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核电专业英语PDF|Epub|txt|kindle电子书版本网盘下载
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- 阎昌琪编 著
- 出版社: 北京:中国电力出版社
- ISBN:9787512302495
- 出版时间:2010
- 标注页数:280页
- 文件大小:21MB
- 文件页数:291页
- 主题词:核电工业-英语-高等学校-教材
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图书目录
Unit 1 The Basic Concepts for Nuclear Physics1
1.1 Atoms and Nuclei1
1.2 Isotopes1
1.3 Mass Defect2
1.4 Binding Energy2
1.5 Energy Levels3
1.6 Fission4
Self-test8
关键字解释9
词汇10
课文注释12
Unit 2 Radiation13
2.1 Radioactivity13
2.2 Excitation and Ionization by Electrons15
2.3 Heavy Charged Particle Slowing by Atoms15
2.4 Heavy Charged Particle Scattering by Nuclei16
2.5 Gamma Ray Interactions with Matter16
2.6 The Properties of Alpha,Beta and Gamma Radiation18
Self-test19
关键字解释19
词汇21
课文注释23
Unit 3 Nuclear Materials24
3.1 Fuels24
3.2 Moderators26
3.3 Coolants28
3.4 Cladding Materials29
3.5 Control Materials30
Self-test31
关键字解释32
词汇33
课文注释35
Unit 4 The Theory of Nuclear Reactors37
4.1 The Chain Reaction37
4.2 The Neutron Cycle in a Thermal Reactor38
4.3 Conversion and Breeding40
4.4 Fuel Cycles42
Self-test44
关键字解释45
词汇46
课文注释47
Unit 5 Nuclear Reactor Concepts49
5.1 Power Reactors49
5.2 Consumption of Nuclear Fuels50
5.3 Reactor Control51
5.4 Other Effects on Reactor Operation52
5.5 The Fast Breeder Reactor52
5.6 Uranium as an Energy Resource53
Self-test55
关键字解释55
词汇56
课文注释58
Unit 6 Nuclear Reactor Thermohydraulics59
6.1 Methods of Heat Transmission59
6.2 Conduction in Reactor Fuel59
6.3 Heat Removal by Coolant62
6.4 Boiling Heat Transfer64
Self-test66
关键字解释67
词汇68
课文注释69
Unit 7 Pressurized water Reactor71
7.1 General71
7.2 Pressurized Water Reactor Components72
7.3 Introduction to the Nuclear Steam Supply System 80+74
Self-test77
关键字解释78
词汇79
课文注释80
Unit 8 Reactor vessel and Internals82
8.1 Reactor Vessel82
8.2 Reactor Vessel Internals85
Self-test87
关键字解释88
词汇89
课文注释90
Unit 9 Reactor Core and Fuel91
9.1 Introduction91
9.2 Core91
9.3 Fuel Rod92
9.4 Fuel Assembly93
9.5 Control Element Assemblies and Drive Mechanisms95
9.6 Control Element Drive Mechanisms(CEDM)96
9.7 Neutron Sources96
9.8 Burnable Absorber Rod Assembly97
Self-test97
关键字解释98
词汇99
课文注释100
Unit 10 The Main Components in PWR Coolant System102
10.1 Steam Generators102
10.2 Pressurizer104
10.3 Reactor Coolant Pumps and Motors106
Self-test108
关键字解释109
词汇110
课文注释111
Unit 11 Pressurized Water Reactor Systems and Containment112
11.1 Plant Heat Balance and the Steam Cycle112
11.2 PWR Primary and Secondary Loops113
11.3 Auxiliary system for Primary Loop114
11.4 Containment116
Self-test120
关键字解释121
词汇122
课文注释124
Unit 12 The Steam Turbine125
12.1 Introduction125
12.2 Classification of Turbines125
12.3 Impulse and Reaction Blading127
12.4 Velocity Compounding Curtis Stage128
12.5 The Reaction-Turbine Principle128
12.6 Reaction Blading129
12.7 Sealing Arrangement129
12.8 Twisted and Tapered Blades130
12.9 Erosion Control and Moisture Removal131
12.10 Other Blade Features132
12.11 Low Pressure Turbine132
12.12 Turbine Control132
Self-test133
关键字解释134
词汇135
课文注释136
Unit 13 Main Steam,Feed and Condensate Systems138
13.1 Introduction138
13.2 Main Steam and Feedwater Piping139
13.3 Main Steam Piping System Flow Restrictor139
13.4 Safety Requirements140
13.5 Feed and Condensate System Description141
13.6 Transients143
13.7 Controls143
Self-test144
关键字解释145
词汇146
课文注释147
Unit 14 Operation of a Nuelear Power Plant149
14.1 Introduction149
14.2 Plant Safety149
14.3 Plant Operations149
14.4 Normal Mode150
14.5 Abnormal Mode152
14.6 Off-Normal(Upset)Mode153
14.7 Control Rooms and Instrumentation154
14.8 System Parameters155
Self-test156
关键字解释157
词汇157
课文注释158
Unit 15 Radiation Hazards and Shielding160
15.1 Introduction160
15.2 Health Physics160
15.3 The Biological Effects of Radiation Exposure161
15.4 The Effects of Inhaled and Ingested Radioactivity163
15.5 Reactor Shielding164
Self-test166
关键字解释167
词汇167
课文注释168
Unit 16 Nuclear Safety170
16.1 Safety and Hazards in Nuclear Power170
16.2 Reactor Accidents171
16.3 The Accident at Three Mile Island172
16.4 The Accident at Chemobyl173
Self-test177
关键字解释178
词汇178
课文注释179
Unit 17 Westinghouse AP1000 Advanced Passive Plant181
17.1 Introduction181
17.2 Major Equipment Description182
17.3 Safety Through Simplicity185
17.4 Passive Safety Systems186
17.5 Probabilistic Risk Assessment189
17.6 Simplification190
17.7 Cost and Construction Schedule192
17.8 Licensing193
17.9 AP1000 Deployment194
17.10 Conclusions195
Self-test195
关键字解释196
词汇198
课文注释199
Unit 18 European Pressurized Water Reactor(EPR)201
18.1 Introduction201
18.2 Construction Schedule204
18.3 Operation,Maintenance and Services204
18.4 Operational Flexibility205
18.5 Safety Systems206
18.6 Primary System207
Self-test211
关键词解释213
词汇213
课文注释215
Unit 19 The Heavy-Water-Moderated Reactor217
19.1 General Characteristics of the Heavy Water Reactor217
19.2 The CANDU Pressure Tube Heavy Water Reactor220
19.3 Advanced CANDU Reactor224
Self-test225
关键字解释226
词汇227
课文注释229
Unit 20 GenerationⅣNuclear Power231
20.1 Introduction231
20.2 The Gas-Cooled Fast Reactor(GFR)235
20.3 Very-High-Temperature Reactor System(VHTR)236
20.4 Supercritical Water-Cooled Reactor(SCWR)237
20.5 Sodium-Cooled Fast Reactor(SFR)239
20.6 Lead-Cooled Fast Reactor(LFR)240
20.7 Molten Salt Reactor(MSR)242
20.8 GenerationⅣand the Hydrogen Economy243
Self-test244
关键字解释245
词汇246
课文注释248
附录Ⅰ Self-test 习题答案250
附录Ⅱ 词汇表252
参考文献279