Nuclear power plants : innovative technologies for instrumentation and control systems : the fifth International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant (ISNPP)

Contents Research on Converged Wireless Communication Network Scheme in Nuclear Power Plants 1 Introduction 2 Converged WCN Scheme for Case 1 3 Converged WCN Scheme for Case 2 4 Converged WCN Scheme for Case 3 5 Conclusion References Research About Computer Based System Reliability Demonstration Methods in Nuclear Power Plant 1 Background 2 Life Cycle of I&C System in Nuclear Power Plant 3 Hardware and Software Reliability Guarantee Methods 3.1 Hardware Reliability Guarantee 3.2 Software Reliability Guarantee 4 Computer Based System Reliability Demonstration Test 4.1 Testing Methods Discussion 4.2 Statistical Testing in Nuclear Power Plant 4.3 Test Cases 4.4 Test Method Deviation 5 Conclusion References Multi-ray Intelligent Monitoring System for Mixed Radiation Field Measurements 1 Introduction 2 Measurement System Design 2.1 γ-ray Measurement Unit 2.2 Neutron Measuring Unit 2.3 α Aerosol Measurement Unit 2.4 Tritium Monitoring Unit 2.5 Radon Concentration Monitoring Unit 2.6 The Integrated Monitoring System 3 Experiments and Discussion 3.1 γ-ray Measurement Unit Test 3.2 Neutron Measurement Unit Test 3.3 α Aerosol Measurement Unit Test 3.4 Tritium Monitoring Unit Test 3.5 Radon Concentration Monitoring Unit Test 4 Conclusion References Basic Model Design of Online Monitoring System for Mixed Radiation Field 1 Preface 2 Establishment of the Basic Model of On-Line Radiation Monitoring System 2.1 Functional Requirements 2.2 Index System 2.3 Establishment Principles 2.4 Instrument Selection and Development Principle 3 Key Technologies and Solutions 3.1 Various Types of Data Acquisition and Processing Technology 3.2 Multi-system Integrated Technology 4 Experimental Verification Design 4.1 Radiation Performance Test 4.2 Environmental Experiment 4.3 Reliability Experiment 4.4 Maintainability Experiment 5 Application Demonstration Design 5.1 Representative Application of Demonstration 5.2 Evaluability of Demonstration Application 6 Conclusion Duty Ratio Restriction Strategies of Space Vector PWM for Power Amplifiers of AMBs 1 Introduction 2 Power Amplifier for AMBs 3 The Principle of SVPWM of Three-Phase Bridge Circuit 4 Two Duty Ratio Restriction Strategies 4.1 Proportional Reduction Strategy 4.2 Period Bisection Strategy 4.3 Comparison of Two Duty Ratio Restrictions 5 Digital Implementation of Power Amplifier Control Algorithm 6 Experiments of Two Duty Ratio Restriction Strategies 6.1 Normal Tracking Experiment 6.2 Compare of Two Duty Ratio Restriction Strategies When Command Signals Exceed the Tracking Range 7 Conclusions References Research and Application of 3D Real-Time Simulation Technology for Thermal and Hydraulic Mechanism in Nuclear Power Plant 1 Introduction 2 Virtual Reality Technology and Application 3 System Implementation 3.1 Design Idea 3.2 Technical Framework 3.3 Thermal Hydraulic Modeling 3.4 Real-Time Analog Data Processing 3.5 Data Driven Model 3.6 Dynamic Visualization Interaction 4 Application Status 5 Conclusion References Research on Software Quality Evaluation Model of Instrument and Control System in Nuclear Power Plant 1 Introduction 2 Software Quality Evaluation Index 3 Software Quality Evaluation Model Based on Analytic Hierarchy Process 3.1 Establishing Hierarchical Model 3.2 Constructing Judgment Matrix 3.3 Computing Weight Vector 3.4 Checking consistency 3.5 Computing Comprehensive Score 4 Concluding remarks References The Security Based on Wireless Network in Nuclear Power Plant 1 Application Background of Wireless Network in Nuclear Power Plant 2 The Security Risks of Wireless Network in Nuclear Power Plants 3 Analyses of Wireless Network Security Regulations and Standards 4 Nuclear Power Plant Wireless Network Security Protection Strategy 4.1 Application Range of Wireless Network 4.2 Wireless Network Security Protection Measures 5 Summaries References Information Fusion Analysis of Cyberattack Identification Based on D-S Evidence Theory 1 Introduction 2 Theoretical Foundations 2.1 Basic Concepts 2.2 Dempster's Rule of Combination 2.3 Triangular Fuzzy Number 2.4 BPA Generation Method Based on Triangular Fuzzy Number 3 Testbed and Cyberattack Types Description 4 Experimental Results and Analysis 4.1 Training and Test Data Generation 4.2 Triangular Fuzzy Number Model Construction 4.3 Test Samples Matching and BPA Generation 4.4 BPA Fusion Using Dempster’s Rule of Combination 5 Conclusions References Power Control System of Small Modular PB-Bi Fast Reactor (SMPBR) 1 Introduction 2 Model and Methods 2.1 Point Reactor Kinetis Equations 2.2 Thermal Dynamic Model 2.3 Hot and Cold Pool 2.4 Reactivity 3 Results and Discussion 3.1 Adjust Power by the Coolant Flow Rate 3.2 Influence of Core Inlet Temperature on the Primary Circuit 4 Conclusion References Research on Integrated Management Technology for Physical Protection System of Nuclear Facilities 1 Physical Protection System 1.1 Definition of Physical Protection System 1.2 Composition of Physical Protection System 1.3 Function Realization of Physical Protection System 2 Integrated Management System 2.1 Development Status of Integrated Management System 2.2 Development Trend of Integrated Management System 3 Construction Scheme of Integrated Management System 3.1 Functional Requirements of Integrated Management System 3.2 Composition of Integrated Management System 3.3 Software Architecture of Integrated Management System 4 Summary References Calculation and Selection of Cross-Sectional Area of Instrumentation and Control Cable Core 1 Introduction 2 Principle Analysis 3 Calculation of Maximum Laying Length of Cable 3.1 Digital Input Signal 3.2 Digital Output Signal 3.3 Analog Input Signal 3.4 Analog Output Signal 3.5 Temperature Measuring Loop System 4 Conclusion References The Formulation of BOP Auxiliary System Centralized Control Network in Nuclear Power Plant 1 Introduction 1.1 A Subsection Sample 2 BOP Auxiliary System Control Network Analysis 2.1 Status of Auxiliary System Control 2.2 Solution of BOP Auxiliary Control Network 3 Network Architecture and System Composition 4 Analysis on the Implementation of BOP Auxiliary Control Network 4.1 Impact Analysis of New Construction Progress 4.2 Impact Analysis of New Works Design 4.3 Impact Analysis of New Construction Procurement 4.4 Impact of Transformation on In-Service Power Plant Operation 5 Conclusion References An AHP-Fuzzy Complex Evaluation Method for MCR Human Factors Engineering Verification and Validation 1 Introduction 2 Human Factors V&V Overview 3 AHP-Fuzzy Complex Evaluation Model 3.1 Establishment of Evaluation Index System 3.2 Multilevel Fuzzy Complex Evaluation Model 4 Case Study 4.1 Weight Determination Based on AHP 4.2 Complex Evaluation 5 Conclusion References Research on Control Strategy of Nuclear Island Ventilation Systems in Nuclear Power Plant 1 Introduction 2 Analyses of Industry Development and Challenges 2.1 Safety Classification Requirements Changes and Challenges 2.2 Automatic and Control Level Requirement Change and Challenge 3 Control Strategy and Development Ideas of Nuclear Island Ventilation Systems 3.1 Control Strategy Face to the Challenge of Safety Classification 3.2 Ideas for Improving the Automation Level 4 Implementation Results 5 Conclusion References The Safety Function Design Improvement of Circulation Water Filter System in CPR1000 Unit 1 Introduction 1.1 The Flow Diagram of CFI System in CPR1000 1.2 The Main Equipment of CFI System in CPR1000 1.3 The Operation Process of CFI System in CPR1000 1.4 The Function Analysis of CFI System in CPR1000 1.5 The Safety Classification of CFI in CPR1000 2 The CFI Safety Function Design Defect in CPR1000 2.1 Design Concept Defect 2.2 Function Classification Defect 2.3 Logic Function Design Defect 2.4 Logic Design Defect 3 The Design Improvement of CFI in the Third Generation Unit 3.1 The Design Concept Improvement 3.2 Function Classification Improvement 3.3 Manual Logic Design Improvement 4 Results 5 Conclusion References A Study About Unit Testing for Embedded Software of Control System in Nuclear Power Plant 1 Introduction 2 Related Works 2.1 Embedded Software Testing Features 2.2 Unit Test of Embedded Software 3 Embedded Software Unit Test Method Based on Program Piling 3.1 Software Structure Analysis 3.2 Program Piling 3.3 Syntax Modification 3.4 Hardware Simulation 4 Engineering Practice 4.1 Software Analysis 4.2 Software Separation 4.3 Unit Test 5 Conclusions References Design of Defence in Depth for I&C System in Pressurized Water Reactor Nuclear Power Plant 1 Introduction 2 Requirements of IAEA 2.1 Requirements of IAEA SSR2/1 2.2 Requirements of IAEA TECDOC 1791 [2] 2.3 Requirements of IAEA SSG-39 [3] 2.4 Summary 3 Design of DiD for I&C System 3.1 DiD of I&C System 3.2 Compliance Analysis with Requirements of IAEA 3.3 Independence Analysis 3.4 Diversity Analysis 4 Conclusion References Test Analysis About Hydrogen Detection Equipment Under Severe Accident in Nuclear Power Plant 1 Introduction 2 Hydrogen Detection Requirement Analysis 2.1 Requirements on System Level 2.2 Requirements on Equipment Level 3 Design of the Testing System 3.1 Testing Requirement Analysis 3.2 Testing Requirement Under Normal Ambient Condition 3.3 Qualification Tests for Nuclear Power Plant 3.4 Testing System Design 3.5 Testing Environment 4 Testing System Application 5 Summary References Research of Advanced Control Algorithm in Primary Loop Control System 1 Introduction 2 Primary Loop System Model 2.1 Core Power Model 2.2 Pressure and Water Level Model of Regulator 2.3 Water Level Model of Steam Generator 3 Advanced Predictive Control 3.1 Stepped DMC 3.2 Multi-model Predictive Control 4 Simulation Verification 4.1 Linkage Relationship Between Primary Loop Control Systems 4.2 Overall Simulation of Primary Circuit 5 Conclusions References Research of SSAE-GPC in Coordinated Control System of Nuclear Power Plant 1 Introduction 2 SSAE-SGPC 2.1 Sparse Stacking Automatic Encoder (SSAE) 2.2 SSAE-SGPC 3 Coordination System Control Based on SSAE-GPC 3.1 Coordinated System Model of Nuclear Power Plant 3.2 SSAE-GPC Model Prediction 4 Simulation Verification 4.1 Setpoint Disturbance Simulation 4.2 Internal Disturbance Simulation 4.3 External Disturbance Simulation 5 Conclusion References Reliability Verification Scheme for Safety Class DCS and Its Implementation in Nuclear Power Plant 1 Introduction 2 Reliability of Safety Class DCS 3 Reliability Index Verification Scheme of Safety Class DCS 3.1 Refusal Probability Verification Scheme of Safety Class DCS 3.2 Malfunction Rate Verification Scheme of Safety Class DCS 3.3 Availability Verification Scheme of Safety Class DCS 4 Implementation of Reliability Verification Scheme of Safety Class DCS 5 Conclusion References An Ergonomic Analysis of Main Control Room Console in Nuclear Power Plant Based on Jack 1 Introduction 2 Human Body Simulation Software 2.1 Comparison of Human Body Modeling Simulation Software 2.2 Jack Simulation Software 3 The Foundation of Ergonomic Analysis 3.1 Digital Human 3.2 Environment Building 4 Ergonomic Analysis 4.1 Accessibility 4.2 Visibility 4.3 Collision Dictation 5 Practical Application 6 Conclusion References Verification Method and Basic Guarantee of RPS Availability in Nuclear Power Plant 1 Introduction 2 Concept of Availability and Necessity of Verification 2.1 The Concept of Availability 2.2 The Necessity of Availability Verification 3 Verification Method for the Availability of Digital Instrument and Control System in Nuclear Power Plant 3.1 Traditional Availability Verification Methods 3.2 Recommended In-Plant Availability Test Verification Method 4 Basic Guarantee of Test 4.1 Test Preparation and Prerequisites 4.2 Test Guarantee Condition 4.3 Test Control and Management 5 Conclusion References Design Method of Human-Computer Interactive Interface of MTS Based on DCS of Nuclear Power Plant 1 Introduction 2 Requirement Analysis of MTS Human-Computer Interaction 2.1 Human-Computer Interaction Model of MTS 2.2 Requirements Analysis of MTS 3 Overall Scheme of Software Human-Computer Interaction System of MTS 3.1 Interaction Design Scheme 3.2 Visual Design Scheme 4 Example of Human-Computer Interface Design of MTS 4.1 Software Development Environment 4.2 Structure and Layout 5 Significance and Impact Analysis 6 Concluding Remarks References Formally Verified a Front-End of the Trusted Code Generator for Safety I&C Software of NPPs 1 Introduction 2 The Graphical Algorithms Model Described Language Lustre 3 The Architecture of the NASCG 4 The Core Transformations in Front-End of NASCG 4.1 Type Check Pass 4.2 Simplification Pass 4.3 Scheduling Pass 5 Operational Semantics and Proof of Correctness 6 Conclusions and Future Work References Design of Emulation System for Safety DCS 1 Background 2 Virtualization 3 Virtual DCS Design 3.1 System Structure Design 3.2 Virtual DPU Development 4 Simulation Functions 4.1 Simulation States Switching Function 4.2 Data Management Function 4.3 Virtual Hardware Function 4.4 Malfunction Simulation Function 4.5 Function Design of VDPU 5 Closed-Loop Simulation Verification 6 Conclusion References Trusted Algorithm Compiler for Safety I&C Software of NPPs Based on Formal Methods 1 Introduction 2 Related Background 3 Trusted Compilation by Formal Methods 3.1 Two Formal Methods 3.2 Trusted Algorithm Compiler Architecture - Composite Compilation for NASPIC 3.3 Proof of the Semantic Consistency of the Compiler 3.4 Compiled to Ensure the Optimization of the Compiler by Translation Validation 3.5 Trusted Compilation Optimization Research 4 Examples and Applications 5 Conclusion References Design and Implementation of Translation-Based Virtual DCS Based on Simulink 1 Introduction 2 System Design 2.1 Process System Model 2.2 Configuration Translation 2.3 Periodic Control and Fast and Slow Speed Functions 2.4 Implementation of Variable Value Setting and Acquiring 2.5 Snapping and Loading Working Conditions Function 2.6 Analysis on the Pressurizer Level Control System 3 Case Analysis 4 Conclusion References Testing Verification of Pressurizer Control in Nuclear Power Plant Based on Comparative Simulation 1 Introduction 2 Testing Verification System Design 2.1 Construction of the Testing Verification Structure 2.2 Testing Software Design 3 Process System Model 4 Experiment Verification 4.1 Closed-Loop Imitation System Design 4.2 Analysis on the Pressurizer Level Control System 4.3 Analysis on the Simulation Results 4.4 Algorithm Logic Check Example Analysis 5 Conclusion References Optical Fiber Communication and Wireless Communication Technology Oriented to Internet of Things 1 Introduction 2 The Basic Structure of the Internet of Things 3 The Scheme of Things and ITS Application in Electric Power Communication System 3.1 Cable EPON+ Wireless Communication Solution 3.2 Optical Fiber and WiFi Wireless Networking Solutions 3.3 The Construction of Network Load to Determine the Way 3.4 The Realization of Intelligent Communication Computer Room Management and Spare Parts Management System 4 Application of the Perception Layer of the Optical Communication Technology in the Internet of Things 4.1 Application of Optical Fiber Sensing Technology in the Perception Layer 4.2 Application of Wireless Optical Communication Technology in the Perception Layer 5 Optical Communication Technology Application in the Network Layer in the Network 5.1 Optical Fiber Communication Technology Application in the Network Layer in the Network 5.2 Wireless Communication Technology Application in the Network Layer in the Network 6 The Wireless Terminal of the Internet of Things 7 Conclusion References Research on Reliability Design of PROFIBUS Fieldbus System in Conventional Island of Nuclear Power Plant 1 Introduction 2 Typical Fault Analysis 3 Discussion on Systematic Solutions 3.1 Redundancy Design of Bus Control System 3.2 Bus Control System and Conventional Control Diversity Means 3.3 Design of Fieldbus Network Segment Based on Function Allocation Principle 3.4 Network Segment Design Based on PROFIBUS Fieldbus Technology 3.5 Selection of Bus Type Intelligent Equipment 3.6 Layout of Bus Intelligent Equipment 4 Potential Problems and Analysis References Research and Practice of Design Process (Knowledge) Reuse in the Data State Environment of Nuclear Power Design Company 1 Introduction 2 New Challenges of the Digital Design and Production Environment 2.1 Analysis of Digital Production Environment for Nuclear Power Design 2.2 Business Challenges Brought by Space Evolution of Archives Objects 2.3 Challenges of Nuclear Power Plant Design Process (Knowledge) Reuse 3 Practice of Preservation Strategy Under Tri-State Archives Situation Awareness 3.1 Construction of Design Results Database Aiming at Design Reuse 3.2 Exploration of Design (Knowledge) Reuse Based on WBS of Nuclear Power Design Criteria 3.3 Design Business Process and Implementation of Knowledge Modeling Technology 3.4 Conclusion References Study on the Feedwater Control of the Once-Through Steam Generator in the Sodium-Cooled Fast Reactor (SFR) 1 Introduction 2 Materials and Methods 2.1 OTSG Model Description 2.2 Parallel Channel Model Description 2.3 Feedwater Pump Model Description 2.4 Feedwater Regulating Valve Model Description 2.5 Control System Establishment 3 Results and Discussion 4 Conclusion References Design and Improvement for γ Dose-Rate Monitor System of Nuclear Power Plant 1 Component Structure and Function 1.1 Ionization Chamber 1.2 Electrode 1.3 Cable 1.4 Electrometer 2 Failure of LOCA Environmental Test 3 Fault Analysis 3.1 Preliminary Analysis 3.2 Location Analysis of Leakage Point 3.3 Cause Analysis of Leakage 4 Improvements 4.1 Improvement of Processing Technology 4.2 Improvement of Detection Method 4.3 Personnel Improvement 5 Conclusion References Discussion on the Software V&V Technology in Nuclear Power Plants 1 Introduction 2 Standard Requirements 3 Technical Discussions 3.1 Pre-developed Software Identification 3.2 New Software V&V 3.3 Calculation Software Used for Safety Analysis 4 Development Trend of Software V&V 5 Summary References Research and Application of RPN Key Technologies in Nuclear Power Plants 1 Introduction 2 Key Technologies Problem 2.1 Technical Status 2.2 Urgent Problem 2.3 Technical Difficulty 3 Solution 3.1 Monitoring After Accident 3.2 Installation Technology of Detector Components 3.3 Signal Anomaly 3.4 Technical Solution 4 Solution Application 5 Conclusions and Prospects References Design of Intelligent Test System for RPI in Nuclear Power Plant 1 Introduction 2 Test System Principle 2.1 Introduction of Rod Position Detector and Its Performance Test 2.2 Test Function Requirement Analysis 3 Test System Design 3.1 Hardware Design 3.2 Software Design 4 Conclusions References Documentation Verification Based on Natural Language Processing for Safety-Critical Digital I&C System in NPP 1 Introduction 2 Key Characteristics of Safety-Critical I&C Software 3 Verification of Structural Integrity 3.1 Calculation of Word Semantic Similarity 3.2 Documentation Structural Integrity Calculation Algorithm 3.3 Scoring Mechanism 4 Example of Documentation Verification 5 Conclusions References Software Quality Evaluation of Non-safety Digital I&C System in NPPs 1 Introduction 2 Standard System 3 Quality Evaluation Model 4 Evaluation Key Points 4.1 Design Phase 4.2 Equipment Manufacturing Phase 4.3 Commissioning Phase 5 Conclusions References Preliminary Study on Improving the Automation Level of Large Commercial Pressurized Water Reactor 1 Introduction 2 Current Status 3 Framework on Improving the Automation Level 4 Discussion and Conclusion References Research and Application of FPGA V&V Technology in NPP Safety I&C System 1 Introduction 2 Standard Research 3 FPGA V&V Scheme 3.1 Research Route 3.2 Scheme Model 3.3 V&V Activities and Tasks 3.4 V&V Techniques and Methods 3.5 Application Effect 4 Conclusions References Research of Software V&V Technology in the Non-safety DCS of NPPs 1 Introduction 2 Requirements of Standards or Reports 3 Operating Experience 4 Software V&V Scheme 4.1 V&V Model 4.2 V&V Activities and Tasks 5 Conclusions References Structural Design and Dynamic Analysis of Nuclear Safety DCS Cabinet with Light-Weight and Impact Resistance 1 Introduction 2 Frame Design of Cabinet 2.1 Structural Design Schemes of the Cabinet 2.2 Result of Cabinet Frame Structure 3 Finite Element Simulation Analysis 3.1 Establishment of Finite Element Model 3.2 Computational Conditions for Impact Design 3.3 Design Shock Spectrum Calculation 3.4 DDAM Impact Response Analysis 4 Conclusion References Research and Application of the Verification and Validation Method Based on Embedded Technology in Nuclear Power Plants 1 Introduction 2 Research on Standards 3 V&V Scheme 4 V&V Strategy 5 V&V Activities and Tasks 6 V&V Technology and Method 7 Application Effect 8 Conclusion References Research and Application of Time-PSF Calculation Method for HRA in Nuclear Power Plant 1 Introduction 2 Research of Time-PSF Calculation Method for HRA 2.1 General Introduction of the Method 2.2 Key Steps of the Method 3 Examples of Application of the Method 3.1 Quantitative Process Based on SOP 3.2 Quantitative Process Based on SEOP 4 Conclusions References Reliability Assessment Research and Application for PCBA Solderless Press-In Connection Technique in DCS Safety Class Devices in Nuclear Power Plants 1 Background Introduction 2 Demand Analysis 3 Application Scheme Design 4 Verification Results of PCBA Weldless and Pressed-In Connection 5 Verification Conclusion on PCBA Solderless Press-in Connections References Research on the Application of Human Factors Engineering in the Physical Protection System of Nuclear Facilities 1 Introduction 2 Analysis of Human Factors Engineering in the Physical Protection System of Nuclear Facilities 3 Optimization Design of Human Factors Engineering in the Physical Protection System of Nuclear Facilities 3.1 Environmental Design 3.2 Layout Design of Security Building Work Area 3.3 Optimization of Equipment Maintenance Space 3.4 Physical Protection System Alarm Management 4 Application 5 Conclusions References The Design and Implementation of an LSTM-Based Steam Generator Level Prediction Model 1 Introduction 2 Implementation of the Prediction Function 2.1 The MATLAB Implementation of the Prediction Unit 2.2 Training of the Prediction Unit. 3 Implementation of the Validation Platform 3.1 Traditional Control Unit 3.2 Observation Unit 3.3 Integration of the Validation Platform 4 Experiments and Results Analysis 4.1 Experiment Setup 4.2 Experiment Results and Analysis 5 Conclusion References Research on Defense-In-Depth Standards for Information Security in NPP I&C System 1 Introduction 2 Introduction to Information Security Standards and Standards in Foreign Nuclear Power 2.1 American Standards System 2.2 Other International Standards 3 Current Situation of Information Security Regulations and Standards in Chinese NPP I&C System 3.1 Chinese Nuclear Power Regulations and Standards System 3.2 Information Security Regulations and Standards in Nuclear Power Field 4 Defense-in-depth System in Nuclear Power Plant’s Information Security Regulations and Standards 4.1 Regulatory Guide 5.71 4.2 IEC 62645 Standard 5 Graded Protection Standards for Domestic Computer Information Systems 6 Summary References The Analysis for Method of I&C Equipment Period Demonstrating in NPP Refueling Cycle Extension Project 1 Introduction 2 Regulatory Standards Requirements 2.1 Regulation Standards for the Frequency of Supervision 2.2 Requirements for Periodic Test Intervals for Regulatory Standards 3 Equipment Cycle Demonstration Method 3.1 Power Plant Experience Feedback Method 3.2 Supplier Feedback Method 3.3 TCM Analysis Method 3.4 Characteristics of Equipment Cycle Demonstration Method 4 Summary References Spurious Actuation of I&C Systems Analysis Methodology in Nuclear Power Plant 1 Introduction 2 Identification of Spurious Actuation 2.1 Failure Scope and Types 2.2 Approach Assumption 2.3 Identification Process 3 Consequence Analysis of Typical Spurious Actuation Event 4 Summary and Discussion References Analysis for Periodic Test Interval of Digital I&C System for NPP Based on PSA Technology 1 Introduction 2 Overview of PSA Technology 3 Digital Control System 4 Self-diagnosis of Safety I&C System and Periodic Test 4.1 Self-diagnosis Design 4.2 Periodic Test Design 4.3 Periodic Test Cycle Analysis and Calculation 5 Calculation Process of Periodic Test Interval of Safety I&C System 6 Conclusion References Research and Application of Nuclear Instrumentation System EMI Design in Nuclear Power Plant 1 Introduction 1.1 Background 1.2 Problem Analysis 2 Analysis of Equipment and Layout Characteristics of RPN System 2.1 RPN System Equipment 2.2 Analysis of RPN System Layout Characteristics 3 Analysis of Identification Standards for RPN Detectors 3.1 Electromagnetic Compatibility Standards Commonly Used in Nuclear Power Plants 3.2 RPN Detector Evaluation Requirements 3.3 RPN Cabinet Qualification Test 4 Conclusions References Research on the Design Improvement of Important Function Interface for Tripping and Load Rejection in Nuclear Power Plant 1 Introduction 1.1 PLC Controller Configuration 1.2 Logic Function Design 1.3 Redundant Fault Tolerance Mechanism 2 Problems Existing in Digital Transformation of DCS 3 Composition of Digital Transformation 3.1 DCS Controller Configuration 3.2 Default Value Implementation 3.3 Logic Optimization of Turbine Trip and Rejection Signals (GST System) 4 Results 5 Conclusion References Closed-Loop Management Optimization of Technical Change in PWR Nuclear Power Plant 1 Introduction 2 Existing Problems of Change Management 3 General Introduction of Optimization Scheme 3.1 Overall Technical Scheme 3.2 Detailed Technical Scheme 4 Implementation Effect 5 Conclusion Reference Research on the Application of STPA Method in Reliability Analysis of Safety Spray Control in NPP 1 General 2 The Characteristics of STPA Method 3 The Reliability Analysis of the Safe Spray Control 3.1 The Engineering Problem of Spray Control 3.2 Reliability Modeling Based on STPA Method 3.3 Improvement Suggestions Based on STPA Result 4 Conclusions References Study for Reliability Analysis of Operator Response Process Under IBLOCA Accident in Nuclear Power Plant 1 Introduction 2 Analysis of IBLOCA Accident Scenario 3 Overview of Operator Response Process 3.1 Required Operator Actions 3.2 Overview of Operator Response Process in Main Control Room (MCR) 4 Analysis of Potential Errors in Operator Response Process 4.1 Task Analysis 4.2 Potential Error Identification 5 Human Reliability Assessment 5.1 Fault Tree Structure of Operator Response Process 5.2 Recovery Opportunities 5.3 Dependency Analysis 5.4 Human Error Probability of Operator Response Process 6 Conclusions References Failure Analysis and Optimization of Turbine Speed-Up Control for Nuclear Power Plant 1 Introduction 2 Original Scheme 3 Failure Analysis 4 Optimization Scheme 5 Conclusions References Research on Application of Humidity Instrument in Nuclear Power Plant Ventilation System 1 Introduction 2 Analysis of Humidity Measurement Scheme 2.1 Common Methods of Humidity Measurement 2.2 A New Optical Fiber Humidity Measurement Method 3 Application Requirements of Humidity Instrument in Ventilation System of Nuclear Power Plant 4 Application Analysis of Humidity Instrument in Ventilation System of Nuclear Power Plant 5 Conclusion References Current Situation Analysis and Research of Computer-Based Procedure System for Nuclear Power Plant 1 Introduction 2 Regulations and Standards Requirement 2.1 Regulations and Standards 2.2 CBP System Type 3 Current Situation Analysis of CBP System 3.1 CBP System of CPR1000 3.2 CBP System of EPR 3.3 CBP System of AP1000 3.4 Comparative Analysis 4 Analysis and Proposal for CBP System Improvement References Study on the Design of HSI Color System in Nuclear Power Plant 1 Introduction 2 Color Application Requirements in Human-System Interface Design 2.1 Color Consistency 2.2 Color Coding Requirements in Different Situations 2.3 Selection of Color Coding 2.4 Requirements for Color Contrast and Display Color Difference 2.5 Types and Recommended Usage of Color Coding 2.6 Redundancy of Color Coding 3 Comparison of Color Schemes for In-Service Power Plants 3.1 Color Schemes in Several Typical Cases 3.2 Comparative Analysis of Color Scheme Application 4 Color Application Feedback from Nuclear Power Plants 5 HPR1000 Color Scheme Design 5.1 Color Scheme Design Principle 5.2 HPR1000 Color Scheme 6 Summary and Prospect References Study for Human Reliability Analysis on Reactor Pit Injection for SA Mitigation in NPP 1 Introduction 2 Assessment Methodology 2.1 Qualitative Analysis 2.2 Quantitative Analysis 3 Human Reliability Analysis for Reactor Pit Injection 3.1 Description of the Assessed Scenario 3.2 Qualitative Analysis for SA Diagnosis 3.3 Quantitative Analysis for SA Diagnosis 3.4 Qualitative Analysis for Reactor Pit Injection 3.5 Quantitative Analysis for Reactor Pit Injection 3.6 The Quantification for Reactor Pit Injection 4 Improvement Recommendations 5 Conclusion References Research and Application of Life Monitoring Scheme of Plant Computer Information and Control System 1 Introduction 2 Analysis of PCICS Life Monitoring in Design Scope 3 Overview of PCICS Life Monitoring Scheme 4 PCICS Life Monitoring Function Analysis 5 Experiment of PCICS Minimum Configuration 6 Conclusions References Application Research on Intelligent Fault-Diagnosis of Nuclear Power Plant Equipment Based on Support Vector Machine 1 Introduction 2 Multi Class Classification Algorithm Based on 2-support Vector Machine 2.1 One Against One Classification 2.2 One Against All Classification 2.3 Linear Binary Tree Classifications 2.4 Selection of Kernel Functions 3 SVM Classification Training and Application 3.1 Vibration Test Device and Fault Feature Extrac