationary latch 保持钩爪ventilation shroud 通风罩（控制棒驱动机构内）（5）.稳压器及卸压箱heating element 电加热器（棒）（不宜称“电热元件”）heater 加热器rupture disc(membrane) 爆破盘（膜）skirt support 筒式支座（不宜称“裙座”）sprayer 喷雾器surge line 波动管4.辅助设备（1）.阀门atmospheric steam dump 蒸汽向空排放阀ball value 球阀check (or non-return) valve 止回阀cock 旋塞阀containment isolation valve 安全壳隔离阀diaphragm valve 隔离阀expansion bellow 波纹管（膨胀节）gate valve 闸阀globe valve 截止阀gasket 垫片（密封用）isolating valve 隔离阀needle valve 针阀open (or shut ) block 锁开（或关）pressure relief valve 卸压阀；释放阀pilot valve 导阀；副筏positioner 定位器；定位装置packing 填料（密封用）stop valve 切断阀safety valve 安全阀steam dump valve 蒸汽排放阀shim 调整垫片steam by-pass valve 蒸汽旁通阀steam relief valve 蒸汽释放阀safety valve 安全阀steam bubble 蒸汽腔valve disc 闸板（闸阀）；阀盘（球阀）valve stem 阀杆valve seat 阀座valve bonnet 阀盖；阀帽（2）.管道和管件blind flange 盲板（法篮）crossover 跨接管filter 过滤器（一般指细过滤器）hanger (支)吊架heat insulation 保温，隔热heat tracing ( 管道)保温加热incoming line 内流管线installation of a fuel flow condensate polishing system安装全流量冷凝水除盐系统instrument line 仪表管线line 小管道（设备上大管道用pipe）letdown orifice 下泄管线letdown crifice 下泄孔板outgoing line 外流管线piping 管道；管系pipe (line) 管道（管线）pipe whipping 管道甩动pipe 管子（一般圆形的）restraint 阻位器；阻挡器strainer 粗过滤器（一般指网式的）spray line 喷雾管surge line 波动管steam line 蒸汽管sensing line 脉冲管steam header 蒸汽总管steam-feedwater line 蒸汽给水管seal water return line 轴封水回流管sprayer pipe 喷雾管tube 管子，传热管throttling orifice 节流孔板tube 管子（各种形状）（3）.容器和离子交换accumulator 安注箱anion bed 阴床batching 制备箱/计量箱chemical mixing tank 化学添加箱chemical additive tank 化学试剂箱concentrate tank 浓缩液箱condensate demineralizer 凝结水除盐装置condensate polisher 凝结水除盐装置cation bed 阳床demineralized water tank 除盐水箱deaerated (or deoxygenated) water tank 除氧水槽drain tank 疏水箱decontaminating tank 去污槽dosing tank 计量槽demineralizer 除盐装置;（水）软化器deborating demineralizer 除硼床free caustic 游离碱hydrazine 联氨N2H4 hold up tank 暂存箱monitor tank 检测槽make-up water tank 补水箱mud settler 澄清槽Mixed bed 混床nitrogen blanked 氮气覆盖surge tank 波动箱（液体）；缓冲罐（气体）storage tank 贮槽（箱）sump 地坑；排水坑tank 箱；槽；罐volume control tank 容积控制箱volume reduction 减容；缩容（4）.热交换器evaporator 蒸发器gas stripper 脱气塔gas stripped feed pump 脱气塔供料泵regenerative heat exchanger 再生热交换器（5）.其它anchor bolt 地脚螺栓adapter 接合器admixture 添加剂anti-reverse device 防倒转机构air vent 放气booster pump 升压泵breathe pipe 呼吸气管controlled leakage 微漏；控制泄漏（柔轴密封）cartridge 滤芯diffuser 导叶（柔）eyebolt 吊环（螺栓）flame arrester 阻火器hood 通风柜header manifold 母管；联箱hanger 吊架muff joint 套管（筒）接头net positive suction head (HPSH) 净正吸入压头；汽蚀裕量positive displacement pump 正排量泵plunger 柱塞（泵）polar crane 环形吊车resin eductor 树脂喷射器screening 筛（选）skimming 撇（去表面浮）渣shut off head 关闭扬程spool (piece) 短轴（段）（主泵更换密封用）support 支架turning gear (or barring gear) 盘车装置vent drain pot 排气盒volute 蜗壳（泵）wet layup 湿保养dry layup 干保养三、运行及安全分析1.运行、操作availability 利用率actuation 触发acceptance run 验收试运burn-up 燃耗condition 工况、状态、条件critical heat flux 临界热负荷、临界热流量control band 调节带cold shutdown 冷停堆continuous duty(motor ) 连续运行（电动机）coolant flow coast down 冷却剂流量惯性下降deviation 偏离，偏差detect 探测d yn a mi c o v err at i n g动态超调departure from nucleate boiling rate(DNBR)烧毁比、偏离泡核沸腾通量比frequency 频率（电波、振动）；频度（事故）feedback 反馈hot shutdown 热停堆heat sink 热阱inventory 装（载）量inactive loop 不工作环路idle operation 空载运行load 负荷（热、电）；负载（力学）load following 负荷跟踪limit 限值（参数）；限制（状态）loose part 松动零件load rejection 甩负荷monitoring 监测operation mode 运行方式operator 操作者offset 偏移over pressure relief 超压释放perturbation 扰动pressure retaining boundary 承压边界power peaking factor 功率不平均系数；功率峰值因子plant shutdown 电站停闭regime 工况state 状态；工况surge 波动shutdown margin 停堆深度（或裕量）threshold 阈（值）transient condition 瞬态工况；动态工况to actuate reactor trip 启堆tripped open set point 快速打开整定点void reactivity 空泡反应性2.安全分析as low as reasonably achievable(ALARA) 尽可能合理地少（或低）accident，incident 事故anticipated operational occurrence 预期运行（偶发）事件burn out 烧毁（燃料）blowdown 喷放，排double-ended break accident 管道双端破裂事故damage 损坏，损伤diversity 多样性DB A(d es i g n b as i s acci d en t) 设计基准事故event，occurance 事件core reflood 堆芯再淹没emergency core cooling system 应急堆芯冷却系统fault 事故，故障failure 故障，损坏，损伤flood 淹没（堆芯电加热器）；洪水泛滥（用于安全分析）fuel mispositioning accident 燃料（组件）错位事故guillstine rupture 切断，破裂hypothetic accident 假想事故inadvertent (or accidental) depressurization 事故卸压incidents of moderate frequency 中等频率事故，一般事故（工况II）infrequent incidents 重大事故；稀有事故（工况III）loss of power (or supply) 断电loss of load 甩负荷loss of reactor coolant flow 反应堆冷却剂断流loss of coolant accident (LOCA) 失水事故limiting incidents 极限事故(工况Ⅳ) multiple failure 多重故障mismatching 失配;失调misoperation 误操作mock-up 全尺寸模型;1:1模型nomal operation 正常运行(工况Ⅰ) operationing transients 运行瞬态off-site power failure 厂外电源断电postulated initial event 假想始发事件power lump 功率骤降power excursion 功率(失控)激增pipe break (管道)破裂;断裂;破口pipe double end rupture 管道双端断裂projectile 飞射物postulated initiating event 假想始发事件reset 复位recriticality 重返临界return to power 重返功率rod ejection 弹棒rod stuck (in position) 卡棒rod uncontrolled withdrawal 失控提棒rod dropping 卡棒rod misalignment 控制棒失步load rejection capability 甩负荷能力redundancy 多重性;冗余度(电,控) RCP locked rotor 主泵转子卡位spurious operation (or action) 假信号动作;误动作SG tube rupture 蒸汽发生器传热管破裂SG tube damage 蒸汽发生器传热管损坏station block out 全厂断电trip 事故停堆;脱扣(汽轮机);跳闸(电) uncontrolled boron dilution 硼(失控)稀释四、机械设备的材料、制造及检修1.材料hardened steel 淬火钢heat（or ladle）analysis 熔炼（或炉前）分析killed steel 镇静钢、全脱氧钢auto clave 高压釜product (or check) analysis 产品（或校核）分析surface carburization 表面渗碳（处理）stress relief annealing 消除应力退火2.检验方法及应用air tightness test 气密性试验couplant 偶合剂contraction （断面）收缩率dye penetrant test 着色（渗透）检验distance-grain-size curve (DGS) 距离幅度曲线examination 检验elongation 延伸率fluorescent penetrating test 荧光（着色）检验flare test （管子）扩口试验flaw 缺陷grain size 晶粒度hydrostatic test; hydro test 水压试验inspection 检查，检验inspector 检验师，检查员（一般指检查的工作人员）indication （缺陷）信号inclusion 夹杂物leak (or leakage) test 检漏试验liquid penetrant test (PT) 着色检验，液体渗透检验magnetic particle test(ing) (MT) 磁粉试验pseudo-defect (or false indication) 伪缺陷radiographic testing (RT) 射线检验reference block 对比试块；基准试块surface inspection 表面检验straight (or angle) beam examination 直（或斜）束法检验scanning 扫描；扫查test coupon 试块test, testing 试验；检验ultrasonic test (UT) 超声（波）检验visual inspection 目视检验；外观检验volume inspection 全容积检验；深部检验3.缺陷名称attack 侵蚀burn through 焊穿；烧穿blow hole (or gas pocket) 气孔；气泡corrosion 腐蚀crevice corrosion 缝隙腐蚀couple corrosion 电偶腐蚀cold shut 冷疤；冷隔deterioration 劣化dimple 凹坑; 凹痕erosion 冲刷腐蚀fret (frettage) (微振)磨损flake (or snow flake) 鳞片发裂general corrosion 均匀腐蚀全面腐蚀galling 擦伤磨损intergranular corrosion 晶间腐蚀lap 折迭lamination 层迭夹层micro-crack(or micro-fissure ) 微裂纹porosity 多孔性孔隙率疏松度ripple 焊波strap inclusion 条状夹渣snake(or fish eye ) 白点spot defect 点状缺陷shrinkage(or shrink cavity) 缩孔transgranular corrosion 穿晶腐蚀underbead crack (焊接)热影响区裂缝；焊道下裂缝repair welding 补焊undercut 咬边uniform corrosion 均匀腐蚀weld tab 焊舌4.焊接及加工argon-arc welding 氩弧焊butt welding 对接焊brazing welding (硬)钎焊back running welding 封底焊built-up sequence 熔敖顺序base metal 基材；母材core wire 焊(条)芯crater 火口deposited metal 熔敖金属electrode 焊条fusion welding 熔焊fillet welding 角焊filler metal 熔敖金属f l u x焊剂groove (or preparation) 焊接破口heat affected zone (HAZ) 热影响区lap welding 搭接焊layer 焊层lift-off effect 提离效应manual welding 手工焊magnetic blow 磁偏吹plug welding 塞焊percussion welding 储能焊pass 焊道positioner 胎具post weld heat treatment (PWHT) 焊后热处理penetration 熔深，焊透repair welding 补焊root opening 焊根间隙run-out plate 引弧板spot welding 点焊soldering welding 软焊，钎焊seal welding 密封焊submerged arc welding 埋弧焊shielded-arc welding 气体保护焊speed of travel 焊接速度tack welding 点（固）焊，（定位）点焊throat thickness 焊缝厚度weld ability 可焊性weld 焊缝，焊接welding 焊接welding wire 焊丝welding condition 焊接规范weld metal 焊缝金属weld junction 熔合五、力学及强度allowable stress 许用应力buckling 屈曲，压曲，失稳loading 加载elastic-plastic analysis 弹塑性分析endurance limit 疲劳（或耐抗）极限circumferential stress 周向（环局）应力frequency spectrum analysis 频谱分析fracture toughness 断裂韧性factor of safety 安全系数load 负载membrane stress 膜应力meridional stress 经线应力non-ductile failure 非延性破坏，脆性破坏nil-ductility transition temperature (TNDT)无延性转变温度；脆性转变温度normal stress 法向应力；正应力principal stress 主应力personnel lock 人行通道residual stress 残余应力radial stress 径向应力shearing stress 剪向应力self-shielding 自屏蔽self-powered detector 自给能探测器switch yard 升压站switch over 切换;转换skin stress 表皮应力tensile strength 抗拉强度t en s i l e t est拉伸试验vibration mode 振型六、物理，剂量及屏蔽activity 活化air borne 空气载带的annihilation (电子)湮灭after power(or heat) 剩余功率（或释热）albedo 反照率attenuation 衰减capture 俘获contamination 污染物decay 衰变disintegration 蜕变、衰变daughter product 子体产物delayed(or prompt)neutron fraction 缓（或瞬）发中子份额dose 剂量（辐射防护）；计量（液体，气体）decontamination 去污exposure 照射（量）(原稿32页重复，33页缺失)七、电气及控制Armature 电枢（电机）Accuracy 精度Annunciator 信号器Busbar 母线Calibration 标定;校准; 校验Cable tray 电缆盘(槽) Display 显示Energize 使……通电Electrical penetration 电气贯穿件Instrumentation (仪表)检测Mimic diagram 模拟图Mutual inductance 互感Orifice meter 孔板流量计Penetration 贯穿(件) Primary element 一次元件Pitot tube 皮托管Resistant element 电阻元件Sensor 传感器;探头Subassembly 元件组件Stoichiometry 化学计量法Transmitter 变送器Two-out-of-four logic 四取二逻辑八、土建,结构及公用设施1.土建Admixture 参合料Aggregate 骨料Buttress 扶壁Bulk head 护岸；隔板Breeze concrete 炉渣；焦渣混凝土Caisson 沉井；沉箱Caulk 堵缝;填实Damp proof course(dpc) 防潮层Drip 屋檐Fascia board 封檐板Form mortice for baluster 预留栏杆孔General layout 总图Quoin 突(屋)角；墙角Hot mixture 热铺混合材料Lintel 过梁Locker room , changing room 更衣室Masonry 砖石建筑Neoprene 氯丁橡胶Plinth 勒脚Relief 地形；浮雕Retaining wall 挡土墙Recess drawing 预留孔（洞）图Reeded tile for stairs 防滑踏步砖roof overhang 挑檐riprap （防冲）乳石subgrade 路基springing line 起拱线utensil 用具2.结构attachment 附件anchor head 锚板bedrock 基岩capable fault 可能活动断层concrete placement 混凝土浇灌embedment 预埋件earthquake magnitude 地震等级free field ground motion 自由场地面运动floor time history 楼面时程曲线floor respond spectrum 楼面响应谱form tie 模板支撑quadric stress 曲面应力intensity scale value 强度值mat foundation 席形基础multiple strand system 多股钢绞线系统out-to-out distance 外包尺寸post tensioning 后涨法pressure grout 压力灌浆reinforcing bars 钢筋stirrup 箍筋slope stability 边坡稳定性tectonic structure 大地构造truss 屋架ungrouted tendons 未灌浆钢筋束wobble coefficient 摇动系数3.给排水bulk head 堵水闸门；挡水墙；驳岸break water 防波堤check 节制闸design basis flood 设计基准洪水fire water 消防(用)水gridiron 格状(或)环状管网hydrosphere 水界offset pipe 偏置管riser pipe 立管;竖管run-off 逕流(量) run-up 波浪爬高revetment 护岸；披坡；砌石面riprap （防冲）抛石；乱石护坡surge 涌浪；涌潮；气象潮service water 生产用水4.暖通Aerosol （大气中）悬浮微粒，带悬浮微粒的气体，气溶胶Baffle 挡板canister （防毒面具用）滤毒器damper 风门；（通风）闸门deluge 洪水；大雨；大水量喷淋demister 除雾器dioctyl phthalate (D.O.P.) 邻苯二酸盐二辛酯filter bank 过滤（器）排架forced draft 强迫通风；鼓风high efficiency particulate air (filter) (HEPA) 高效粒子空气（过滤器）housing （通风）小室；柜架；骨架humidifier 调湿器heating ventilating and air conditioning (HV AC)（采）暖通（风）和空气调节induced draft 排气通风；吸气；引风kidney filtration system 内部循环过滤系统；肾式过滤系统plenum 充气压力通风；通风集管purge 清洗t r a i n序列第一课单词⏹Atom [ ✌♦☜❍], 原子⏹Nucleus [ ⏹◆●✋☜♦], 原子核⏹Nuclei [ ⏹◆●♓♋♓], nucleus 的复数形式⏹Nucleon [ ⏹◆●♓⏹], 核子⏹Electron [✋●♏♦❒⏹], 电子⏹Proton [ ☐❒☜☺♦⏹], 质子⏹Neutron [ ⏹◆♦❒⏹]，中子⏹Neutrino [⏹◆♦❒♓⏹☜◆], 中微子⏹Orbital [ ♌✋♦☎☜✆●], 轨道的⏹⏹Element [ ♏●♓❍☜⏹♦], 元素⏹Isotope [ ♋♓♦☜◆♦☜◆☐]，同位素⏹Hydrogen [ ♒♋♓♎❒☜◆♎✞☜⏹], 氢⏹Deuterium [♎◆♦♓☜❒♓☜❍], 氘⏹Tritium [ ♦❒♓♦♓☜❍], 氚⏹Helium [ ♒♓●☜❍ ●♓☜❍], 氦⏹Barium [ ♌☪☜❒♓☜❍], 钡⏹Bismuth [ ♌♓❍☜], 铋⏹Boron [ ♌❒☜⏹], 硼⏹Lithium [ ●♓♓☜❍]，锂⏹Plutonium [☐●◆♦☜◆⏹♓☜❍], 钚⏹Sodium [ ♦☜◆♎☜❍ ♎♓☜❍], 钠⏹Thorium [ ❒♓☜❍]，钍⏹Uranium [ ◆☜❒♏♓⏹♓☜❍], 铀⏹Transuranium [ ♦❒✌⏹♦◆❒♏♓⏹☜❍] , 铀后元素⏹Radioactive [ ❒♏♓♎♓☜◆✌♦♓], adj.,放射性的⏹Fissile [ ♐♓♦♋♓●], adj.,易裂变的⏹Emission [♓❍♓☞☜⏹], n.发射⏹Decay [♎♓♏♓], v., n., 衰变⏹Electrostatic [ ♓●♏♦❒☜◆♦♦✌♦♓ ], adj., adj.,静电的⏹Momentum [❍☜◆❍♏⏹♦☜❍]，n.,动量⏹Particle [ ☐♦♓●]，n., 粒子⏹Radiation [ ❒♏♓♎♓♏♓☞☜⏹]，n., 放射性，放射，射线⏹Repulsion [❒♓☐✈●☞☜⏹]，n., 排斥⏹Constituent [ ☜⏹♦♦♓♦◆☜⏹♦], adj., 组成的⏹Violate [ ♋♓☜●♏♓♦], vt., 违反⏹Valid [ ✌●♓♎], adj., 有效的，正确的⏹Instantaneous [ ♓⏹♦♦☜⏹♦♏♓⏹☜♦], adj., 瞬时的⏹Disrupt [♎♓♦❒✈☐♦], v., 使分离⏹Unionized [✈⏹♋♓☜⏹♋♓♎], adj., 未电离的。

化工装置常用英语词汇对照

化工装置常用英语词汇对照1. 反应釜（Reactort） Reactor2. 蒸馏塔（Distillation Tower） Distillation Column3. 冷凝器（Condenser） Condenser4. 换热器（Heat Exchanger） Heat Exchanger5. 压缩机（Compressor） Compressor6. 泵（Pump） Pump7. 阀门（Valve） Valve8. 管道（Pipeline） Pipeline9. 传感器（Sensor） Sensor10. 控制系统（Control System） Control System11. 进料（Feed） Feed12. 产品（Product） Product13. 副产品（Byproduct） Byproduct14. 废料（Waste） Waste15. 物料（Material） Material16. 流量（Flow Rate） Flow Rate17. 压力（Pressure） Pressure18. 温度（Temperature） Temperature19. 浓度（Concentration） Concentration20. 比重（Specific Gravity） Specific Gravity21. 开车（Startup） Startup22. 停车（Shutdown） Shutdown23. 维修（Maintenance） Maintenance24. 检修（Overhaul） Overhaul25. 调试（Commissioning） Commissioning26. 操作规程（Operating Procedure） Operating Procedure27. 安全规程（Safety Procedure） Safety Procedure28. 紧急停车（Emergency Shutdown） Emergency Shutdown29. 报警系统（Alarm System） Alarm System30. 防爆区域（Explosionproof Area） Explosionproof Area 化工装置常用英语词汇对照（续）31. 化学反应（Chemical Reaction） Chemical Reaction32. 反应速率（Reaction Rate） Reaction Rate33. 溶解度（Solubility） Solubility34. 酸碱度（pH Value） pH Value35. 悬浮物（Suspension） Suspension36. 沉淀（Precipitation） Precipitation37. 搅拌（Agitation） Agitation38. 过滤（Filtration） Filtration39. 萃取（Extraction） Extraction40. 吸附（Adsorption） Adsorption41. 蒸发（Evaporation） Evaporation42. 结晶（Crystallization） Crystallization43. 干燥（Drying） Drying44. 焙烧（Calcination） Calcination45. 熔融（Melting） Melting46. 铸造（Casting） Casting47. 冷却（Cooling） Cooling48. 加热（Heating） Heating49. 真空（Vacuum） Vacuum50. 压缩空气（Compressed Air） Compressed Air51. 工艺流程（Process Flow） Process Flow52. 设备布局（Equipment Layout） Equipment Layout53. 流程图（Piping and Instrumentation Diagram, P&ID）Piping and Instrumentation Diagram54. 设计规范（Design Specification） Design Specification55. 操作手册（Operation Manual） Operation Manual56. 安全手册（Safety Manual） Safety Manual57. 环保要求（Environmental Requirements） Environmental Requirements58. 能耗（Energy Consumption） Energy Consumption59. 自动化（Automation） Automation60. 信息化（Informatization） Informatization这些词汇在化工装置的日常操作、维护和管理中扮演着重要角色。

化工厂反应釜清洗操作流程

化工厂反应釜清洗操作流程1.关闭反应釜，断开电源和供应管线，保证安全。

Close the reactor, disconnect the power supply and supply pipelines to ensure safety.2.打开排污阀门，将余留在反应釜内的废液排出。

Open the drain valve and drain the residual waste liquid in the reactor.3.使用清洁剂和清水对反应釜内部进行清洗。

Clean the inside of the reactor with detergent and clean water.4.注意保护好自己的皮肤和眼睛，避免接触有害物质。

Pay attention to protect your skin and eyes, and avoid contact with harmful substances.5.用清水冲洗反应釜内壁，确保彻底清除残留物质。

Rinse the inner wall of the reactor with clean water to ensure thorough removal of residues.6.检查反应釜内部是否有死角，对难以清洗的区域进行特别处理。

Check if there are dead corners inside the reactor, and treat the areas that are difficult to clean in a special way.7.使用专门的工具和设备清洁反应釜的夹套和搅拌器。

Use special tools and equipment to clean the reactor's jacket and agitator.8.确保清洗完毕后，反应釜内不再有异味和污渍。

Ensure that there are no odors and stains inside the reactor after cleaning.9.根据清洗情况选择合适的处理方法，如干燥、消毒等。

用于高温气冷堆的核石墨(英文)

第32卷第3期 2017年6月新型炭材料NEW CARBON MATERIALSVol. 32 No. 3Jun. 2017文章编号：1007-8827(2017)03鄄0193-12用于高温气冷堆的核石墨周湘文，唐亚平，卢振明，张杰，刘兵(清华大学核能与新能源技术研究院,先进核能技术协同创新中心,先进反应堆工程与安全教育部重点实验室，北京100084)摘要：自1942年首次在CP-1反应堆中使用以来，核石墨因其优异的综合性能，在核反应堆特别高温气冷堆中被广泛使用。

作为第四代候选堆型之一，高温气冷堆主要包括球床堆和柱状堆两种堆型。

在两种堆型中，石墨主要用作慢化剂、燃料元件基体材料及堆内结构材料。

在反应堆运行中，中子辐照使得石墨的相关性能下降甚至可能失效。

原材料及成型方式对于石墨的结构、性能及其在辐照中的表现起到决定性的作用。

辐照中石墨微观结构及尺寸的变化是其宏观热力学性能变化的内在原因，辐照温度及剂量对于石墨的结构及性能变化起决定性作用。

本文介绍了高温气冷堆中核石墨的性能要求及核石墨的生产流程，阐述了不同温度及辐照条件下石墨热力学性能及微观结构的变化规律，并对当前国内外核石墨的研究现状及未来核石墨的长期发展如焦炭的稳定供应和石墨的回收进行讨论。

本文可为有志于研发用于未来我国商业化的高温气冷堆中的核石墨的生产厂家提供参考。

关键词：核石墨；高温气冷堆；辐照；微观结构；物理、力学及热学性能中图分类号：TQ127.1 + 1文献标识码：A基金项目：国家公派留学基金（201406215002);国家科技重大专项（ZX06901);清华大学自主科研项目（20121088038).通讯作者：周湘文，副教授，博士. E-mail: xiangwen@ . cnNuclear graphite for high temperature gas-cooled reactorsZHOU Xiang-wen，TANG Ya-ping，LU Zhen-ming，ZHANG Jie，LIU Bing (Institute o f Nuclear and New Energy Technology o f Tsinghua University，Collaborative Innovation Center o f Advanced Nuclear Energy Technology，the key laboratory o f advanced reactor engineering and safety，Ministry o f Education，Beijing100084，China)Abstract: Since its first successful use in the CP-1 nuclear reactor in 1942，nuclear graphite has played an important role in nuclear reactors especially the high temperature gas-cooled type (HTGRs) owing to its outstanding comprehensive nuclear properties. As the most promising candidate for generation IV reactors，HTGRs have two main designs，the pebble bed reactor and the prismatic reactor. In both designs，the graphite acts as the moderator，fuel matrix，and a major core structural component. However，the mechanical and thermal properties of graphite are generally reduced by the high fluences of neutron irradiation of during reactor opera- tion，making graphite more susceptible to failure after a significant neutron dose. Since the starting raw materials such as the cokes and the subsequent forming method play a critical role in determining the structure and corresponding properties and performance of graphite under irradiation，the judicious selection of high-purity raw materials，forming method，graphitization temperature and any halogen purification are required to obtain the desired properties such as the purity and isotropy. The microstructural and corresponding dimensional changes under irradiation are the underlying mechanism for the changes of most thermal and mechanical properties of graphite，and irradiation temperature and neutron fluence play key roles in determining the microstructural and property changes of the graphite. In this paper，the basic requirements of nuclear graphite as a moderator for HTGRs and its manufacturing process are presented. In addition，changes in the mechanical and thermal properties of graphite at different temperatures and under different neutron fluences are elaborated. Furthermore，the current status of nuclear graphite development in China and abroad is discussed，and long-term problems regarding nuclear graphite such as the sustainable and stable supply of cokes as well as the recycling of used material are discussed. This paper is intended to act as a reference for graphite providers who are interested in developing nuclear graphite for potential applications in future commercial Chinese HTGRs.Key words：Nuclear graphite；High temperature gas-cooled reactors；Irradiation；Microstructure；Physical，mechanical and thermal propertiesReceived date：2017-02-26；Revised date:2017-05-13Foundation item：State Scholarship Foundation of China (201406215002) ；Chinese National S&T Major Project (ZX06901) ；Tsinghua University Initiative Scientific Research Program (20121088038).Corresponding author：ZHOU Xiang-wen，Associate Professor. E-mail: xiangwen@ tsinghua. edu. cnEnglish edition available online ScienceDirect ( http://www. sciencedirect. com/science/journal/18725805 ).DOI：10. 1016/S1872-5805(17)60116-1• 194•新型炭材料第32卷1IntroductionThe phrase nuclear graphite began to be used at the end of 1942 when the first nuclear fission occurred in the graphite moderated nuclear reactor CP-1[I]. From the early 1960s, the United Kingdom, the United States and Germany began to develop high temperature gas-cooled reactors (HTGRs). Japan began the construction of a 30 MWth high temperature test reactor (HTTR) in 1991, which reached its first criticality in 1998. In China, a 10 MW experimental high temperature gas-cooled reactor ( HTR-10 )[23], whose design started in 1992 and construction commenced in 1995, reached it criticality in the end of 2000, and its full power in the beginning of 2003. Since the Fukushima accident in March, 2011, the public has paid more and more attention to the safety of nuclear power. As a candidate reactor for the Gen- eration-IV reactors, the construction of a 2x250 MW high temperature gas-cooled reactor pebble-bed module (HTR-PM) with inherent safety is underway in Shidao Bay, Rongcheng of Shandong province, China and is expected to complete in 2017[4]. In both of the research and commercial HTGRs, the reactor reflectors and cores have been constructed by structural graphite components. Past designs represent two primary core concepts commercially favored for HTGRs ：the prismatic block reactor (PM R) and the pebble- bed reactor (PB R)[2]. In both of the HTGR concepts the polycrystalline graphite not only is a major structural component which offers thermal and neutron shielding and provides channels for fuel and coolant gas, channels for control and safety shut off devices, but also acts as a moderator and matrix material for the fuel elements and control rods and a heat sink or conduction path during reactor trips and transients.The polycrystalline graphite exhibits significant importance in HTGRs because of its outstanding nuclear physical properties such as high moderating and reflecting efficiency, a relatively low atomic mass and a low absorption cross-section for neutrons, in addition to high mechanical strength, good chemical stability and thermal shock resistance, high machinabili- ty and light weight[5]. The following example illustrates the importance of nuclear graphite in more details. For the thorium high temperature reactor ( TH- TR) in Germany with a power of 300 MWe, nearly 400 000 kg of nuclear graphite has been used[2] •In China, approximately 60 tons of graphite was used in HTR-10[3], and more than 1000 tons of nuclear graphite will be used in HTR-PM as the structural material and matrix graphite of pebble fuel elements ⑷. The raw materials of matrix graphite of fuel elements for HTR-10 and HTR-PM such as natural flake graphite and artificial graphite powder are supplied by Chinese domestic providers[6,7]. The behavior of the individual fuel particles and the matrix graphite material in which the particles are encased are not considered here. However, it should be noted that although the graphite technology associated with the matrix graphite is related to that of the main structural graphite such as the moderator there are differences as non- graphitized materials and natural flake graphite are used in the matrix graphite. Because so far no qualified domestic nuclear graphite is available, all the structural nuclear graphite materials for HTR-10 and HTR-PM are imported from Toyo Tanso of Japan. In April 2015, China Nuclear Engineering Corporation Ltd ( CNEC) announced that its proposal for two commercial 600 MWe HTGRs (HTR-600) at Ruijin city in Jiangxi Province had passed an initial feasibility review. The HTR-600 is planned to start construction in 2017 and for grid connection in 2021[8]. In order to achieve the economy and security of supply, the structural nuclear graphite must be provided by domestic providers in China in the future. Fortunately, with the rocketing development of photovoltaic industry in China, several Chinese companies have emerged which can produce the fine-grained isotropic, isostatic molded, high strength graphite in large scale. Some of the manufacturers with state-of-the-art graphite manufacture capabilities should be chosen as the potential candidate providers of the structural nuclear graphite for HTGRs based on qualification programs. However, during the operation of a reactor, many of the graphite physical properties are significantly changed due to the high fast neutron doses. The physical, mechanical and chemical properties of graphite can be influenced negatively by irradiation induced damage, which would lead to the failure of graphite components. In pebble-bed HTGRs such as HTR-PM in China, the core support graphite structure is particularly considered permanent, although it is expected that certain high neutron dose components ( inner graphite reflector) will be replaced during the whole lifetime of the reactor. During the life time of the reactor, the reflector graphite would be subjected to a very high integrated fluence of fast neutrons of around 3x1022n/cm2(E>0.1M eV)[910]. Therefore, the pre-irradiation and post-irradiation comprehensive properties of nuclear graphite candidates must be thoroughly examined and evaluated. Those properties of nuclear graphite are strongly dependent on the extent of anisotropy, grain size, microstructural orientation and defects, purity, and fabrication method.In this paper, basic nuclear requirements of nu第3期ZHOU Xiang-wen et a l：Nuclear graphite for high temperature gas-cooled reactors•195.clear graphite are presented and the specifications such as the manufacture, material properties with three primary areas (physical, thermal and mechanical) and irradiation responses of nuclear graphite suitable for HTGRs are elaborated, which could be a reference for the potential providers who are anxious to develop the nuclear graphite for future commercial HTGRs of China. The long-term considerations such as those involving the cokes and recycle for nuclear graphite are also discussed.2 Nuclear requirements of graphite for HTGRs2.1 Fission reactions with neutronsThe tremendous energy produced in HTGRs is from the fission of isotopes such as 92 U233，92 U235，and 94Pu239 . Fission of a heavy element，with release of energy and further neutrons，is usually initiated by an impinging neutron. The fission of 92U235 can be described as：92『5+。

BY-PASS CONTROL CIRCUIT FOR NUCLEAR REACTOR SAFETY

专利名称：BY-PASS CONTROL CIRCUIT FOR NUCLEAR REACTOR SAFETY PROTECTION SYSTEM 发明人：KOBAYASHI HIDEO,YABUMOTO KOICHI申请号：JP2971786申请日：19860213公开号：JPS62187902A公开日：19870817专利内容由知识产权出版社提供摘要：PURPOSE:To prevent a reactor from being stopped due to the failure of another channel during the test and correction of a quadruple system by forming a '0' logic signal generating means and a by-pass switch means. CONSTITUTION:A trip discrimination circuit TR supervises the logical states of compared outputs inputted through by-pass table circuits B1-B4, and when two inputs out of four are logic '1', generates a trip signal Q for stopping the nuclear reactor. The circuits B1-B4 compare signals PV1'-PV4' generated from signal means C1-C4 for processing signals generated from the nuclear reactor through transmission lines T1-T4 with normal level set points SV1-SV4, and when abnormality is detected, output '1'. By-pass switch means BPS11-41 are manually turned to the N side at the normal time and turned to the BP side at the by-pass time. At the by-pass time, the BP side is connected with a '0' logic signal generating means. When only one switch is by-passed, a TR acts as a 30UTOF1 circuit and the nuclear reactor is switched to duplex system constitution.申请人：YOKOGAWA ELECTRIC CORP更多信息请下载全文后查看。

加速器驱动的陶瓷快堆的中子物理进展

2017·201·state within10s respectively.It can be seen that the variation law and range of simulation results are in good agreement with the experimental results,which show that the IQS/MC program is reliable in simulating dynamic behavior of source jerk of sub-critical zero power reactor.Fig.1(color online)The comparison of simulation results and experiment results of three schemes in the process of source jerk.Reactivity insertion processFigure2shows the comparison curves between the experimental value and the simulated value of the relative change behavior of neutronﬂux at the detector channel during the process of the single safety rod falling and double safety rod falling at diﬀerent subcritical levels,and the neutronﬂux under stable state is seen as the reference value of relative neutronﬂux.In thisﬁgure,the sawtooth curve is the experimental data recorded at the detector channel, and the smooth curve is the simulated data calculated by IQS/MC program.As can be seen from the Fig.2,the power is rapidly reduced when safety rod is falling and then the power is slowly attenuated to a stable level under the action of delayed neutrons.At the same time,the deeper the subcritical degree is,the lower the attenuation amplitude of relative count is.We can alsoﬁnd that the simulated data is consistent with the experimental data on the changing trends.Fig.2(color online)The comparison of IQS/MC simulation and experiment under SC1to SC3layout schemes in the process of single safety rod falling process(left)and double safety rods falling process(right).5-20Progress of Neutron Simulation in Accelerator-drivenCeramic Fast ReactorYan Xuesong,Zhang Xunchao,Zhang Yaling and Yang LeiIn an attempt to allow nuclear power to reach high resource utilization,suﬃcient nuclear safety,nuclear prolifera-tion resistance and lowerﬁnancial risk,the concept of accelerator-driven ceramic fast reactor(ADCFR)is proposed. The ADCFR could converted loaded nuclear fertile material toﬁssile fuel and burns it over a40-year core life without fuel shuﬄing or supplementation.Figure.1(a)is schematic of accelerator-driven ceramic fast reactor.AD-CFR consists of a high-power superconducting linear accelerator[1],a spallation target[2]and an ceramic-coolant·202·2017fast reactor.This system is constructed based on the accelerator-driven system (ADS)[3]and belongs the burner system in Accelerator-Driven Advanced Nuclear Energy System (ADANES)[4,5].Fig.1(color online)(a)Schematic of accelerator-driven ceramic fast reactor.(b)Schematic radial cross-section of the ADCFR.Figure 1(b)shows a schematic cross-section of the reactor core.The red component of the reactor is a spallation target.There are 7layers of fuels wrapped outside the spallation target,expressed in 6diﬀerent colors(except for red and dark blue).The dark blue outside the fuel is the reﬂection component and the shieldingcomponent.Fig.2(color online)Time-dependent distribution of theideal K eﬀfor ZrO 2and Al 2O 3ceramic materials.To study the operation time of the core and the perfor-mance of the nuclear fuel breeding,we have chosen thecomplete ceramic reactor to carry out the simulation.The reactor core consists of ZrO 2and Al 2O 3ceramic ma-terials,which include the coolant,nuclear fuels,struc-tural materials,reﬂective materials,and absorption-control materials.Figure.2shows the ideal eﬀectivemultiplication factor (K eﬀ)as a function of full-poweroperation-time (∼35a).Initially,the CFR can operateunder sub-critical conditions due to the external neu-tron source.K eﬀis initially set to 0.98.Nearly 5alater,K eﬀreaches around ∼1.0,which means it can be-gin to operate under a critical mode because of excessreactivity,without the need to be sustained by an ex-ternal neutron-source.After 15a,K eﬀwould reach its maximum,and then it gradually decreased over morethan 20a.The total operation time is over 30a.The CFR has increased inherent safety,excellent breeding performance,eﬃcient power generation.If CFR would be combined with simple high dry reprocessing,a fully closed nuclear-energy system might become feasible.It is belong to ADANES,which would be an ideal clean nuclear ﬁssion energy system.References[1]H.A.Abderrahim,J.Galambos,Y.Gohar,et al.,DOE white paper on ADS,(2010).[2]G.S.Bauer,J Nucl.Mat.,398(2010)19.[3]C.Rubbia,J.Aleixandre,S.Andriamonje,ENEA Report,(2001).[4]L.Yang,W.L.Zhan,Sci.China Technol.Sci.,(2017);in press.[5]X.S.Yan,L.Yang,X.C.Zhang,Energies,10(2017)944.。

华龙1号原理

华龙1号原理The principles behind the Hualong One nuclear reactor are an interesting topic worth exploring. 华龙一号核反应堆背后的原理是一个值得探讨的有趣话题。

As one of China's most advanced nuclear power technologies, it represents a significant step forward in the country's efforts to develop clean and sustainable energy sources. 作为中国最先进的核能技术之一，它代表着该国在开发清洁可持续能源方面迈出的重要一步。

The Hualong One reactor boasts improved safety features compared to older models, with enhanced reliability and efficiency. 华龙一号反应堆相较于旧型号拥有更加完善的安全特性，具有更高的可靠性和效率。

Its design incorporates advanced technologies that make it less susceptible to accidents, minimizing the risks associated with nuclear power generation. 其设计融合了先进技术，使其更不容易发生事故，从而降低了与核能发电相关的风险。

One of the key aspects of the Hualong One reactor is its use of passive safety systems, which rely on natural processes rather than active control mechanisms in the event of an emergency. 华龙一号反应堆的关键之一是其采用被动安全系统，这些系统依靠自然过程而非紧急控制机制。

核能的应用和风险英语作文

核能的应用和风险英语作文Title: Application and Risks of Nuclear Energy.Nuclear energy plays a crucial role in meeting the world's energy demands. Its application in power generation has proven to be efficient and reliable, contributing significantly to reducing greenhouse gas emissions. Nuclear power plants produce large amounts of electricity without emitting carbon dioxide, making them an attractive option for countries seeking to transition to cleaner energy sources.However, along with its benefits, nuclear energy also carries significant risks. The most prominent risk is the potential for nuclear accidents, such as the Chernobyl and Fukushima disasters, which have had devastating environmental and health consequences. Radioactive waste disposal is another major concern associated with nuclear energy. Proper management of radioactive waste is essential to prevent environmental contamination and protect public health.To address these risks, strict safety regulations and protocols are enforced in the operation of nuclear power plants. Regular inspections, maintenance, andemergency preparedness measures are implemented to minimize the likelihood of accidents. Additionally, advancements in nuclear technology, such as the development of safer reactor designs and improved waste management techniques, are continuously being pursued to enhance the safety and sustainability of nuclear energy.In conclusion, while nuclear energy offers significant benefits in terms of power generation and emissions reduction, it is essential to acknowledge and mitigate the associated risks through comprehensive safety measures and responsible waste management practices.标题：核能的应用和风险。

设备英语词汇_机械英语词汇

1.恒温·干燥器/恒温恒湿器(恒温干燥箱) drying ovens/humidity chambers---(在重庆有oem生产)送风定温恒温器 forced convection constant temperature ovens惰性气体恒温器 inert gas ovens精密恒温器 precisionconstant temperature ovens2.洁净恒温器clean ovens送风定温干燥器forced convection constant temperature drying ovens空气幕送风定温恒温器 forced convection ovens with air curtain定温干燥箱constant temperature drying ovens3.角形真空定温干燥器(真空干燥箱） vacuum drying ovens恒温恒湿器 constant temperature and humidity chambers流水线设备in-line system for underfill adhesive and encapsulation4.恒温培养器（恒温培养箱）（在重庆有oem生产）constant temperature incubators---可程式低温培养器low temperature program type incubators5.低温培养器low temperature incubators低温稳定性培养器low temperature stability incubators培养器 incubatorsco2培养器co2 incubators振荡培养器 shaking incubators6.冻结干燥器 freeze dryers---冻结干燥器 freeze dryers离心形冻结干燥器 centrifugal freeze dryers7.灭菌器sterilizers---干热灭菌器drying sterilizers高压灭菌器（高压灭菌锅）autoclaves sterilizers低温等离子灭菌器low temperature plasma sterilizers环形燃烧管灭菌器 loop cinerator8.纯水制造装置 water purifiers---纯水制造装置 water stills超纯水制造装置ultra-pure water purifiers简易纯水制造装置water purifiers超纯水制造装置系统 ultra-pure water purifier system大容量纯水制造装置 water purifiers system9.洗净器washers---实验室玻璃器皿清洗机laboratory glassware washers超声波清洗机 ultrasonic cleaners大型超声波清洗机aqueous ultrasonic cleaning systems超声波试管清洗机ultrasonic pipet washers超声波清洗机 ultrasonic cleaners10.恒温液槽constant temperature baths---投入式恒温装置constant temperature devices油槽oil baths振荡式低温水槽low constant temperature shaking baths深槽形恒温水槽constant temperature water baths11.离心形冻结干燥机器 centrifugal freeze dryers12.冷却液体循环器cooling liquid circulators冷却水循环器cooling water circulators便携式冷却器 immersion cooler寒流捕获器 cooling trap冷却水外部循环器 cooling water circulators试验槽thoughs13.高温炉 high temperature furnaces heating apparatus---马弗炉 muffle furnaces超高温电气炉 ultra-high temperature electric furnaces高温电气炉 high temperature electric furnaces真空气体置换炉14.造粒干燥装置（喷雾干燥机、喷雾造粉机、喷雾造粒机）granulating and drying apparatus for wet powder body and liquid---喷雾干燥器 spray dryer有机溶剂喷雾干燥器 spray dryer生产线喷雾干燥器 spray dryer for product line15.浓缩器evaporators---旋转蒸发仪rotary evaporators溶媒回收装置 solvent recovery unit16.乳化·搅拌·振荡器homogenizers, stirrers, shakers---磁力搅拌器magnetic stirrers加热板hot plates振荡器shakers送液·减压·加压装置 aspirators, pumps, compressors搅拌器 stirrers实验室自动乳钵粉碎器17.等离子装置 low temperature ashers, cleaners, etchers---气体等离子蚀刻机gas plasma etcher “plasma reactor”气体等离子清洗机 gas plasma dry cleaner气体等离子灰化机 gas plasma asher 半导体基板自动机器18.桌上小型探测显微镜desk-top small probe microscope “nanopics”半导体制造用检查装置yield management for semiconductor ptoducts非破坏评价解析装置nondestructive testing system紫外线洗净·改质装置尘埃计数器风速计19.去静电风机、风幕及静电测定计auto balanced over head ion blower环境试验设备temperature,humidity testing chamber 防湿保管库 moisture-proof storage nanotechnology 半导体用设备anelva日本电子制品 jeol振动试验装置 vibration test systems冲击试验装置20.形态观察分析系统mapping analyzer生物分子间相互作用分析系统biomioleculer interaction analysis system高速液相色谱仪lc-ce/cec system21.血管壁细胞混合培养系统 dynamic coculture system22.基因检查仪器 genopattern analyzer23.atp测定器atp measuring instrument分光光度计microplate spectrophotometer细胞培养·发酵用自动分析系统automated chemistry analyzer for monitoring cell culture and fermentation processes细胞生死判别系统 cell vital analyzer24.细胞计数分析装置 cell scaler/analyzer 2元电泳仪荧光 spot cutter高速冷却离心机 high speed refrigerated,centrifuges微量高速离心机high speed micro-centrifuges液体中微生物简单测试仪simple germ test kit “simple tester”试料混合器25.防爆冷藏柜 explosion proof freezer and refrigerator 杀菌水生成系统 sterilization water production device 膜式脱气装置 filter-type air extractor 抗酸化机能水制造装置acid-resistant water purifier 高性能净水器反渗透式高性能净水器26.分光光度计spectrophotometer元素分析装置atomic absorption spectrophotometericp发光分光分析icp atomic emission spectrophotometerx线光分析计x-ray fluorescence analysis气体分析计27.近红外分析装置fourier transform near infrared spectrometer融点测定仪 melting point measuring instrument热分析系统thermo system自动反应装置automatic reactor水分计moisture analyzer引张压缩试验机 tester,tension and compression数字粘度计28.振动式粘度计vibro viscometer浸透压测定装置osmotic pressure meters 超临界水酸化系统 small scwo systems重金属排液处理装置 heavy metal eliminator 简易水质检查试验纸 water quality tester stripsph计 phmeter导电率计 conductivity meters湿度计29.yamato试验研究设备 laboratory design and engineering---通风柜 fume hoods排风机 blowers实验台 laboratory furniture 保管柜storage cabinets实验台用附属器具carts and laboratory table attachments30.环境制御设施research facilities, product lines, environment control devices---生物安全柜biohazard safety equipment 废水处理系统waste water treatment 试验动物饲养室bio clean room for animal experiment31.试料混合器 blender防爆冷藏柜 explosion proof freezer and refrigerator 杀菌水生成系统 sterilization water production device 膜式脱气装置filter-type air extractor 抗酸化机能水制造装置acid-resistant water purifier 高性能净水器反渗透式高性能净水器32.分光光度计spectrophotometer元素分析装置atomic absorption spectrophotometericp发光分光分析icp atomic emission spectrophotometerx线光分析计x-ray fluorescence analysis气体分析计 gas analyzers33.回折/散乱式粒度分布测定装置analyzer,particle size distribution laser diffraction device 低真空走查电子显微镜scanning probe micro scope高速液相色谱仪liquid chromatograph 滴定装置 automatic titration34.大塚电子制品电位计膜厚计散乱光光度计 lcd测定·评价装置热量计35.天平 balances36.近红外分析装置fourier transform near infrared spectrometer融点测定仪 melting point measuring instrument热分析系统thermo system自动反应装置automatic reactor水分计moisture analyzer37.近红外分析装置fourier transform near infrared spectrometer融点测定仪 melting point measuring instrument热分析系统thermo system自动反应装置automatic reactor水分计moisture analyzer38.引张压缩试验机 tester,tension and compression数字粘度计digital viscometer振动式粘度计vibro viscometer浸透压测定装置osmotic pressure meters 超临界水酸化系统 small scwo systems39.引张压缩试验机 tester,tension and compression数字粘度计digital viscometer振动式粘度计vibro viscometer浸透压测定装置osmotic pressure meters 超临界水酸化系统 small scwo systems40.引张压缩试验机 tester,tension and compression数字粘度计digital viscometer振动式粘度计vibro viscometer浸透压测定装置osmotic pressure meters 超临界水酸化系统 small scwo systems41.重金属排液处理装置 heavy metal eliminator 简易水质检查试验纸water quality tester stripsph计phmeter导电率计conductivity meters湿度计 hygrothermometers过滤器 filter42.通风柜fume hoods排风机blowers实验台laboratory furniture保管柜storage cabinets实验台用附属器具carts and laboratory table attachments43.生物安全柜biohazard safety equipment 废水处理系统waste water treatment 试验动物饲养室 bio clean room for animal experiment44.生物安全柜biohazard safety equipment 废水处理系统waste water treatment 试验动物饲养室 bio clean room for animal experiment45.电磁波室隔音室恒温室/恒温恒湿室constant temperature and humidity facilities低温室 constant low temperature facilities 人工气候室 artificial atmospheric phenomena simulator46.电磁波室隔音室恒温室/恒温恒湿室constant temperature and humidity facilities低温室 constant low temperature facilities 人工气候室 artificial atmospheric phenomena simulator动物研究用高压蒸汽灭菌装置47.动物研究用高压蒸汽灭菌装置sterilization systems, for animal research48.动物研究用高压蒸汽灭菌装置sterilization systems, for animal research49.送风定温恒温器forced convection constant temperature ovens惰性气体恒温器inert gas ovens精密恒温器precision constant temperature ovens洁净恒温器 clean ovens送风定温干燥器 forced convection constant temperature drying ovens50.定温干燥箱 constant temperature drying ovens角形真空定温干燥器 vacuum drying ovens恒温恒湿器 constant temperature and humidity chambers流水线设备in-line system for underfill adhesive and encapsulation51.液晶产业用高压脱泡机 autoclaves ----用于去除lcd的气泡。