Marine Nuclear Power Technology
Junchong Yu
Marine Nuclear Power Technology
123
Junchong Yu
Nuclear Power Institute of China Chengdu, Sichuan, China
ISBN 978-981-15-2893-4 ISBN 978-981-15-2894-1 (eBook) https://doi.org/10.1007/978-981-15-2894-1
Jointly published with Shanghai Jiao Tong University Press
The print edition is not for sale in China. Customers from China please order the print book from:
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Preface
Entrusted by the Editorial Board of the series of books for“Nuclear Energy and Nuclear Technology Publication Project”, the editors began the preparatory work of the fascicle Marine Nuclear Power Technology at the beginning of 2014. As we know, with the rapid development of marine nuclear power technology and industry in recent years, lots of textbooks, monographs and popular science articles on marine nuclear power technology have been published all over the world. Making Marine Nuclear Power Technology a featured reference book becomes both an expectation of and a challenge for the editors.
Based on the analysis of the characteristics of existing related publications and the purpose of the“Nuclear Energy and Nuclear Technology Publication Project”, the orientation of this book is a professional book on the fundamentals of the R&D process and the whole lifetime management of a marine nuclear power plant. This book consists of 18 chapters: Chapter1 introduces basic types, design character- istics and development trends of marine nuclear power plants, providing the readers an overview of marine nuclear power plants; Chapter2elaborates comprehensively the design principles, methods and means for the reactor, which is the most critical part of the marine nuclear power plants, from such aspects as core physics, thermo-hydraulics, fuel design and reactor structure; Chapters 3–11 describe the design features and technological evolution of marine nuclear power plants, including the aspects of systems, equipment, instrumentation and control, radiation protection and shielding, vibration and noise reduction, mechanical analysis and evaluation, and reliability and maintainability design, etc.; Chapters12–14 intro- duce the safety analysis, operation analysis and accident management related to marine nuclear power plants, and describe the safety design concept of marine nuclear power plants and the countermeasures and response for anticipated oper- ational incidents and accidents; Chapter15focuses on the strategies, methods and application examples for aging management of marine nuclear power plants;
Chapter 16 introduces the content, methods and procedures of relevant tests throughout the design of marine nuclear power plants; Chapter17is about the fuel loading and unloading process unique to marine reactors; and Chapter18goes to the schemes and methods for marine reactor decommissioning.
v
With the support by the National Key Laboratory on Reactor System Design Technology and Nuclear Power Institute of China (NPIC), a group of experienced experts and talented staff (please refer to the Editorial Board of this book for the detailed list) were organized to write the above chapters. This book was proofread by Director Yu Hongxing, and I made thefinal check and revision.
We would like to acknowledge the valuable inputs contributed by the experts from Nuclear Power Institute of China during the writing of this book, as well as the considerable supports and assistance provided by the related administrative departments, and to express our gratitude to them all.
While we have tried our best to bring the publishing process to a conclusion as satisfactory as possible, we regret any errors you may discover and appreciate any suggestions or comments.
Chengdu, China Junchong Yu
vi Preface
Acknowledgements
In the process of writing this book, the author does all chapter’s designs and the content framework of the whole book. I would like to thank the following experts (in alphabetical order by surname) for contribution to the details of the book.
The translation of this book from its Chinese version is done by the following experts (in alphabetical order by surname), and I would like to extend thanks to them.
English translated by: Jiaquan Hu, Ming Lei, Yang Lan, Lihua Qin, Xue Xiong, Yue Zhang.
English proofread by: Xuedong Huang, Qiong Zhang.
Gratitude to Dr. Yingchun Yang from Shanghai jiaotong University Press for her effort to organize.
Junchong Yu
Xiaoming Chai Zhi Chen Xingdou Gao Xiaoqiang He
Xindong Huang Guangming Jiang Changxiang Li Yuanming Li
Longtao Liao Wenjin Liu Chuan Lu Zongjian Lu
Ying Luo Biao Quan Danrong Song Bin Tang
Hong Yang Dong Yao Hongxing Yu Wei Zeng
Lin Zhang
vii
Contents
1 Overview. . . 1
1.1 Introduction . . . 1
1.2 Basic Types of Nuclear Power Ships . . . 3
1.2.1 Nuclear Submarines . . . 3
1.2.2 Nuclear-Powered Aircraft Carriers. . . 4
1.2.3 Nuclear-Powered Cruisers. . . 5
1.2.4 Nuclear-Powered Deep-Sea Facilities. . . 5
1.2.5 Nuclear-Powered Icebreakers . . . 5
1.2.6 Nuclear-Powered Merchant Ships . . . 6
1.3 Design Characteristics and Development Trends of Marine Nuclear Power Plants . . . 6
1.3.1 Design Characteristics. . . 6
1.3.2 Development Trends. . . 7
Reference. . . 9
2 Nuclear Reactors. . . 11
2.1 Overview . . . 11
2.2 Nuclear Reactor Physics . . . 12
2.2.1 Theory of Nuclear Reactor Physics . . . 13
2.2.2 Reactor Nuclear Design . . . 33
2.2.3 Software for Reactor Nuclear Design. . . 34
2.2.4 Design Verification. . . 35
2.3 Reactor Thermo-Hydraulics. . . 37
2.3.1 Overview. . . 37
2.3.2 Reactor Heat Transfer Theory. . . 38
2.3.3 Reactor Hydraulics. . . 48
2.3.4 Reactor Thermo-Hydraulic Design. . . 56
2.3.5 Reactor Thermo-Hydraulic Test. . . 68
ix
2.4 Fuel Assembly and Core Components . . . 69
2.4.1 Fuel Assembly. . . 69
2.4.2 Core Components. . . 88
2.5 Reactor Pressure Vessel . . . 93
2.5.1 Overview. . . 93
2.5.2 A Brief Introduction to Structure. . . 94
2.5.3 Materials . . . 99
2.5.4 Design Analysis and Verification . . . 104
2.6 Control Rod Drive Mechanism . . . 104
2.6.1 Overview. . . 104
2.6.2 A Brief Introduction to Structure. . . 105
2.6.3 Materials . . . 106
2.6.4 Design Analysis and Verification . . . 106
2.7 Reactor Internals. . . 107
2.7.1 Overview. . . 107
2.7.2 A Brief Introduction to Structure. . . 107
2.7.3 Materials . . . 109
2.7.4 Design Analysis and Verification . . . 111
2.8 Reactor Support and Shielding. . . 112
2.8.1 Overview. . . 112
2.8.2 A Brief Introduction to Structure. . . 113
2.8.3 Reactor Shielding Design . . . 113
2.8.4 Shielding Materials. . . 114
2.8.5 Reactor Support Materials. . . 118
2.8.6 Design Analysis. . . 122
References . . . 123
3 Reactor Coolant System (RCS). . . 125
3.1 Overview . . . 125
3.1.1 Functions. . . 125
3.1.2 System Composition. . . 125
3.1.3 System Process . . . 126
3.2 Design Requirements . . . 128
3.3 System Arrangement. . . 129
3.3.1 Separated Arrangement. . . 130
3.3.2 Compact Arrangement . . . 130
3.3.3 Integrated Arrangement. . . 131
3.4 Characteristic Design . . . 131
3.4.1 Operation Scheme with Constant Average Coolant Temperature . . . 132
3.4.2 Operation Scheme with Constant Steam Pressure. . . 133
3.4.3 Compromised Solution. . . 133
3.4.4 Static Characteristics of Once-Through Steam Generator. . . 134
x Contents
3.5 Brief Introduction to Main Equipment . . . 135
3.5.1 Steam Generator. . . 135
3.5.2 Reactor Coolant Pump . . . 150
3.5.3 Reactor Coolant Piping. . . 155
3.6 Reactor Coolant Water Chemistry . . . 157
References . . . 160
4 Nuclear Auxiliary Systems . . . 161
4.1 Overview . . . 161
4.2 Pressure Safety System . . . 162
4.2.1 System Description. . . 163
4.2.2 Equipment Description . . . 164
4.3 Residual Heat Removal System. . . 168
4.3.1 System Description. . . 169
4.3.2 Equipment Description . . . 169
4.4 Coolant-Charging System . . . 170
4.4.1 System Description. . . 170
4.4.2 Equipment Description . . . 171
4.5 Component Cooling Water System . . . 171
4.5.1 System Description. . . 171
4.5.2 Equipment Description . . . 172
4.6 Coolant Purification System. . . 173
4.6.1 System Description. . . 173
4.6.2 Equipment Description . . . 174
4.7 Valves . . . 176
4.7.1 Overview. . . 176
4.7.2 Shut-off Valves . . . 177
4.7.3 Safety Valves. . . 179
4.7.4 Check Valves. . . 180
4.7.5 Regulating Valves . . . 180
4.7.6 Valve Reliability . . . 181
References . . . 183
5 Engineered Safety System. . . 185
5.1 Overview . . . 185
5.1.1 Design Principles for Engineered Safety System. . . 186
5.1.2 Basis for Determining Engineered Safety System. . . 186
5.1.3 Design Characteristics of Engineered Safety System of Marine Nuclear Power Plants . . . 187
5.2 Emergency Core Cooling System. . . 188
5.2.1 Safety Injection System . . . 188
5.2.2 Emergency Residual Heat Removal System. . . 190
5.3 Reactor Compartment Heat Removal System . . . 193
5.4 Dehydrogenation System. . . 194
Contents xi
5.5 Backup Reactor Shutdown System. . . 195
5.6 Case Analysis of Design Flow of Safety Injection System. . . 196
References . . . 199
6 Instrumentation and Control System . . . 201
6.1 Overview . . . 201
6.1.1 Functions of I&C System. . . 201
6.1.2 Design Principles. . . 202
6.1.3 Overall Structure and Characteristics . . . 203
6.2 Nuclear Measurement System . . . 205
6.2.1 System Functions. . . 205
6.2.2 Basic Principle of Ex-core Nuclear Measurement Detectors. . . 206
6.2.3 Description of the System and Equipment . . . 208
6.3 Process Measurement and Control System . . . 210
6.3.1 Process Measurement System . . . 210
6.3.2 Process Control System . . . 213
6.4 Reactor Power Control System . . . 218
6.4.1 System Functions. . . 218
6.4.2 Principles of Reactor Power Regulation. . . 221
6.4.3 Design Constraints. . . 225
6.4.4 Description of the System and Equipment . . . 226
6.5 Reactor Protection System. . . 228
6.5.1 System Functions. . . 228
6.5.2 System Design Principles . . . 229
6.5.3 System and Equipment Description. . . 231
6.6 Control Rod Control and Rod Position Measuring System . . . . 234
6.6.1 Functions. . . 234
6.6.2 System and Equipment Description. . . 235
6.7 Electrical Control System for Pumps and Valves . . . 238
6.7.1 System Functions. . . 238
6.7.2 System and Equipment Description. . . 239
6.8 Man-Machine Information Display and Operation System. . . 241
6.8.1 Functions. . . 241
6.8.2 System Design Principles . . . 242
6.8.3 System and Equipment Description. . . 243
6.9 Digitization of I&C System. . . 244
6.9.1 Technological Development Overview. . . 244
6.9.2 Technical Schemes of Digital I&C System . . . 246
References . . . 250
7 Steam Power Conversion System . . . 253
7.1 Overview . . . 253
7.2 Steam System. . . 255
xii Contents
7.2.1 System Description. . . 255
7.2.2 Equipment Description . . . 256
7.2.3 System Operation. . . 257
7.3 Condensate and Feedwater System. . . 257
7.3.1 System Description. . . 257
7.3.2 Equipment Description . . . 258
7.3.3 System Operation. . . 260
7.4 Steam Dump System. . . 260
7.4.1 System Description. . . 260
7.4.2 Equipment Description . . . 261
7.5 Circulating Cooling Water System. . . 262
7.6 Steam Turbine-Gear Unit . . . 264
7.6.1 Turbines . . . 264
7.6.2 Gear Reducer. . . 265
7.7 Turbo-Generator Set . . . 266
Reference. . . 267
8 Source Term and Radiation Protection. . . 269
8.1 Concept and Principles of Radiation Protection. . . 269
8.1.1 Concept of Radiation Protection . . . 269
8.1.2 Ionization Radiation Source of Nuclear Power Plants . . . 271
8.1.3 Basic Principles of Radiation Protection . . . 271
8.1.4 Dose Limit for Radiation Protection . . . 272
8.1.5 Design Principles for Radiation Protection of Marine Nuclear Power Plant. . . 273
8.1.6 Characteristics of Radiation Protection for Marine Nuclear Power Plant. . . 274
8.2 Source Term Design. . . 275
8.2.1 Overview. . . 275
8.2.2 Source Terms Under Normal Operation. . . 275
8.2.3 Source Terms in Accidents. . . 277
8.3 Radiation Protection Facilities . . . 279
8.4 Management of Radiation Protection Work . . . 280
8.4.1 Control Through Radiation Zoning . . . 280
8.4.2 Emergency Plan. . . 280
8.4.3 Radiation Protection Requirements for Nuclear Power Plant at Each Stage . . . 280
References . . . 282
9 Vibration and Noise Reduction. . . 283
9.1 Overview . . . 283
9.2 Sources and Transfer Paths of the Vibration Noise . . . 283
9.3 Control Measures for Vibration Noise . . . 284
Contents xiii
9.3.1 Control Measures for Vibration Noise. . . 284
9.3.2 Vibration Isolation of Transfer Paths. . . 285
References . . . 287
10 Mechanical Analysis and Evaluation. . . 289
10.1 Overview . . . 289
10.2 Main Theories of Mechanical Analysis. . . 290
10.2.1 Analysis Theory for Shock Resistance of System and Equipment. . . 290
10.2.2 Analysis Theory for Structural Stress. . . 300
10.3 Main Methods for Mechanical Analysis. . . 305
10.3.1 Theoretical Analysis. . . 305
10.3.2 Finite Element Method. . . 306
10.3.3 Experimental Research Methods . . . 308
10.4 Main Content of Mechanical Analysis . . . 309
10.4.1 Load Distribution of Systems and Equipment. . . 309
10.4.2 Stress Analysis for Structures and Components . . . 311
10.5 Analysis and Evaluation . . . 315
10.5.1 Load Distribution of Systems and Equipment. . . 315
10.5.2 Stress Analysis of Structures and Components. . . 318
10.5.3 Analysis Example. . . 319
References . . . 323
11 Reliability and Maintainability Design . . . 325
11.1 Overview . . . 325
11.2 Reliability and Maintainability Management. . . 326
11.3 Reliability Design and Analysis. . . 327
11.3.1 Reliability Requirements. . . 327
11.3.2 Methods for Reliability Design. . . 328
11.4 Design and Analysis of Maintainability . . . 333
11.4.1 Maintainability Requirements . . . 333
11.4.2 Qualitative Maintainability Design. . . 334
11.4.3 Allocation and Prediction of Maintainability . . . 336
11.5 Tests and Evaluation of Reliability . . . 337
11.5.1 Environmental Stress Screening Test. . . 338
11.5.2 Reliability Growth Test . . . 339
11.5.3 Reliability Qualification Test and Reliability Acceptance Test. . . 339
References . . . 340
12 Accident and Safety Analysis . . . 341
12.1 Overview . . . 341
12.2 Accident Analysis Methods. . . 342
xiv Contents
12.2.1 Deterministic Accident Analysis . . . 343
12.2.2 Probabilistic Safety Analysis. . . 345
12.3 Classification and Analysis Requirements for Design Basis Accidents . . . 346
12.3.1 Accident Classification and Limit Criteria . . . 346
12.3.2 Reactivity Insertion Accidents. . . 349
12.3.3 Loss-of-Flow Accidents . . . 350
12.3.4 Loss of Heat Sink Accidents. . . 350
12.3.5 Steam Generator Tube Ruptures . . . 351
12.3.6 Loss of Coolant Accidents . . . 351
12.3.7 Ship Blackout Accidents. . . 352
12.3.8 Anticipated Transients Without Scram. . . 353
12.4 Accident Analysis Cases. . . 353
12.4.1 Causes of Ship Blackout Accidents. . . 353
12.4.2 Frequency of Occurrence and Limiting Criteria of Ship Blackout Accidents. . . 354
12.4.3 Analysis Methods and Assumptions of Ship Blackout Accidents. . . 354
12.4.4 Analysis Results of Ship Blackout Accidents. . . 355
12.4.5 Severe Accidents . . . 356
12.4.6 Major Phenomena and Processes of Severe Accidents. . . 356
12.4.7 Severe Accident Prevention and Mitigation . . . 357
Reference. . . 360
13 Operation and Operation Analysis . . . 361
13.1 Overview . . . 361
13.2 Operation. . . 362
13.2.1 Initial Cold Start-Up. . . 362
13.2.2 Normal Cold Start-Up . . . 362
13.2.3 Steady-Power Operation . . . 363
13.2.4 Variable Condition Operation . . . 364
13.2.5 Natural-Circulation Operation . . . 365
13.2.6 Cold Shutdown of Reactor System . . . 365
13.2.7 Hot Shutdown and Hot Start-Up of Reactor System . . . 366
13.2.8 Reactor Operation Under Abnormal Conditions . . . 368
13.3 Operation Analysis of Reactor Accident Conditions . . . 369
13.3.1 Purpose. . . 369
13.3.2 Methods . . . 370
13.3.3 Content . . . 370
Contents xv
13.4 Operation Analysis Cases . . . 370
13.4.1 Analysis of Transition Between Forced Circulation and Natural Circulation. . . 370
13.4.2 Operation Analysis of LOCAs . . . 375
References . . . 378
14 Accident Management. . . 379
14.1 Overview . . . 379
14.2 Objectives of the Accident Management. . . 380
14.3 Accident Management Methods. . . 381
14.4 Objects of Accident Management . . . 383
14.5 Diagnostic Methods for Thermo-Hydraulic Phenomena in Typical Accidents. . . 383
14.6 Emergency Response to Accidents. . . 385
15 Ageing Management. . . 393
15.1 Concept of Ageing Management . . . 393
15.1.1 Concept of Ageing and Its Management . . . 393
15.1.2 Method for Systematic Ageing Management . . . 394
15.1.3 Relationship Between Ageing Management and Current Operation Management . . . 394
15.1.4 Purposes and Significance of Ageing Management of Marine Nuclear Power Plants . . . 395
15.2 Status of Ageing Management. . . 396
15.3 Strategies for Ageing Management . . . 398
15.3.1 Overview. . . 398
15.3.2 Design. . . 398
15.3.3 Fabrication and Construction. . . 399
15.3.4 Commissioning . . . 399
15.3.5 Operation. . . 400
15.3.6 Decommissioning. . . 400
15.4 Ageing Management During Operation . . . 401
15.4.1 Screening of Ageing-Sensitive Systems and Equipment. . . 401
15.4.2 Ageing Management Program for Marine Nuclear Power Plants. . . 404
15.4.3 Aging Mechanism Analysis for Aging-Sensitive Equipment. . . 406
15.4.4 Equipment Ageing Management Program . . . 409
15.4.5 Data Collection and Retention for Ageing Management . . . 412
15.4.6 Actual Status Evaluation of Ageing-Sensitive Equipment. . . 413
15.4.7 Ageing Management Review . . . 414
xvi Contents
15.5 Application of Ageing Management in Lifetime Extension . . . . 415
15.5.1 Application of Ageing Management Results in the Demonstration of Lifetime Extension. . . 415
15.5.2 Requirements of Ageing Management in the Extended Lifetime . . . 416
16 Test Verification . . . 419
16.1 Overview . . . 419
16.2 Classification of Tests for Marine Nuclear Power Plant. . . 420
16.3 Comprehensive Verification Tests of Systems. . . 421
16.3.1 Function of Comprehensive Verification Tests of Systems. . . 421
16.3.2 Content of Comprehensive Verification Tests of Systems. . . 421
16.4 Reactor Physical Start-Up Tests. . . 422
16.4.1 Definition of Physical Start-Up Tests. . . 422
16.4.2 Stages of Physical Start-Up Test . . . 423
16.4.3 Brief Introduction of Physical Start-Up Test. . . 423
16.5 Mooring Tests and Sea Trials . . . 424
16.5.1 Overview. . . 424
16.5.2 Mooring Tests . . . 425
16.5.3 Sea Trials . . . 428
16.6 Engineering Assessment Tests of Prototype Reactors . . . 429
16.6.1 Significance and Role of Prototype Reactors . . . 429
16.6.2 Content of Engineering Assessment Tests of Prototype Reactors . . . 430
16.6.3 Development of Prototype Reactors. . . 430
16.6.4 Development Trend of Prototype Reactors. . . 431
16.7 Virtual Tests and Digital Reactor System Simulation Verification . . . 433
16.7.1 Virtual Tests . . . 433
16.7.2 Definition and Role of Digital Reactors. . . 434
16.7.3 Overview of Digital Reactor Research. . . 434
16.7.4 Technical Route of the Digital Reactor Development . . . 436
References . . . 438
17 Reactor Loading and Unloading. . . 439
17.1 Overview . . . 439
17.1.1 System Functions. . . 439
17.1.2 System Composition. . . 439
17.1.3 Main Process Flow. . . 440
17.1.4 Design Principles. . . 441
17.2 Reactor Fuel Loading . . . 441
Contents xvii
17.2.1 Reactor Fuel Loading Technology. . . 441
17.2.2 Reactor Fuel Loading Process. . . 442
17.2.3 Main Equipment for Reactor Loading . . . 443
17.3 Reactor Fuel Unloading. . . 443
17.3.1 Reactor Fuel Unloading Technology . . . 443
17.3.2 Reactor Fuel Unloading Process . . . 444
17.3.3 Main Reactor Fuel Unloading Equipment . . . 444
17.4 Design of Reactor Refueling . . . 445
17.4.1 Selection of Materials. . . 445
17.4.2 Cooling Design . . . 446
17.4.3 Criticality Safety Evaluation . . . 448
17.4.4 Industrial Safety Design . . . 448
17.4.5 Design of Radiation Protection Safety . . . 449
18 Decommissioning of Marine Nuclear Power Plants. . . 451
18.1 Overview . . . 451
18.2 Decommissioning Scheme Study. . . 452
18.2.1 Decommissioning Schemes in Foreign Countries . . . 454
18.2.2 Decommissioning Scheme in China. . . 456
18.3 Study on the Status of Nuclear Power Plant Before Decommissioning . . . 456
18.3.1 Investigation of Reactor Operation History . . . 456
18.3.2 Calculation and Measurement of Residual Radioactivity . . . 457
18.3.3 Calculation of Reactor Residual Heat Release and Measurement of Related Temperature . . . 458
18.3.4 Inspection of Reactor Control Rod Positions . . . 459
18.3.5 Tests of Performance of Pumps, Valves and Systems. . . 459
18.4 Reactor Decommissioning. . . 460
18.4.1 Decommissioning Procedure. . . 460
18.4.2 On-site Condition Preparation. . . 460
18.4.3 Reactor Unloading . . . 461
18.4.4 Decontamination . . . 462
18.5 Decommissioning of Circuit Systems and Other Equipment in the Reactor Compartment . . . 463
18.6 Treatment of Radioactive Wastes. . . 464
18.7 Radiation Protection and Safety. . . 465
18.7.1 Classification and Management of Work Place. . . 465
18.7.2 Management of Operators. . . 466
18.7.3 Safety Measures for Radiation Protection. . . 466
18.7.4 Strengthening of Radiation Monitoring . . . 467
Index . . . 469
xviii Contents
