Nuclear Power Plants: Innovative Technologies for Instrumentation and Control Systems (eBook)

The Fourth International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant (ISNPP)

Yang Xu, Yongbin Sun, Yanyang Liu, Yanjun Wang, Pengfei Gu, Zheming Liu (Herausgeber)

eBook Download: PDF

2020 | 1st ed. 2020
XIII, 571 Seiten
Springer Singapore (Verlag)
978-981-15-1876-8 (ISBN)

Infos

This book presents a compilation of selected papers from the Fourth International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, held in August 2019 in Guiyang, China. The purpose of the symposium was to discuss inspection, testing, certification and research concerning the software and hardware of instrument and control (I&C) systems used at nuclear power plants (NPP), such as sensors, actuators and control systems. The event provides a venue for exchange among experts, scholars and nuclear power practitioners, as well as a platform for the combination of teaching and research at universities and enterprises to promote the safe development of nuclear power plants. Readers will find a wealth of valuable insights into achieving safer and more efficient instrumentation and control systems.

1. Dr. Yang Xu received his doctoral degree from the Department of Engineering Physics of Tsinghua University, Beijing, China, in 2003. After obtaining his degrees, Dr. Xu worked for Institute of Nuclear and New Energy Technology (INET) of Tsinghua University from year 2003 to 2014; after that, he returned to the Department of Engineering Physics. Since December 2010, he served as Associate Professor and National Registered Consulting Engineer. Dr. Xu's research focuses on the nuclear fuel cycle and instrument control. He has directed, participated and finished several projects on this area, such as 'Study on Common Cause Failure of Digital Instrument', 'Standards and Literature's Research of Digital Control Room Modernization Program', 'Seismic stability Design, Identification and Verification for Large LCD screen for Nuclear Power Plant', 'Expert System for Numerical Operation of Nuclear Power Plant' and so on. His research work has won the third-grade prize of national defense science and technology.

2. Yongbin Sun works as Deputy General Manager of China Techenergy Co., Ltd, a researcher-level senior engineer mainly engaged in design and project management of nuclear power plant (NPP) digital instrument and control (I&C) systems. Mr. Sun undertook and completed 4 research projects of the National 863 Program, took over the I&C design work of 14 CPR1000 units and Yangjiang Units 5 & 6 and participated in the I&C design of EPR units. Mr. Sun is one of the team leaders in charge of preparation of the top standards in nuclear power I&C industry, which were organized the National Energy Administration (NEA). He is also a Leading Talent in Shenzhen.

3. Mr. Yanyang Liu was graduated from Engineering Physics Department of Tsinghua University, Beijing, China, in 1992. And Mr. Liu worked for Nuclear Power Institute of China from 1992 to now. Since December 2007, he served as Professor Senior Engineer. Since October 2013, he was appointed by the institute as chief expert in the field of reactor instrument and control. Mr. Yanyang Liu is engaged in the research and design of nuclear I&C more than 20 years, who has plenty experience in the field of in-core and ex-core nuclear instrumentation, reactor control, DCS and so on. The main project Mr. Liu had taken include design and research of I&C of Qinshan phase II and extension, Fangjiashan and Fuqing, development of the third generation in-core instrumentation system and DCS for ACP1000, and I&C system design and research of experiment nuclear facility.

4. Ms. Yanjun Wang got the bachelor's degree from Electrical Engineering Department of Beijing Mechanical Engineering Institute in 1991 and got the master's degree from Engineering Physics Department of Tsinghua University in 2010. From year 1991 up to now, she has been working in I&C Department of China Nuclear Power Engineering Co., Ltd. Ms. Yanjun Wang works on instrumentation and control systems design for nuclear power plants, and she had participated in many NPPs design. She had also taken the lead on drafting some standards, such as NB/T 20342-2015 and NB/T 20054-2011. She is the membership of IAEA I&C technical group, the membership of WGA7 of IEC45A. She had won several second- and third-grade prizes of China Nuclear Energy Association.

5. Dr. Pengfei Gu received the Ph.D. degree in Institute of Nuclear and New Energy Technology from Tsinghua University, Beijing, China. Currently, he worked at China Nuclear Power Design Co., Ltd (Shenzhen). In recent years, he worked on software verification and validation of safety instrument and control system for nuclear power plants. Dr. Gu mainly focuses on the research of software verification and validation. His recent research interests include software aging management, software reliability analysis and the safety and security of software. He has won the first prize in Science and Technology of China Instrument and Control Society and China Patent Excellence Award.

6. Mr. Zheming Liu studied Enterprise Financial Accounting in Jilin College of Finance & Taxation and Computer Software and Applications at Jilin University between 1996 and 2013. Working as Special Assistant to secretariat of China Instrument and Control Society and Secretary General of Product Information Committee of China Instrument and Control Society from 2013, Mr. Liu organized forums, conferences, training, salons and exhibitions more than 200 times in instrumentation and petroleum field, pushing forward China Instrument and Control Society which now ranked one of the most professional organizations in this field. Working with professors and experts, Mr. Liu manages professional publications such as Manual of Petrochemical Engineering Measurement and Control, Processing Industries Automatic Measurement and Application, Manual of Petrochemical Machinery, New Techniques and Applications of Petrochemical Engineering.

Inhalt

Preface 6
Organization 8
Hosts 8
Organizers 8
Co-organizers 8
Editors 8
Secretary of Organizing Committee 9
Director of Executive Committee 9
Contents 10
Analysis and Countermeasures of Inconsistency for Acoustic Design and Lighting Design Regulations and Standards in Main Control Room of Nuclear Power Plant 15
Abstract 15
1 Introduction 15
2 Standard System of Environmental Design Laws and Regulations for MCR 16
3 Requirements of Design Regulations and Standards for MCR and Analysis of Current Situation in Operating Power Plant 17
3.1 Acoustic Design in MCR 17
3.2 Lighting Design in MCR 19
4 Correct and Error Analysis of Environmental Part Standard Description of MCR 21
5 Concluding Remarks 22
References 22
Application of Mixed Reality Based on Hololens in Nuclear Power Engineering 23
Abstract 23
1 Application of MR in Nuclear Power Engineering 23
1.1 Design of Nuclear Power Engineering 24
1.2 Equipment Maintenance 24
1.3 Staff Training 25
2 Solutions of MR 26
2.1 Collaborative Design 26
2.2 Intelligent Maintenance 28
2.3 Training System for HPR1000 30
3 Analysis of Application Effect 33
4 Conclusion 33
References 34
Visualization of Geologic Engineering Data Based on Nuclear Power Plant 35
Abstract 35
1 Research Background 35
2 Visualization Blue Print 36
2.1 Data Collection 36
2.2 Data Management 37
2.3 Arithmetic Disposal 38
2.4 Three-Dimensional Imaging 40
3 Visualization Application 41
4 Conclusion and Expectation 42
References 42
Research on Defense-in-Depth Zone of Low-Altitude Security Area in Nuclear Power Plant 44
Abstract 44
1 Preface 44
2 Analysis of Low-Altitude Defense Zones in Nuclear Power Plants 45
2.1 Analysis of Nuclear Power Plant Security Area 45
2.2 Analysis of the Intrusion UAV 46
2.3 Analysis of Detection Equipment 47
2.4 Analysis of Response Time 48
3 Defense-in-Depth Zone of Low-Altitude Area in NPPs 49
3.1 Proposal for Defense-in-Depth Zone of Low-Altitude Area in NPPs 49
3.2 Problems 50
4 Conclusion 51
References 51
Research on Axial Power Deviation Safety Early Warning Technology Based on Online Simulation 52
Abstract 52
1 Introduction 52
2 Mechanism of Online Simulation Technology 53
3 Axial Power Deviation Safety Early Warning Technology 54
3.1 Safety Early Warning Mechanism and Axial Power Deviation 54
3.2 Early Warning for Axial Power Deviation ?I Control 55
3.3 System Verification 58
4 Conclusions 58
References 59
Integrated Digital Control Platform for Flywheel Systems with Active Magnetic Bearings 60
Abstract 60
1 Introduction 60
2 Nonintegrated Digital Control System 62
2.1 Insufficient of the Single-Core DSP Control Platform 63
2.2 Similar Tasks Between the Digital Control Board and the Amplifier Control Board 63
2.3 Higher Integration Degree 65
3 Integrated Digital Control System 65
3.1 Dual-Core DSP 66
3.2 Integration of the Digital Control Board, the Power Amplifier Control Board and the Displacement Sensor Board 66
3.3 Control Parameter Adjustment on Line 67
4 Function Implement 67
4.1 Board Integration 68
4.2 Experiments Using the Integrated Platform to Replace the Nonintegrated Platform 68
4.3 Control Parameter Adjustment on Line 70
5 Conclusion 71
Acknowledgments 71
References 71
Off-Line Performance Calculating Software of the Secondary Loop Thermal System in AP1000 Nuclear Power Plant 72
Abstract 72
1 Introduction 72
2 Offline Software Theoretical Calculation Model 73
2.1 Design Condition Module Main Equipment Calculation Model 73
2.2 Variable Working Condition Module Calculation Model 75
2.3 Consumption Difference Analysis Module Calculation Model 76
3 Off-Line Software Development Environment 76
3.1 Off-Line Software Development Platform 76
3.2 Off-Line Software Program Execution Block Diagram 77
4 Off-Line Software Function Module 78
4.1 Design Conditions Module 79
4.2 Variable Working Condition Analysis Module 81
4.3 Dissipation Analysis Module 81
5 Conclusion 81
References 82
Monitoring and Analyzing of Wall Temperature Fluctuations for Thermal Fatigue in Elbow Pipe 83
Abstract 83
1 Introduction 83
2 Model Analysis 84
2.1 Inversion Heat Conduction 84
2.2 Interpolation Analysis of Temperature Fields 85
3 Model Solving and Calculation 88
3.1 Pipe Structural Information 88
3.2 Solving of Inner and Outer Wall Temperatures at the Analysis Point 8 88
3.3 Solving of Inner and Outer Wall Temperatures at the Analysis Point 9 90
4 Test and Analysis 91
4.1 Experiment Condition 91
4.2 Meshing and Boundary Conditions 91
4.3 Results Analysis 92
5 Conclusions 96
References 96
Discussions on Information Security Test Strategy for Digital Industrial Control System in Nuclear Power Plant 97
Abstract 97
1 Introduction 97
2 Related Works 98
2.1 Difference Between Industrial Control System and IT System 98
2.2 Status of Application of Industrial Control System in Nuclear Power Plants 98
3 Nuclear Electric Control System Information Security Layering Model 99
4 Nuclear Power Plant Industrial Control System Safety Test 100
4.1 Human-Machine Layer Test 101
4.2 Network Transport Layer Test 101
4.3 Entity Layer Test 101
4.4 Enterprise Layer Test 102
4.5 Nuclear Power Plant Information Security Defense in Depth 102
5 Conclusions 103
References 103
Study and Implementation on General Operating Procedure of CPR1000 Main Control Room in China 104
Abstract 104
1 Introduction 105
2 General Operating Procedure of CPR1000 Main Control Room 106
2.1 Structure and Operating Means 107
2.2 Navigation 108
2.3 Data Integrity and Monitoring 109
2.4 Computerized Operating Modes 110
2.5 Document Management 110
3 Human Factor Engineering 111
3.1 Commissioning Test Results 112
3.2 Application Results 113
4 Conclusions 113
References 113
Inductive Displacement Sensors Based on the Integrated Demodulation Chip 115
Abstract 115
1 Introduction 115
2 Design and Principle 116
2.1 Sensor Principle 116
2.2 Synchronous Demodulation 117
2.3 ADA2200 118
3 Hardware Design 119
4 Software Design 120
4.1 The Configuration of the ADA2200 120
4.2 Data Collecting of the ADC 121
5 Experimental Results and Discussion 121
5.1 The Build of the Test Platform 121
5.2 Debugging with an Oscilloscope 122
5.3 Signal Acquisition and Processing 123
6 Conclusion 124
Acknowledgments 125
References 125
The Development of TMSR-SF0 Simulation Protection System 126
Abstract 126
1 Introduction 126
2 System Design 127
2.1 System Configuration 127
2.2 Signal Processing Chassis and Logic Processing Chassis 128
2.3 Local Engineer Stations 129
2.4 One-Way Gateways 129
2.5 Safety Panel 130
2.6 Simulation Nuclear Instrument System 131
2.7 Periodic Test Device 131
3 RPS Experiment 131
4 Conclusions 133
References 133
Assessment of Operating Safety State of Nuclear Power Plant Based on Improved CAE Method 134
Abstract 134
1 Introduction 134
2 State Assessment Method Based on CAE Theory 135
2.1 Simplified State Assessment Method Based on CAE Theory 135
2.2 Quantification of Assessment Results 136
3 A Variable Weight Analytical Hierarchy Process Algorithm for Assessment Model 137
3.1 Variable Weight Algorithm and Weights Optimization 137
4 Establishment of Operation Safety Assessment Model for Nuclear Power Plant 139
4.1 The Assessment of Integrity State of Pressure Boundaries in Nuclear Power Plants 139
4.2 The Determination of Weights 139
5 The Verification of Operation Safety Assessment for Nuclear Power Plant 140
6 Conclusion 141
References 142
Analysis and Solution of Design Difficulties of HMI with Scale Increase in Limited Space 143
Abstract 143
1 Introduction 143
2 Analysis of HMI Change 143
3 Formulating Effective Coping Strategies 145
4 Design Scheme of HMI 147
5 Conclusions 148
References 148
Application Analysis of Wireless Sensor Networks in Nuclear Power Plant 149
Abstract 149
1 Introduction 149
2 Wireless Sensor Network Architecture and Node Composition 150
3 Application of Wireless Sensor Networks in Nuclear Power Plant 151
3.1 Application Status 151
3.2 Application Analysis 153
4 Technical Feasibility Analysis 154
4.1 Anti-jamming Technology 154
4.1.1 Spread Spectrum Frequency Hopping 154
4.1.2 Ultra-Wideband Communication Technology 154
4.1.3 Separation Limits Between I& C Equipment and Wireless Devices
4.1.4 Cognitive Wireless Anti-Jamming Based On Machine Learning 156
4.2 Low Power Technology 156
4.2.1 Sleep/Wake Mechanism 156
4.2.2 Power Management 157
4.3 Wireless Coexistence Measures 158
4.4 Information Safety 159
4.5 Anti-irradiation Measures 160
5 Conclusion 161
References 161
Development and Application of Intelligent Platform for Collaborative Electrical Design of Nuclear Power 163
Abstract 163
1 Introduction 163
2 Electrical Design Platform 164
2.1 Project Information 164
2.2 Construction Objectives 164
2.3 Features of Electrical Design Platform 165
3 Platform Technical Scheme and Functions 165
3.1 System Architecture 165
3.2 Platform Application Framework 166
3.3 Function Modules 167
4 Platform Application and Advantages 168
4.1 User Rights Management 168
4.2 Intelligent Applications 169
4.3 Platform Advantages 172
5 Applications in Nuclear Power 172
5.1 Project Application Status 172
5.2 Deficiencies and Improvement Direction 174
6 Conclusion 174
References 175
Research on Stewardship-Intensive Digital Procedure System 176
Abstract 176
1 Preface 176
2 General Introduction 177
2.1 Development of Digital Procedure of NPPs 177
2.2 Overall Goal of SIDPS 177
2.3 Function of SIDPS 178
3 Technology Implementation of SIDPS 178
3.1 Logical Architecture Design 178
3.2 System Deployment 179
3.3 Workflow of SIDPS 180
4 Improved Function of SIDPS 181
5 Conclusions and Prospects 182
References 182
Study and Optimization of Load Fluctuation of the Turbine Generator After Connected to the Grid in Nuclear Power Plant 183
Abstract 183
1 Preface 183
2 Technology Description of the Turbine Speed and Load Control 184
3 Study in Load Fluctuation and Optimization of the Control Scheme 185
3.1 Optimization of the Grid Connection Scheme 186
3.2 Optimization of the Load Closed Loop Control 186
4 Conclusion 188
References 188
Study for Design and Application of Procedure-Based Automation in Nuclear Power Plant 190
Abstract 190
1 Types of Operating Procedures 190
2 Consideration for CBPs Design and Application 191
3 Characterization Framework of PBA 192
4 Design and Application of PBA 192
4.1 Automatic Diagnosis of Plant Conditions 192
4.2 Architecture of the CBPs of PBA 193
4.2.1 Start/Stop by Operators 194
4.2.2 Plant Parameters and Soft Controller Integrated into CBPs 194
4.2.3 Automatic Calculation of Procedure Steps 194
4.2.4 Dynamic Path Indication 195
4.2.5 Automatic Control Selected by Operator 195
4.2.6 Record Function 195
5 Verification 195
6 Conclusion 198
References 198
Research on KDA System Reliability Model Based on Total Probability Formula 199
Abstract 199
1 Introduction 199
2 Analysis of Serious Accident Instrument Control System 200
3 Application of Full Probability Formula 200
3.1 Sample Space Division 200
3.2 Derivation of the Full Probability Formula 201
4 Derivation of Reliability Model Based on Full Probability Formula 201
4.1 Sample Space Division 202
4.2 Dual Unit Failure Mode 203
4.3 Single Unit Failure Mode 204
4.4 No Unit Failure Mode 205
5 Model Calculation and Analysis 205
6 Conclusion 207
References 207
The Research and Application of Test Method for 1E I& C System Platform’s Change
Abstract 208
1 Introduction 208
2 Standard Requirements for Nuclear Safety Product Changes 209
3 Technical Solutions 210
3.1 Process Integrity 210
3.2 Test Adequacy 211
4 Application Practice 212
5 Conclusion 215
References 215
Research and Application of a User Interface Automatic Testing Method Based on Data Driven 216
Abstract 216
1 Introduction 216
2 Technical Solution Realization 218
2.1 Basic Widget Library 219
2.2 Basic Operation Library 220
2.3 The Test Data 220
3 Test Case Realization 222
4 Test Case Execution 223
5 Practical Application and Effect 224
6 Conclusion 224
References 224
Research on a Certainty Data Link Layer Protocol for the Communication Network in Nuclear Safety DCS 226
Abstract 226
1 Introduction 226
2 Certainty for Safety Communication Protocols 227
2.1 Certainty Required by Standards and Regulations 227
2.2 Factors Influencing the Certainty of Protocols 228
2.2.1 Cumulative Characteristics 228
2.2.2 Discrete Characteristics 229
2.2.3 Parallel Characteristics 230
3 Solution to Certainty Safety Communication Protocols 231
3.1 The Topology and the Sample Model 231
3.1.1 The Topology of the Safety Communication Network 231
3.1.2 The Simple Model in the Safety Communication Network 232
3.2 The DLL of the Safety Communication Network 233
3.2.1 The Data Mapping Control Sublayer 233
3.2.2 The MAC Control Sublayer 234
3.2.3 The MAC Data Channel Sublayer 234
3.3 The Certainty Protocol Implemented in the DLL 234
3.3.1 State-Based Communication with Certainty 234
3.3.2 Fixed Transmission Mode 234
3.3.3 Producer-Consumer Model 235
3.3.4 Optimised Types of Frames 235
3.3.5 Fixed and Calculable Transit Data 236
3.3.6 Parallel Data Mapping Management 236
4 Test and Verification 237
5 Conclusion 238
References 238
A Design of FPGA-Based Self-healing System for Communication Networks in Nuclear Safety DCS 240
Abstract 240
1 Introduction 240
2 Analysis of the Fault Mode in the FirmNet 241
2.1 Review of the FirmNet 241
2.2 Analysis of the Fault Mode 243
2.2.1 Single Node Failure 243
2.2.2 Multi-node Failure 243
2.3 Requirement of Self-healing Systems 244
3 Design of a FPGA-Based Self-healing System 245
3.1 Design of the Self-healing System 245
3.1.1 Structure of the Network 245
3.1.2 Working Principle of the Self-healing System 245
3.2 Implementation of the Self-healing System on FPGAs 247
3.2.1 The Advantage of FPGAs 247
3.2.2 The Design of Logic 247
3.2.3 The Data Flow 248
3.2.4 Isolation 248
4 Simulation and Verification 249
4.1 Simulation 249
4.2 Verification 250
5 Conclusion 250
References 251
A Formal Method for Verifying the Ability of a Protocol to Resist Replay Attacks 252
Abstract 252
1 Introduction 252
2 Overview of Verification Methods 253
3 Verification Process 254
3.1 Analysis of Communication Protocol 254
3.2 Building of Communication Model 254
3.3 Building of Attacker Model 255
3.4 Detection with Formal Tools 255
3.5 Verification Conclusion 255
4 Application Practice 255
4.1 Analysis of Communication Protocol 255
4.2 Building of a Communication Model 257
4.3 Building of an Attacker Model 257
4.4 Detection with Formal Tools 257
4.5 Display of Attack Process and Verification Conclusion 257
5 Conclusions 260
Acknowledgement 260
References 260
Design and Analysis of Safety DCS Cabinet for Small Marine Reactor Based on the FirmSys 262
Abstract 262
1 Introduction 262
2 SMR DCS Cabinet Demand Analysis 263
3 Key Design Difficulties of SMR DCS Cabinet 263
3.1 Shock Resistance Design and Input Requirement 263
3.1.1 Shock Resistance Design Requirement 264
3.1.2 Shock Requirement Input Requirement 264
3.2 IP Protection and Heat Dissipation Requirement 264
3.2.1 IP Protection Design Requirement 264
3.2.2 Heat Dissipation Requirement 264
3.2.3 Design Difficulty to Meet Both IP Protection and Heat Dissipation Requirements 265
4 Solutions to Key Design Difficulties of SMR DCS Cabinet 265
4.1 Shock Resistance Design Scheme 265
4.1.1 Shock Resistance System Design 265
4.1.2 Shock Resistance Detail Design 266
4.2 Design Schemes of Heat Dissipation and IP Protection 268
4.2.1 Airway Design 268
4.2.2 IP Protection Design 269
4.2.3 Heat Dissipation Analysis 269
4.2.4 Prototype Verification 270
5 Conclusions 270
Acknowledgement 271
References 271
The Design of Safety Control Display Device of Small Modular Offshore Floating Reactor Protection System Based on FirmSys 272
Abstract 272
1 Introduction 272
2 Application Status of Safety Control Display Device 273
3 Requirement of Safety Control Display Device Analysis 274
4 Safety Control Display Project Design 275
5 Safety Control Display Screen Design 275
5.1 Main Function Design 275
5.2 Man-Machine Interface Design 276
6 Customized Keyboard Design 278
6.1 Design Features 278
6.2 Keys Design 279
7 Design Verification 280
8 Conclusions 280
9 Acknowledgement 280
References 280
Research on Maintenance Network Design Based on Nuclear Power Station Safety DCS System 282
Abstract 282
1 Introduction 282
2 Composition of LAN System and Analysis of 802.3 Protocol 283
3 Design of Real-Time Data Monitoring Method 284
3.1 Network Model Design 284
3.2 Design of Functional Instructions 286
3.3 Format Design of Network Protocol 286
3.4 Design of Communication Security and Reliability 288
3.5 Design of Abnormal Notice 289
3.6 Design of Communication Process 289
4 Realization of Data Monitoring Process 291
4.1 Create Link 291
4.2 Data Monitoring 292
4.3 Data Enforcement 292
4.4 Disconnect the Link 292
5 Test Results and Analysis of Prototype 4 293
6 Closing Remarks 294
References 294
Research and Application of RPN Detector Positioning Technologies in Nuclear Power Plants 295
Abstract 295
1 Introduction 295
2 Positioning Requirements 296
2.1 Radial Arrangement 296
2.2 Axial Arrangement 296
2.3 Measurement Requirements 297
2.4 Operation and Maintenance Requirements 297
2.5 Environmental Conditions 298
2.6 Engineering Implementation 298
3 Technological Status 298
4 Implementation of Advanced “Bucket Type” Technology 300
4.1 Positioning Scheme 301
4.2 Radial Position of Detectors 302
4.3 Axial Position of Detectors 302
4.4 Connection Box and Junction Board 303
4.5 Detector Assembly Connection 304
5 Technological Advantages 304
5.1 Pros and Cons Analysis of Positioning Technologies 304
5.2 Technological Advantages of “Bucket-Type” 305
6 Conclusion 306
References 306
A Safety Level DCS Symbol Execution Test Optimization Method 308
Abstract 308
1 Introduction 308
2 Symbolic Execution Technique 309
3 Nuclear Safety Level DCS Software System 311
4 DCS Software Symbolic Execution Test 312
5 Experiment 315
6 Summary 316
References 316
Application Research of Fault Diagnosis in Conventional Island of Nuclear Power Plant Based on Support Vector Machine 318
Abstract 318
1 Introduction 318
2 Establishment of Dataset 319
3 Establishment of SVM Model 320
3.1 Theory and Mathematical Model 320
3.2 Mathematical Expression 321
3.3 Programming Language Python 321
3.4 SVM Model 322
3.5 Kernel Function Selection 322
3.6 Parameters Tuning and Prediction 323
3.7 Result Analysis 324
4 Summary and Discussion 325
References 325
Software Verification and Validation of Digital Nuclear Instrumentation System 327
Abstract 327
1 Introduction 327
2 The Software Lifecycle Model 328
3 The Tasks of Software V& V in Different Stages
3.1 Verification of RPN Equipment Specification 330
3.2 Verification of Software Requirements Specification and Design Specification 330
3.3 Verification of Software Code 331
3.4 Unit Test 332
3.5 Integration Test 332
3.6 Validation Test 333
4 Summary 333
5 Conclusion 334
References 335
Research on the Human Factors Integration in Some Third Generation NPP 336
Abstract 336
1 Introduction 336
2 Human Factors Integration Strategy Analysis 337
3 HF Organization 338
3.1 HF Team 338
3.2 Human Factors Integration Goal 339
3.3 HF Training 340
4 Human Factors Integration Process 340
4.1 Previously Practice and Regulation Expectation Analysis 340
4.2 Human Factors Integration Process Development 341
5 HFI Activities Practices 342
5.1 Operating Experience Review 343
5.2 HF Guidelines Development and Implementation 343
5.3 HF Review 345
5.4 Important Human Actions Identification and Assessment 345
5.4.1 Important Human Actions Identification 345
5.4.2 Important Human Actions Assessment 346
5.5 HF Verification & Validation
5.6 HF Issues Register Management 347
6 Conclusions 347
References 348
Development and Application of Closed-Loop Control Performance Evaluation System for Nuclear Power Plant 349
Abstract 349
1 Introduction 349
2 Key Technologies of Performance Evaluation for Closed-Loop Control Systems 350
2.1 Classification of Control System Responses of Nuclear Power Units 350
2.2 Evaluation Index and Calculation Method 351
3 Development of Evaluation System System 352
3.1 Functional Architecture of System System 352
3.2 Data Storage 354
3.3 Implementation of System System 354
4 Experimental Result 355
4.1 Performance Evaluation of Pressurizer Pressure Control 355
4.2 Performance Evaluation of Pressurizer Level Control 356
4.3 Contrastive Analysis Unit and Reference Unit 357
5 Conclusion 358
References 358
Research on Typical Fault Diagnosis of Nuclear Power Plant Based on Weighted Logical Inference Arithmetic 359
Abstract 359
1 Introduction 359
1.1 Research Background 359
1.2 Research Contents 360
2 Research and System Development Based on Weighted Logical Inference Arithmetic 361
2.1 Fault Diagnosis Reasoning Logic 361
2.2 Obtaining the Set Value of Expert Database 362
2.3 Fault Diagnosis Interface and Logical Inference Design 365
3 Typical Fault Diagnosis – Excessive Discharge of Steam in the Second Loop 368
4 Conclusions 368
References 369
Information Security Risk Analysis and Countermeasures of Digital Instrumentation Control System in NPP 370
Abstract 370
1 Introduction 370
2 Introduction to the Information Safety of Digital Instrument Control System in NPPs 371
2.1 Information Safety 371
2.2 Digital Instrument Control System in NPPs 372
2.2.1 Level of Information Management of the Whole Plant 373
2.2.2 Control and Monitoring Level 373
2.2.3 Automatic Control and Protection Level 374
2.2.4 Process System Interface Layer 374
2.3 Current Situation of Information Safety of Digital Instrument Control System in NPPs 374
3 Risk Analysis on Information Safety of Digital Instrument Control System in NPPs 375
3.1 Risk Analysis on Information Safety of Digital Instrument Control System in NPPs 375
3.1.1 Risk Analysis on Process System Interface Layer 375
3.1.2 Risk Analysis on the Automatic Control and Protection Level 375
3.1.3 Risk Analysis on Operation and Information Management Level 376
3.1.4 Risk Analysis on the Level of Information Management of the Whole Plant 376
3.2 Risk Analysis on the Information Safety of Digital Instrument Control System in NPPs 377
4 Discussion on Responses to the Information Safety of Digital Instrument Control System in NPPs 377
4.1 Operating Power Plants 377
4.1.1 Management 377
4.1.2 System Software 378
4.1.3 Internet 378
4.1.4 Monitor and Response 378
4.2 New Power Plants 378
5 Conclusion 379
References 379
The Research and Development of Digital General Operating Procedure 381
Abstract 381
1 Foreword 381
2 General Planning of the Digital General Operating Procedure 382
2.1 The Concept of Digitalization 382
2.2 The Feedback of N4 and EPR 382
2.3 General Guidelines for Digitalization of Operating Procedures 383
3 Design Scheme of Each Module’s Structure of the General Operating Procedure 384
3.1 “Procedure Body” and “Digital Operating Sheet” 384
3.2 Supporting Display Design According to the Task-Oriented Principle 385
3.3 Format and Content of Structured Navigation Display 388
3.4 Alarm Monitoring for Unit Start and Shutdown 389
4 The Verification of Digital General Operating Procedures 389
4.1 Simulation Verification 389
4.2 Application Validation During Commission Start-up 390
5 Usage of the Digital General Operating Procedures 390
6 Conclusion 391
References 391
Research on Hybrid Communication System for Nuclear Power Plants Safety-DCS 393
Abstract 393
1 Introduction 393
2 Development of Industrial Wireless Communication Technology 394
3 Design of Hybrid Communication System 395
3.1 Construction of Hybrid Communication in DCS 395
3.2 The Advantage of Hybrid Communication in DCS 396
3.3 Feasibility Research of Hybrid Communication in Safety DCS of NPP 397
3.3.1 Electromagnetic Properties of Wireless Communication Channels 397
3.3.2 Reliability Assurance of Hybrid Communication DCS 398
4 Conclusions 399
References 399
Analysis of Analog Circuit Error in Reactor Control System 401
Abstract 401
1 Introduction 401
2 The Error Model of Op-Amp Circuit 402
2.1 Offset and Temperature Drift of Op-Amp 402
2.2 Open Loop Gain, Input and Output Impedance in Op-Amp 403
2.3 Peripheral Resistance Error and Temperature Drift 404
2.4 Op-Amp Noise and Resistor Noise 404
2.5 Comparison of Error Sources 404
3 Error Combination 405
3.1 A General Model of Inverting Op-Amp Circuit 405
3.2 Calculation Results 407
3.3 PSPICE Simulation 407
4 Analog Circuits in Reactor Control System 408
4.1 Analog Input Circuit 408
4.2 RTD Conditioning Circuit 408
4.3 Fission Chamber Preamplifier 409
4.4 Comparison of Three Circuits 409
5 Conclusions 410
References 410
Reliability Analysis of Safety Class Analog Output Module Based on FFTA in Nuclear Power Plant 412
Abstract 412
1 Introduction 412
2 Fuzzy Fault Tree Analysis (FFTA) Method 412
2.1 Fuzzy Probability 413
2.2 Logic Gate Fuzzy Operator 414
2.3 Fuzzy Significance 414
3 Reliability Analysis of the Analog Output Module 415
3.1 Fuzzy Fault Tree of the Analog Output Module 415
3.2 Quantitative Analysis of Reliability of Analog Output Module 416
3.2.1 Analysis on the Probability of the Module Failure 416
3.2.2 Analysis of the Weak Link 418
4 Conclusion 418
References 419
Research on Instrument Channel Uncertainty of Nuclear Power Plant 420
Abstract 420
1 Introduction 420
2 The Traditional Method of Calculating Uncertainty 421
2.1 Preparation for Calculation 421
2.2 Uncertainty Calculating Method Based on SRSS 422
2.3 Uncertainty Calculating Method Based on GUM 423
3 Uncertainty Calculation Method Based on Monte Carlo 424
4 Comparisons Between MCM and Traditional Methods 425
5 Conclusion 428
References 428
Research and Analysis on 1E Distributed Control System Priority Logic Module 429
Abstract 429
1 Introduction 429
2 Priority Logic Module Analysis of Different Platform 430
2.1 CommonQ 430
2.2 NASPIC 432
2.3 Firmsys 433
2.4 MELTAC 435
2.5 Tricon 436
2.6 TXS 438
2.7 The Reliability of Priority Logic Module 439
3 Summary Analysis 441
4 Conclusions 442
Acknowledgments 442
References 442
Design and Optimization of Communication in Nuclear Safety Class Emulation System 444
Abstract 444
1 Background 444
2 The Communication Framework of Virtual Nuclear Safety DCS Based on TCP Protocol 445
2.1 Brief of TCP 445
2.2 Emulation Framework Design of Safety Communication Protocol Based on TCP 446
3 Design of the Communication 447
3.1 Design of the Communication in I& C Emulation System
3.1.1 Communication Design Between DMS and VCS 448
3.1.2 Communication Design Between DMS and VCS 448
3.1.3 Communications Between VCSs 448
3.2 Communication of Process Model 448
3.3 Communication Between I& C Emulation System and Other Parts of FSS
4 Signal Transmission Optimization in Emulation System 450
4.1 Signal Transmission Difference Between Emulation System and Physical System 450
4.2 Optimization 450
4.3 Analysis of Optimization Case 451
5 Conclusion 453
References 454
Reliability Allocation Based on Importance Measures 455
Abstract 455
1 Introduction 455
2 Why Reliability Allocation Based on Importance Measures Is Needed? 456
2.1 A Simple Example 456
2.2 One Fact 457
2.3 An Idea 457
3 The Model of Reliability Allocation Based on Importance Measures 458
3.1 The General Model 458
3.2 The Forms of f(·) 459
4 Relation with Conventional Models of Reliability Allocation 460
4.1 Traditional Models of Reliability Allocation 460
4.2 Cost-Related Importance Measure 460
4.3 Relationship of the Two Reliability Allocation Methods 461
5 Case Study 463
6 Conclusion 467
References 467
Discussion on Traceability Analysis Method of Safety Software in Nuclear Power Plants 469
Abstract 469
1 Introduction 469
2 Software Verification and Validation 470
3 Requirement Items 471
4 Traceability Analysis Method 473
5 Summary 475
References 476
The Application of LSTM Model to the Prediction of Abnormal Condition in Nuclear Power Plants 477
Abstract 477
1 Introduction 477
2 Prediction Methods: Past and Present 478
2.1 A Traditional Statistical Attempt: Kalman Filter 478
2.2 Traditional RNN Attempts: Struggling Against the Timeline 478
2.3 The LSTM Model: Keeping Critical Info for Prediction 479
2.3.1 LSTM Model 479
2.3.2 Rolling Update Mechanism 480
2.3.3 Data Normalization 481
2.3.4 Dropout Method 482
2.3.5 MSE 483
3 Experiment Preparation: Data, Parameters, and Training 483
3.1 Data Normalization 483
3.1.1 Steam Generator Pressure Adjustment 483
3.1.2 Small LOCA 484
3.2 Model Configuration 485
3.3 Model Training 486
4 Results and Analysis 486
4.1 Comparison Between RNN and LSTM 486
4.2 Prediction of Small LOCA Accident 488
5 Conclusion 489
References 489
Development and Application of Undisturbed Online Downloads in the FirmSys 491
Abstract 491
1 Introduction 491
2 Requirement Analysis of the Online Downloading 492
2.1 Configuration Modification Supported by Online Download 492
2.2 Control Station Function Requirements During Online Download Process 494
2.3 Online Downloading Tool Requirements 494
2.4 Performance Specifications 495
2.5 Safety Requirement 496
3 Schematic Design 496
3.1 The Online Downloading in General Industrial Control System 496
3.2 Overall Design of the Downloading 497
3.3 Implementation of Each Step 498
3.3.1 S1: Download VC 498
3.3.2 S2: Switch B to RUN 499
3.3.3 S3: Synchronize with the Counter-Partner 499
3.3.4 S4: Operate as Slave 500
3.3.5 SWAB: Switch Master-Slave 501
3.4 Tool-Related Design 501
3.4.1 Compiling 501
3.4.2 Download 502
3.4.3 Version Comparison 503
3.5 Design Standard Compliance Analysis 503
4 Implementation and Application 503
5 Conclusion 504
References 504
The Study on Automatic Control of Pressure and Temperature for the Pressure Water Reactor Nuclear Power Plant 506
Abstract 506
1 Introduction 506
2 Algorithm Analysis and Development of Temperature Control Module 507
3 Logic Design and Implementation of Automatic Temperature Control 508
3.1 Logic Design of Temperature Control of Steam Generator 508
3.2 Logic Design of Normal Residual Heat Removal of Temperature Control 509
3.3 Logic Design of Pressure Control 509
4 Verification of Results and Analysis 510
4.1 Verification of Temperature and Pressure Reduction in Normal Intermediate Shutdown 510
4.2 Verification of Cooling Control After RHR Shutdown 512
4.3 Analyses of Results 512
5 Conclusion 514
References 514
A Hierarchical Task Analysis Approach for Static Human Factors Engineering Verification and Validation of Human-System Interface 516
Abstract 516
1 Introduction 517
1.1 A Subsection Sample 517
2 Concept of V& V
3 A Hierarchical Approach for Task Analysis 520
4 Case Study 524
5 Conclusions 528
References 528
Research on Static Testing Technology of Nuclear Safety-Critical Software Based on FPGA Technology 530
Abstract 530
1 Introduction 530
2 Nuclear Safety-Critical FPGA Software Programming Rules Requirements 531
3 Research on Static Test Framework of Nuclear Security Level FPGA Software 533
3.1 Applicability and Limitations of Test Tools 533
4 Static Test Framework 534
4.1 Static Test Basic Process 535
5 Practice 536
6 Conclusion 536
References 537
Features Extraction Based on Deep Analysis of Network Packets in Industrial Control Systems 538
Abstract 538
1 Introduction 538
2 Related Work 539
3 Analysis of Network Packets 539
3.1 Packets Capture 539
3.2 Structure of Network Packets 540
4 IT Network Feature Extraction 540
5 Industrial Control Feature Extraction 541
5.1 Conversation Correspondence 541
5.2 Feature Extraction 541
6 Application in Neural Network Approach 542
7 Conclusion 542
Acknowledgments 542
References 542
An Optimum Solutions for Venturi Used for Main Feedwater Flowrate Measurement in Nuclear Power Plant 544
Abstract 544
1 Introduction 544
1.1 Working Principle and Structure of Venturi Tube 544
2 Structures and Problems Found in the Venturi Tube 545
3 Causes of Problems and Analysis of Structural Defects 546
4 Optimum Design Scheme 550
5 The Advantages and Disadvantages of the Optimization Program 552
6 Venturi Optimization Program Performance 553
7 Conclusion 553
References 553
Research and Application of Software Reliability Analysis Method for Safety I& C System in NPPs
Abstract 555
1 Introduction 555
2 Software FMEA and FTA Comprehensive Analysis 556
2.1 The Advantages and Disadvantages of the Analysis Methods 556
2.2 The Principle of the Comprehensive Analysis 557
3 Modeling and Application 558
3.1 System Function and Structure 558
3.2 Basic Conditions and Constraints 559
3.3 FMEA and FTA Comprehensive Analysis 559
3.4 Solve the Minimum Cut Set 560
3.5 Develop Control or Improvement Measures 562
4 Conclusions 563
References 563
Development of Closed-Circuit Television Inspection System for Steam Generators in Nuclear Power Plants 564
Abstract 564
1 Introduction 564
2 Inspection Scope and Inspection Requirement 565
3 Mechanical System 566
4 Drive Control System 567
5 Software System 568
6 Conclusion 569
References 569
Research on the Security Technology of the Internet of Things in Nuclear Power Plant 570
Abstract 570
1 Introduction 570
2 Internet of Things Threats at Nuclear Power Plant 571
3 The Security Analysis of Nuclear Power Plant Internet of Things 572
4 The Security Measures of Nuclear Power Plant Internet of Things 573
5 Conclusions 575
References 575
A Study About Safety Technology of Control System and Information System in Nuclear Power Plant 577
Abstract 577
1 Introduction 577
2 Research on the NPP Control System and Information System Security Technology 578
3 Conclusion 580
References 580
Author Index 582

Produkt-Details

• Erscheint lt. Verlag: 7.1.2020
• Reihe/Serie: Lecture Notes in Electrical Engineering
• Reihe/Serie: Lecture Notes in Electrical Engineering
• Zusatzinfo: XIII, 571 p. 306 illus., 154 illus. in color.
• Sprache: englisch
• Themenwelt: Informatik ► Netzwerke ► Sicherheit / Firewall
• Themenwelt: Naturwissenschaften ► Biologie ► Ökologie / Naturschutz
• Themenwelt: Naturwissenschaften ► Physik / Astronomie ► Angewandte Physik
• Themenwelt: Technik ► Bauwesen
• Themenwelt: Technik ► Elektrotechnik / Energietechnik
• Themenwelt: Technik ► Maschinenbau
• Themenwelt: Wirtschaft ► Betriebswirtschaft / Management
• Schlagworte: Advanced Process Control • Automation, Instrument and Control • Digital I&C System • Digital transformation • Instrument and Control • Nuclear power plant • Process Safe Management • Quality Control, Reliability, Safety and Risk
• ISBN-10: 981-15-1876-9 / 9811518769
• ISBN-13: 978-981-15-1876-8 / 9789811518768