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《“十二五”普通高等教育本科国家级规划教材 核电专业英语 第2版》_阎昌琪编;阮於珍主审_14119487_9787512391864

【书名】:《“十二五”普通高等教育本科国家级规划教材 核电专业英语 第2版》
【作者】:阎昌琪编;阮於珍主审
【出版社】:北京:中国电力出版社
【时间】:2016
【页数】:279
【ISBN】:9787512391864
【SS码】:14119487

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内容简介

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 The 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 Reactor Thermo-hydraulics

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 TheSteam 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 Safetr

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 AP 1000 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 Constuction Schedule

18.3 Operation, Maintenance and Services

18.4 Operational Flexibility

18.5 Safety Systems

18.6 Primart 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

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