核电专业英语

出版时间：2010-7  出版社：中国电力出版社  作者：阎昌琪 编  页数：279  
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前言

　　核电工程技术涉及的学科领域广泛，包含很多高新技术。目前，美、英等发达国家在该领域处于领先地位，很多新的研究成果和新技术的介绍都以英文发表，每个从事核电工程研究、设计和运行的专业人员都需要阅读大量的英文资料。为了满足越来越多的核电工程专业人员学习专业英语的需要，编写了本书。　　本书内容涵盖了核电工程所涉及的主要学科，在介绍核反应堆物理及核反应堆热工等基础知识的同时，也介绍了各种类型的核反应堆及主要设备的原理和使用特性等。主要内容包括：核反应堆物理的基础知识、核材料、核反应堆热工水力学、反应堆结构、核动力系统和主要设备、核反应堆运行及核安全、核动力的发展及新一代反应堆等。本书内容广泛，选用不同风格的文章，做到内容新、知识面宽；选用的课文概念性和知识性强、难度适中，不涉及复杂的专业理论。为了便于读者掌握专业词汇，每课课后对重要的关键词作了英、中文两种解释，同时还列出了重要的词汇解释、课文中的难点注释。为了加深读者对课文内容的理解，课后还附有习题和答案。　　本书的内容安排由浅入深、由基础到专业，可适合不同层次的学生使用。全书围绕着核电工程这一主题，在专业部分中以新一代压水堆核电站动力装置为主线，介绍了目前运行的核电技术以及新一代的核电技术。书中的每一课都有相当的独立性，可以根据学生的兴趣和专业方向选择使用，同时也考虑了课文内容满足总体需要，保证全书内容是一个完整的整体。　　本书的阅读内容取自英文的原版教科书和工程设计说明书。书中的引文，编者尽力与版权所有者取得联系，但仍有部分联系不上，在此深表歉意。　　全书共20个单元，由哈尔滨工程大学阎昌琪教授编写，由中国原子能科学研究院阮於珍研究员主审，阮老师提出了许多宝贵的意见和建议，在此深表谢意。　　由于编者水平所限，书中难免存在缺点和不足，敬请读者提出宝贵意见。

内容概要

本书为普通高等教育核工程与核技术专业规划教材。    本书的内容涵盖了与核电有关的基础理论知识和专业知识，介绍了反应堆结构、核动力系统和设备，也包括了近年来核电的新发展，例如第三代和第四代反应堆的介绍。书中涉及的核电专业词汇广泛、内容丰富、知识性强。    为了便于读者掌握专业词汇，每课课文后对重要的关键词作了英、中文两种解释，同时还列出了重要的词汇解释、课文中的难点注释。为了加深读者对课文内容的理解，课后还附有习题和答案。    本书可作为普通高等教育本科核工程与核技术专业的英语阅读教材，也可作为核电工程技术人员的培训和自学用书，同时可作为能源动力类等相关专业人员的阅读材料。

书籍目录

前言Unit 1 The Basic Concepts for Nuclear Physics  1.1 Atoms and Nuclei  1.2 Isotopes  1.3 Mass Defect  1.4 Binding Energy  1.5 Energy Levels  1.6 Fission  Self-test  关键字解释  词汇  课文注释Unit 2 Radiation  2.1 Radioactivity  2.2 Excitation and Ionization by Electrons  2.3 Heavy Charged Particle Slowing by Atoms  2.4 Heavy Charged Particle Scattering by Nuclei  2.5 Gamma Ray Interactions with Matter  2.6 The Properties of Alpha, Beta and Gamma Radiation  Self-test  关键字解释  词汇  课文注释Unit 3 Nuclear Materials  3.1 Fuels  3.2 Moderators  3.3 Coolants  3.4 Cladding Materials  3.5 Control Materials  Self-test  关键字解释  词汇  课文注释Unit 4 The Theory of Nuclear Reactors  4.1 Th6 Chain Reaction  4.2 The Neutron Cycle in a Thermal Reactor  4.3 Conversion and Breeding  4.4 Fuel Cycles  Self-test  关键字解释  词汇  课文注释Unit 5 Nuclear Reactor Concepts  5.1 Power Reactors  5.2 Consumption of Nuclear Fuels  5.3 Reactor Control  5.4 Other Effects on Reactor Operation  5.5 The Fast Breeder Reactor  5.6 Uranium as an Energy Resource  Self-test  关键字解释  词汇  课文注释Unit 6 Nuclear ReactorThermohydraulics  6.1 Methods of Heat Transmission  6.2 Conduction in Reactor Fuel  6.3 Heat Removal by Coolant  6.4 Boiling Heat Transfer  Self-test  关键字解释  词汇  课文注释Unit 7 Pressurized water Reactor  7.1 General  7.2 Pressurized Water Reactor Components  7.3 Introduction to the Nuclear Steam Supply System 80+  Self-test  关键字解释  词汇  课文注释Unit 8 Reactor vessel and Internals  8.1 Reactor Vessel  8.2 Reactor Vessel Internals  Self-test  关键字解释  词汇  课文注释Unit 9 Reactor Core and Fuel  9.1 Introduction  9.2 Core  9.3 Fuel Rod  9.4 Fuel Assembly  9.5 Control Element Assemblies and Drive Mechanisms  9.6 Control Element Drive Mechanisms (CEDM)  9.7 Neutron Sources  9.8 Burnable Absorber Rod Assembly  Self-test  关键字解释  词汇  课文注释Unit 10 The Main Components in PWR Coolant System  10.1 Steam Generators  10.2 Pressurizer  10.3 Reactor Coolant Pumps and Motors  Self-test  关键字解释  词汇  课文注释Unit 11 Pressurized Water Reactor Systems and Containment  11.1 Plant Heat Balance and the Steam Cycle  11.2 PWR Primary and Secondary Loops  11.3 Auxiliary system for Primary Loop  11.4 Containment  Self-test  关键字解释  词汇  课文注释Unit 12 The Steam Turbine  12.1 Introduction  12.2 Classification of Turbines  12.3 Impulse and Reaction Blading  12.4 Velocity Compounding Curtis Stage  12.5 The Reaction-Turbine Principle  12.6 Reaction Blading  12.7 Sealing Arrangement  12.8 Twisted and Tapered Blades  12.9 Erosion Control and Moisture Removal  12.10 Other Blade Features  12.11 Low Pressure Turbine  12.12 Turbine Control  Self-test  关键字解释  词汇  课文注释Unit 13 Main Steam, Feed and Condensate Systems  13.1 Introduction  13.2 Main Steam and Feedwater Piping  13.3 Main Steam Piping System Flow Restrictor  13.4 Safety Requirements  13.5 Feed and Condensate System Description  13.6 Transients  13.7 Controls  Self-test  关键字解释  词汇  课文注释Unit 14 Operation of a Nuclear Power Plant  14.1 Introduction  14.2 Plant Safety  14.3 Plant Operations  14.4 Normal Mode  14.5 Abnormal Mode  14.6 Off-Normal (Upset) Mode  14.7 Control Rooms and Instrumentation  14.8 System Parameters  Self-test  关键字解释  词汇  课文注释Unit 15 Radiation Hazards and Shielding  15.1 Introduction  15.2 Health Physics  15.3 The Biological Effects of Radiation Exposure  15.4 The Effects of Inhaled and Ingested Radioactivity  15.5 Reactor Shielding  Self-test  关键字解释  词汇  课文注释Unit 16 Nuclear Safety  16.1 Safety and Hazards in Nuclear Power  16.2 Reactor Accidents  16.3 The Accident at Three Mile Island  16.4 The Accident at Chernobyl  Self-test  关键字解释  词汇  课文注释Unit 17 Westinghouse APl000 Advanced Passive Plant  17.1 Introduction  17.2 Major Equipment Description  17.3 Safety Through Simplicity  17.4 Passive Safety Systems  17.5 Probabilistic Risk Assessment  17.6 Simplification  17.7 Cost and Construction Schedule  17.8 Licensing  17.9 AP1000 Deployment  17.10 Conclusions  Self-test  关键字解释  词汇  课文注释Unit 18 European Pressurized Water Reactor (EPR)  18.1 Introduction  18.2 Construction Schedule  18.3 Operation, Maintenance and Services  18.4 Opreational Flexibility  18.5 Safety Systems  18.6 Primary System  Self-test  关键字解释  词汇  课文注释Unit 19 The Heavy-Water-Moderated Reactor  19.1 General Characteristics of the Heavy Water Reactor  19.2 The CANDU Pressure Tube Heavy Water Reactor  19.3 Advanced CANDU Reactor  Self-test  关键字解释  词汇  课文注释Unit 20 Generation IV Nuclear Power  20.1 Introduction  20.2 The Gas-Cooled Fast Reactor (GFR)  20.3 Very-High-Temperature Reactor System (VHTR)  20.4 Supercritical Water-Cooled Reactor (SCWR)  20.5 Sodium-Cooled Fast Reactor (SFR)  20.6 Lead-Cooled Fast Reactor (LFR)  20.7 Molten Salt Reactor (MSR)  20.8 Generation IV and the Hydrogen Economy  Self-test  关键字解释  词汇  课文注释附录Ⅰ Self-test习题答案附录Ⅱ 词汇表参考文献

章节摘录

　　The further development of the British system, the advanced gas-cooled reactor（AGR）,uses graphite as a moderator and a somewhat enriched fuel to compensate for the fact that thefuel is contained in stainless steel, which absorbs a significant fraction of the neutrons.　　We shall describe and discuss all the above reactors, and in particular their coolingproblems, in the following chapters. However, before doing so, it may be interesting to glanceback to prehistoric times. The light water-cooled and moderated reactors have been around farlonger than one might imagine. In fact, the invention of Enrico Fermi was preempted by natureapproximately 2 billion years earlier. In 1972, evidence was found of the dormant remains of anatural fission reactor located at Oklo, in the West African Republic of Gabon. This naturalreactor operated for a period of hundreds of thousands of years. Its existence was discoveredby an intriguing piece of detective work by French nuclear scientists.　　In May 1972, H. Bouzigues obtained a curious result during a routine analysis of standardsamples of uranium ore from Gabon. He found that they contained about 0.4% less 235U thanexpected. This was not due to an error in his analysis or to a natural variation. On this planet, atany particular time, the ratio of 235U to 238U is fixed; some other explanation had to be foundfor the discrepancy. A careful investigation carried out by the French Atomic Energy Agencytraced the abnormal ore to one particular location in Oklo. It was concluded that the deficiencyin 235U could be explained only by the occurrence of a natural fission reaction at the site. At thetime this natural reactor was operating, the ore was buried deep underground and naturalgroundwater served as a moderator and to some extent as a coolant. Such a reactor would notbe possible with the present-day concentration of 235U in naturally occurring uranium, as weexplained above. However, it should be remembered that the half-life of 235U is about 700million years and that of 238U is about 4.5 billion years. Thus, in prehistoric times, theconcentration of 235U was much higher than it is today. When the earth was formed some 4.6billion years ago, the concentration of 235U in natural uranium was about 25%, and it haddecreased to about 3% at the time when the Oklo reactor was operating.

编辑推荐

　　本书内容涵盖了核电工程所涉及的主要学科，在介绍核反应堆物理及核反应堆热工等基础知识的同时，也介绍了各种类型的核反应堆及主要设备的原理和使用特性等。主要内容包括：核反应堆物理的基础知识、核材料、核反应堆热工水力学、反应堆结构、核动力系统和主要设备、核反应堆运行及核安全、核动力的发展及新一代反应堆等。本书内容广泛，选用不同风格的文章，做到内容新、知识面宽；选用的课文概念性和知识性强、难度适中，不涉及复杂的专业理论。为了便于读者掌握专业词汇，每课课后对重要的关键词作了英、中文两种解释，同时还列出了重要的词汇解释、课文中的难点注释。为了加深读者对课文内容的理解，课后还附有习题和答案。

用户评论 (总计17条)

•   对于核电专业学习非常使用，强烈推荐。
•   科普用的书，不用就没用，如果工作在核电这本书也没什么了
•   书是不错的，要好好学习了
•   书很不错，言简意赅
•   这个书是不错，质量好。
•   包装袋包的严，不过封面破了个口，目测运输途中造成的
•   工作了，才知道实用
•   真的还没看
•   书还不错，质量很好
•   就是慢点
•   从基本原理到第四代的反应堆技术都有涉及,内容比较全面,也比较新颖.对于有原子核物理基础的读者来讲，内容本身不难理解，但英文基础不能太差，否则阅读会有些困难。综合来讲，是一本很好的核电英文专业读物。
•   内容还行，有点像科普类文章。
  主要问题是，包装还能再差点吗？！！买了16本书，就一个破箱子装着，书都漏出来了。好歹也找个袋子把书装起来吧。不能再差的包装！！！
•   此书适合入门人员阅读
•   书来的很快 只是送货的服务很一般
•   对于非专业人士 有点难偶
•   RTRTRTRTRTRTRTRT
•   十分无聊的专业英语