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。

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
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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
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Unit 3 Nuclear Materials
3.1 Fuels
3.2 Moderators
3.3 Coolants
3.4 Cladding Materials
3.5 Control Materials
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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
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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
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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
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Unit 7 Pressurized water Reactor
7.1 General
7.2 Pressurized Water Reactor Components
7.3 Introduction to the Nuclear Steam Supply System 80+
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Unit 8 Reactor vessel and Internals
8.1 Reactor Vessel
8.2 Reactor Vessel Internals
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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
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Unit 10 The Main Components in PWR Coolant System
10.1 Steam Generators
10.2 Pressurizer
10.3 Reactor Coolant Pumps and Motors
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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
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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
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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
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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
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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
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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
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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
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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
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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
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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
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附录Ⅰ Self-test习题答案
附录Ⅱ 词汇表
参考文献

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**、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。