Nuclear Power Plants: Innovative Technologies for Instrumentation and Control Systems: The Fourth International Symposium on Software Reliability, ... Protection of Nuclear Power Plant ISNPP

Preface
Organization
	Hosts
	Organizers
	Co-organizers
	Editors
	Secretary of Organizing Committee
	Director of Executive Committee
Contents
Analysis and Countermeasures of Inconsistency for Acoustic Design and Lighting Design Regulations and Standards in Main Control Room of Nuclear Power Plant
	Abstract
	1 Introduction
	2 Standard System of Environmental Design Laws and Regulations for MCR
	3 Requirements of Design Regulations and Standards for MCR and Analysis of Current Situation in Operating Power Plant
		3.1 Acoustic Design in MCR
		3.2 Lighting Design in MCR
	4 Correct and Error Analysis of Environmental Part Standard Description of MCR
	5 Concluding Remarks
	References
Application of Mixed Reality Based on Hololens in Nuclear Power Engineering
	Abstract
	1 Application of MR in Nuclear Power Engineering
		1.1 Design of Nuclear Power Engineering
		1.2 Equipment Maintenance
		1.3 Staff Training
	2 Solutions of MR
		2.1 Collaborative Design
		2.2 Intelligent Maintenance
		2.3 Training System for HPR1000
	3 Analysis of Application Effect
	4 Conclusion
	References
Visualization of Geologic Engineering Data Based on Nuclear Power Plant
	Abstract
	1 Research Background
	2 Visualization Blue Print
		2.1 Data Collection
		2.2 Data Management
		2.3 Arithmetic Disposal
		2.4 Three-Dimensional Imaging
	3 Visualization Application
	4 Conclusion and Expectation
	References
Research on Defense-in-Depth Zone of Low-Altitude Security Area in Nuclear Power Plant
	Abstract
	1 Preface
	2 Analysis of Low-Altitude Defense Zones in Nuclear Power Plants
		2.1 Analysis of Nuclear Power Plant Security Area
		2.2 Analysis of the Intrusion UAV
		2.3 Analysis of Detection Equipment
		2.4 Analysis of Response Time
	3 Defense-in-Depth Zone of Low-Altitude Area in NPPs
		3.1 Proposal for Defense-in-Depth Zone of Low-Altitude Area in NPPs
		3.2 Problems
	4 Conclusion
	References
Research on Axial Power Deviation Safety Early Warning Technology Based on Online Simulation
	Abstract
	1 Introduction
	2 Mechanism of Online Simulation Technology
	3 Axial Power Deviation Safety Early Warning Technology
		3.1 Safety Early Warning Mechanism and Axial Power Deviation
		3.2 Early Warning for Axial Power Deviation ΔI Control
		3.3 System Verification
	4 Conclusions
	References
Integrated Digital Control Platform for Flywheel Systems with Active Magnetic Bearings
	Abstract
	1 Introduction
	2 Nonintegrated Digital Control System
		2.1 Insufficient of the Single-Core DSP Control Platform
		2.2 Similar Tasks Between the Digital Control Board and the Amplifier Control Board
		2.3 Higher Integration Degree
	3 Integrated Digital Control System
		3.1 Dual-Core DSP
		3.2 Integration of the Digital Control Board, the Power Amplifier Control Board and the Displacement Sensor Board
		3.3 Control Parameter Adjustment on Line
	4 Function Implement
		4.1 Board Integration
		4.2 Experiments Using the Integrated Platform to Replace the Nonintegrated Platform
		4.3 Control Parameter Adjustment on Line
	5 Conclusion
	Acknowledgments
	References
Off-Line Performance Calculating Software of the Secondary Loop Thermal System in AP1000 Nuclear Power Plant
	Abstract
	1 Introduction
	2 Offline Software Theoretical Calculation Model
		2.1 Design Condition Module Main Equipment Calculation Model
		2.2 Variable Working Condition Module Calculation Model
		2.3 Consumption Difference Analysis Module Calculation Model
	3 Off-Line Software Development Environment
		3.1 Off-Line Software Development Platform
		3.2 Off-Line Software Program Execution Block Diagram
	4 Off-Line Software Function Module
		4.1 Design Conditions Module
		4.2 Variable Working Condition Analysis Module
		4.3 Dissipation Analysis Module
	5 Conclusion
	References
Monitoring and Analyzing of Wall Temperature Fluctuations for Thermal Fatigue in Elbow Pipe
	Abstract
	1 Introduction
	2 Model Analysis
		2.1 Inversion Heat Conduction
		2.2 Interpolation Analysis of Temperature Fields
	3 Model Solving and Calculation
		3.1 Pipe Structural Information
		3.2 Solving of Inner and Outer Wall Temperatures at the Analysis Point 8
		3.3 Solving of Inner and Outer Wall Temperatures at the Analysis Point 9
	4 Test and Analysis
		4.1 Experiment Condition
		4.2 Meshing and Boundary Conditions
		4.3 Results Analysis
	5 Conclusions
	References
Discussions on Information Security Test Strategy for Digital Industrial Control System in Nuclear Power Plant
	Abstract
	1 Introduction
	2 Related Works
		2.1 Difference Between Industrial Control System and IT System
		2.2 Status of Application of Industrial Control System in Nuclear Power Plants
	3 Nuclear Electric Control System Information Security Layering Model
	4 Nuclear Power Plant Industrial Control System Safety Test
		4.1 Human-Machine Layer Test
		4.2 Network Transport Layer Test
		4.3 Entity Layer Test
		4.4 Enterprise Layer Test
		4.5 Nuclear Power Plant Information Security Defense in Depth
	5 Conclusions
	References
Study and Implementation on General Operating Procedure of CPR1000 Main Control Room in China
	Abstract
	1 Introduction
	2 General Operating Procedure of CPR1000 Main Control Room
		2.1 Structure and Operating Means
		2.2 Navigation
		2.3 Data Integrity and Monitoring
		2.4 Computerized Operating Modes
		2.5 Document Management
	3 Human Factor Engineering
		3.1 Commissioning Test Results
		3.2 Application Results
	4 Conclusions
	References
Inductive Displacement Sensors Based on the Integrated Demodulation Chip
	Abstract
	1 Introduction
	2 Design and Principle
		2.1 Sensor Principle
		2.2 Synchronous Demodulation
		2.3 ADA2200
	3 Hardware Design
	4 Software Design
		4.1 The Configuration of the ADA2200
		4.2 Data Collecting of the ADC
	5 Experimental Results and Discussion
		5.1 The Build of the Test Platform
		5.2 Debugging with an Oscilloscope
		5.3 Signal Acquisition and Processing
	6 Conclusion
	Acknowledgments
	References
The Development of TMSR-SF0 Simulation Protection System
	Abstract
	1 Introduction
	2 System Design
		2.1 System Configuration
		2.2 Signal Processing Chassis and Logic Processing Chassis
		2.3 Local Engineer Stations
		2.4 One-Way Gateways
		2.5 Safety Panel
		2.6 Simulation Nuclear Instrument System
		2.7 Periodic Test Device
	3 RPS Experiment
	4 Conclusions
	References
Assessment of Operating Safety State of Nuclear Power Plant Based on Improved CAE Method
	Abstract
	1 Introduction
	2 State Assessment Method Based on CAE Theory
		2.1 Simplified State Assessment Method Based on CAE Theory
		2.2 Quantification of Assessment Results
	3 A Variable Weight Analytical Hierarchy Process Algorithm for Assessment Model
		3.1 Variable Weight Algorithm and Weights Optimization
	4 Establishment of Operation Safety Assessment Model for Nuclear Power Plant
		4.1 The Assessment of Integrity State of Pressure Boundaries in Nuclear Power Plants
		4.2 The Determination of Weights
	5 The Verification of Operation Safety Assessment for Nuclear Power Plant
	6 Conclusion
	References
Analysis and Solution of Design Difficulties of HMI with Scale Increase in Limited Space
	Abstract
	1 Introduction
	2 Analysis of HMI Change
	3 Formulating Effective Coping Strategies
	4 Design Scheme of HMI
	5 Conclusions
	References
Application Analysis of Wireless Sensor Networks in Nuclear Power Plant
	Abstract
	1 Introduction
	2 Wireless Sensor Network Architecture and Node Composition
	3 Application of Wireless Sensor Networks in Nuclear Power Plant
		3.1 Application Status
		3.2 Application Analysis
	4 Technical Feasibility Analysis
		4.1 Anti-jamming Technology
			4.1.1 Spread Spectrum Frequency Hopping
			4.1.2 Ultra-Wideband Communication Technology
			4.1.3 Separation Limits Between I&C Equipment and Wireless Devices
			4.1.4 Cognitive Wireless Anti-Jamming Based On Machine Learning
		4.2 Low Power Technology
			4.2.1 Sleep/Wake Mechanism
			4.2.2 Power Management
		4.3 Wireless Coexistence Measures
		4.4 Information Safety
		4.5 Anti-irradiation Measures
	5 Conclusion
	References
Development and Application of Intelligent Platform for Collaborative Electrical Design of Nuclear Power
	Abstract
	1 Introduction
	2 Electrical Design Platform
		2.1 Project Information
		2.2 Construction Objectives
		2.3 Features of Electrical Design Platform
	3 Platform Technical Scheme and Functions
		3.1 System Architecture
		3.2 Platform Application Framework
		3.3 Function Modules
	4 Platform Application and Advantages
		4.1 User Rights Management
		4.2 Intelligent Applications
		4.3 Platform Advantages
	5 Applications in Nuclear Power
		5.1 Project Application Status
		5.2 Deficiencies and Improvement Direction
	6 Conclusion
	References
Research on Stewardship-Intensive Digital Procedure System
	Abstract
	1 Preface
	2 General Introduction
		2.1 Development of Digital Procedure of NPPs
		2.2 Overall Goal of SIDPS
		2.3 Function of SIDPS
	3 Technology Implementation of SIDPS
		3.1 Logical Architecture Design
		3.2 System Deployment
		3.3 Workflow of SIDPS
	4 Improved Function of SIDPS
	5 Conclusions and Prospects
	References
Study and Optimization of Load Fluctuation of the Turbine Generator After Connected to the Grid in Nuclear Power Plant
	Abstract
	1 Preface
	2 Technology Description of the Turbine Speed and Load Control
	3 Study in Load Fluctuation and Optimization of the Control Scheme
		3.1 Optimization of the Grid Connection Scheme
		3.2 Optimization of the Load Closed Loop Control
	4 Conclusion
	References
Study for Design and Application of Procedure-Based Automation in Nuclear Power Plant
	Abstract
	1 Types of Operating Procedures
	2 Consideration for CBPs Design and Application
	3 Characterization Framework of PBA
	4 Design and Application of PBA
		4.1 Automatic Diagnosis of Plant Conditions
		4.2 Architecture of the CBPs of PBA
			4.2.1 Start/Stop by Operators
			4.2.2 Plant Parameters and Soft Controller Integrated into CBPs
			4.2.3 Automatic Calculation of Procedure Steps
			4.2.4 Dynamic Path Indication
			4.2.5 Automatic Control Selected by Operator
			4.2.6 Record Function
	5 Verification
	6 Conclusion
	References
Research on KDA System Reliability Model Based on Total Probability Formula
	Abstract
	1 Introduction
	2 Analysis of Serious Accident Instrument Control System
	3 Application of Full Probability Formula
		3.1 Sample Space Division
		3.2 Derivation of the Full Probability Formula
	4 Derivation of Reliability Model Based on Full Probability Formula
		4.1 Sample Space Division
		4.2 Dual Unit Failure Mode
		4.3 Single Unit Failure Mode
		4.4 No Unit Failure Mode
	5 Model Calculation and Analysis
	6 Conclusion
	References
The Research and Application of Test Method for 1E I&C System Platform’s Change
	Abstract
	1 Introduction
	2 Standard Requirements for Nuclear Safety Product Changes
	3 Technical Solutions
		3.1 Process Integrity
		3.2 Test Adequacy
	4 Application Practice
	5 Conclusion
	References
Research and Application of a User Interface Automatic Testing Method Based on Data Driven
	Abstract
	1 Introduction
	2 Technical Solution Realization
		2.1 Basic Widget Library
		2.2 Basic Operation Library
		2.3 The Test Data
	3 Test Case Realization
	4 Test Case Execution
	5 Practical Application and Effect
	6 Conclusion
	References
Research on a Certainty Data Link Layer Protocol for the Communication Network in Nuclear Safety DCS
	Abstract
	1 Introduction
	2 Certainty for Safety Communication Protocols
		2.1 Certainty Required by Standards and Regulations
		2.2 Factors Influencing the Certainty of Protocols
			2.2.1 Cumulative Characteristics
			2.2.2 Discrete Characteristics
			2.2.3 Parallel Characteristics
	3 Solution to Certainty Safety Communication Protocols
		3.1 The Topology and the Sample Model
			3.1.1 The Topology of the Safety Communication Network
			3.1.2 The Simple Model in the Safety Communication Network
		3.2 The DLL of the Safety Communication Network
			3.2.1 The Data Mapping Control Sublayer
			3.2.2 The MAC Control Sublayer
			3.2.3 The MAC Data Channel Sublayer
		3.3 The Certainty Protocol Implemented in the DLL
			3.3.1 State-Based Communication with Certainty
			3.3.2 Fixed Transmission Mode
			3.3.3 Producer-Consumer Model
			3.3.4 Optimised Types of Frames
			3.3.5 Fixed and Calculable Transit Data
			3.3.6 Parallel Data Mapping Management
	4 Test and Verification
	5 Conclusion
	References
A Design of FPGA-Based Self-healing System for Communication Networks in Nuclear Safety DCS
	Abstract
	1 Introduction
	2 Analysis of the Fault Mode in the FirmNet
		2.1 Review of the FirmNet
		2.2 Analysis of the Fault Mode
			2.2.1 Single Node Failure
			2.2.2 Multi-node Failure
		2.3 Requirement of Self-healing Systems
	3 Design of a FPGA-Based Self-healing System
		3.1 Design of the Self-healing System
			3.1.1 Structure of the Network
			3.1.2 Working Principle of the Self-healing System
		3.2 Implementation of the Self-healing System on FPGAs
			3.2.1 The Advantage of FPGAs
			3.2.2 The Design of Logic
			3.2.3 The Data Flow
			3.2.4 Isolation
	4 Simulation and Verification
		4.1 Simulation
		4.2 Verification
	5 Conclusion
	References
A Formal Method for Verifying the Ability of a Protocol to Resist Replay Attacks
	Abstract
	1 Introduction
	2 Overview of Verification Methods
	3 Verification Process
		3.1 Analysis of Communication Protocol
		3.2 Building of Communication Model
		3.3 Building of Attacker Model
		3.4 Detection with Formal Tools
		3.5 Verification Conclusion
	4 Application Practice
		4.1 Analysis of Communication Protocol
		4.2 Building of a Communication Model
		4.3 Building of an Attacker Model
		4.4 Detection with Formal Tools
		4.5 Display of Attack Process and Verification Conclusion
	5 Conclusions
	Acknowledgement
	References
Design and Analysis of Safety DCS Cabinet for Small Marine Reactor Based on the FirmSys
	Abstract
	1 Introduction
	2 SMR DCS Cabinet Demand Analysis
	3 Key Design Difficulties of SMR DCS Cabinet
		3.1 Shock Resistance Design and Input Requirement
			3.1.1 Shock Resistance Design Requirement
			3.1.2 Shock Requirement Input Requirement
		3.2 IP Protection and Heat Dissipation Requirement
			3.2.1 IP Protection Design Requirement
			3.2.2 Heat Dissipation Requirement
			3.2.3 Design Difficulty to Meet Both IP Protection and Heat Dissipation Requirements
	4 Solutions to Key Design Difficulties of SMR DCS Cabinet
		4.1 Shock Resistance Design Scheme
			4.1.1 Shock Resistance System Design
			4.1.2 Shock Resistance Detail Design
		4.2 Design Schemes of Heat Dissipation and IP Protection
			4.2.1 Airway Design
			4.2.2 IP Protection Design
			4.2.3 Heat Dissipation Analysis
			4.2.4 Prototype Verification
	5 Conclusions
	Acknowledgement
	References
The Design of Safety Control Display Device of Small Modular Offshore Floating Reactor Protection System Based on FirmSys
	Abstract
	1 Introduction
	2 Application Status of Safety Control Display Device
	3 Requirement of Safety Control Display Device Analysis
	4 Safety Control Display Project Design
	5 Safety Control Display Screen Design
		5.1 Main Function Design
		5.2 Man-Machine Interface Design
	6 Customized Keyboard Design
		6.1 Design Features
		6.2 Keys Design
	7 Design Verification
	8 Conclusions
	9 Acknowledgement
	References
Research on Maintenance Network Design Based on Nuclear Power Station Safety DCS System
	Abstract
	1 Introduction
	2 Composition of LAN System and Analysis of 802.3 Protocol
	3 Design of Real-Time Data Monitoring Method
		3.1 Network Model Design
		3.2 Design of Functional Instructions
		3.3 Format Design of Network Protocol
		3.4 Design of Communication Security and Reliability
		3.5 Design of Abnormal Notice
		3.6 Design of Communication Process
	4 Realization of Data Monitoring Process
		4.1 Create Link
		4.2 Data Monitoring
		4.3 Data Enforcement
		4.4 Disconnect the Link
	5 Test Results and Analysis of Prototype 4
	6 Closing Remarks
	References
Research and Application of RPN Detector Positioning Technologies in Nuclear Power Plants
	Abstract
	1 Introduction
	2 Positioning Requirements
		2.1 Radial Arrangement
		2.2 Axial Arrangement
		2.3 Measurement Requirements
		2.4 Operation and Maintenance Requirements
		2.5 Environmental Conditions
		2.6 Engineering Implementation
	3 Technological Status
	4 Implementation of Advanced “Bucket Type” Technology
		4.1 Positioning Scheme
		4.2 Radial Position of Detectors
		4.3 Axial Position of Detectors
		4.4 Connection Box and Junction Board
		4.5 Detector Assembly Connection
	5 Technological Advantages
		5.1 Pros and Cons Analysis of Positioning Technologies
		5.2 Technological Advantages of “Bucket-Type”
	6 Conclusion
	References
A Safety Level DCS Symbol Execution Test Optimization Method
	Abstract
	1 Introduction
	2 Symbolic Execution Technique
	3 Nuclear Safety Level DCS Software System
	4 DCS Software Symbolic Execution Test
	5 Experiment
	6 Summary
	References
Application Research of Fault Diagnosis in Conventional Island of Nuclear Power Plant Based on Support Vector Machine
	Abstract
	1 Introduction
	2 Establishment of Dataset
	3 Establishment of SVM Model
		3.1 Theory and Mathematical Model
		3.2 Mathematical Expression
		3.3 Programming Language Python
		3.4 SVM Model
		3.5 Kernel Function Selection
		3.6 Parameters Tuning and Prediction
		3.7 Result Analysis
	4 Summary and Discussion
	References
Software Verification and Validation of Digital Nuclear Instrumentation System
	Abstract
	1 Introduction
	2 The Software Lifecycle Model
	3 The Tasks of Software V&V in Different Stages
		3.1 Verification of RPN Equipment Specification
		3.2 Verification of Software Requirements Specification and Design Specification
		3.3 Verification of Software Code
		3.4 Unit Test
		3.5 Integration Test
		3.6 Validation Test
	4 Summary
	5 Conclusion
	References
Research on the Human Factors Integration in Some Third Generation NPP
	Abstract
	1 Introduction
	2 Human Factors Integration Strategy Analysis
	3 HF Organization
		3.1 HF Team
		3.2 Human Factors Integration Goal
		3.3 HF Training
	4 Human Factors Integration Process
		4.1 Previously Practice and Regulation Expectation Analysis
		4.2 Human Factors Integration Process Development
	5 HFI Activities Practices
		5.1 Operating Experience Review
		5.2 HF Guidelines Development and Implementation
		5.3 HF Review
		5.4 Important Human Actions Identification and Assessment
			5.4.1 Important Human Actions Identification
			5.4.2 Important Human Actions Assessment
		5.5 HF Verification & Validation
		5.6 HF Issues Register Management
	6 Conclusions
	References
Development and Application of Closed-Loop Control Performance Evaluation System for Nuclear Power Plant
	Abstract
	1 Introduction
	2 Key Technologies of Performance Evaluation for Closed-Loop Control Systems
		2.1 Classification of Control System Responses of Nuclear Power Units
		2.2 Evaluation Index and Calculation Method
	3 Development of Evaluation System System
		3.1 Functional Architecture of System System
		3.2 Data Storage
		3.3 Implementation of System System
	4 Experimental Result
		4.1 Performance Evaluation of Pressurizer Pressure Control
		4.2 Performance Evaluation of Pressurizer Level Control
		4.3 Contrastive Analysis Unit and Reference Unit
	5 Conclusion
	References
Research on Typical Fault Diagnosis of Nuclear Power Plant Based on Weighted Logical Inference Arithmetic
	Abstract
	1 Introduction
		1.1 Research Background
		1.2 Research Contents
	2 Research and System Development Based on Weighted Logical Inference Arithmetic
		2.1 Fault Diagnosis Reasoning Logic
		2.2 Obtaining the Set Value of Expert Database
		2.3 Fault Diagnosis Interface and Logical Inference Design
	3 Typical Fault Diagnosis – Excessive Discharge of Steam in the Second Loop
	4 Conclusions
	References
Information Security Risk Analysis and Countermeasures of Digital Instrumentation Control System in NPP
	Abstract
	1 Introduction
	2 Introduction to the Information Safety of Digital Instrument Control System in NPPs
		2.1 Information Safety
		2.2 Digital Instrument Control System in NPPs
			2.2.1 Level of Information Management of the Whole Plant
			2.2.2 Control and Monitoring Level
			2.2.3 Automatic Control and Protection Level
			2.2.4 Process System Interface Layer
		2.3 Current Situation of Information Safety of Digital Instrument Control System in NPPs
	3 Risk Analysis on Information Safety of Digital Instrument Control System in NPPs
		3.1 Risk Analysis on Information Safety of Digital Instrument Control System in NPPs
			3.1.1 Risk Analysis on Process System Interface Layer
			3.1.2 Risk Analysis on the Automatic Control and Protection Level
			3.1.3 Risk Analysis on Operation and Information Management Level
			3.1.4 Risk Analysis on the Level of Information Management of the Whole Plant
		3.2 Risk Analysis on the Information Safety of Digital Instrument Control System in NPPs
	4 Discussion on Responses to the Information Safety of Digital Instrument Control System in NPPs
		4.1 Operating Power Plants
			4.1.1 Management
			4.1.2 System Software
			4.1.3 Internet
			4.1.4 Monitor and Response
		4.2 New Power Plants
	5 Conclusion
	References
The Research and Development of Digital General Operating Procedure
	Abstract
	1 Foreword
	2 General Planning of the Digital General Operating Procedure
		2.1 The Concept of Digitalization
		2.2 The Feedback of N4 and EPR
		2.3 General Guidelines for Digitalization of Operating Procedures
	3 Design Scheme of Each Module’s Structure of the General Operating Procedure
		3.1 “Procedure Body” and “Digital Operating Sheet”
		3.2 Supporting Display Design According to the Task-Oriented Principle
		3.3 Format and Content of Structured Navigation Display
		3.4 Alarm Monitoring for Unit Start and Shutdown
	4 The Verification of Digital General Operating Procedures
		4.1 Simulation Verification
		4.2 Application Validation During Commission Start-up
	5 Usage of the Digital General Operating Procedures
	6 Conclusion
	References
Research on Hybrid Communication System for Nuclear Power Plants Safety-DCS
	Abstract
	1 Introduction
	2 Development of Industrial Wireless Communication Technology
	3 Design of Hybrid Communication System
		3.1 Construction of Hybrid Communication in DCS
		3.2 The Advantage of Hybrid Communication in DCS
		3.3 Feasibility Research of Hybrid Communication in Safety DCS of NPP
			3.3.1 Electromagnetic Properties of Wireless Communication Channels
			3.3.2 Reliability Assurance of Hybrid Communication DCS
	4 Conclusions
	References
Analysis of Analog Circuit Error in Reactor Control System
	Abstract
	1 Introduction
	2 The Error Model of Op-Amp Circuit
		2.1 Offset and Temperature Drift of Op-Amp
		2.2 Open Loop Gain, Input and Output Impedance in Op-Amp
		2.3 Peripheral Resistance Error and Temperature Drift
		2.4 Op-Amp Noise and Resistor Noise
		2.5 Comparison of Error Sources
	3 Error Combination
		3.1 A General Model of Inverting Op-Amp Circuit
		3.2 Calculation Results
		3.3 PSPICE Simulation
	4 Analog Circuits in Reactor Control System
		4.1 Analog Input Circuit
		4.2 RTD Conditioning Circuit
		4.3 Fission Chamber Preamplifier
		4.4 Comparison of Three Circuits
	5 Conclusions
	References
Reliability Analysis of Safety Class Analog Output Module Based on FFTA in Nuclear Power Plant
	Abstract
	1 Introduction
	2 Fuzzy Fault Tree Analysis (FFTA) Method
		2.1 Fuzzy Probability
		2.2 Logic Gate Fuzzy Operator
		2.3 Fuzzy Significance
	3 Reliability Analysis of the Analog Output Module
		3.1 Fuzzy Fault Tree of the Analog Output Module
		3.2 Quantitative Analysis of Reliability of Analog Output Module
			3.2.1 Analysis on the Probability of the Module Failure
			3.2.2 Analysis of the Weak Link
	4 Conclusion
	References
Research on Instrument Channel Uncertainty of Nuclear Power Plant
	Abstract
	1 Introduction
	2 The Traditional Method of Calculating Uncertainty
		2.1 Preparation for Calculation
		2.2 Uncertainty Calculating Method Based on SRSS
		2.3 Uncertainty Calculating Method Based on GUM
	3 Uncertainty Calculation Method Based on Monte Carlo
	4 Comparisons Between MCM and Traditional Methods
	5 Conclusion
	References
Research and Analysis on 1E Distributed Control System Priority Logic Module
	Abstract
	1 Introduction
	2 Priority Logic Module Analysis of Different Platform
		2.1 CommonQ
		2.2 NASPIC
		2.3 Firmsys
		2.4 MELTAC
		2.5 Tricon
		2.6 TXS
		2.7 The Reliability of Priority Logic Module
	3 Summary Analysis
	4 Conclusions
	Acknowledgments
	References
Design and Optimization of Communication in Nuclear Safety Class Emulation System
	Abstract
	1 Background
	2 The Communication Framework of Virtual Nuclear Safety DCS Based on TCP Protocol
		2.1 Brief of TCP
		2.2 Emulation Framework Design of Safety Communication Protocol Based on TCP
	3 Design of the Communication
		3.1 Design of the Communication in I&C Emulation System
			3.1.1 Communication Design Between DMS and VCS
			3.1.2 Communication Design Between DMS and VCS
			3.1.3 Communications Between VCSs
		3.2 Communication of Process Model
		3.3 Communication Between I&C Emulation System and Other Parts of FSS
	4 Signal Transmission Optimization in Emulation System
		4.1 Signal Transmission Difference Between Emulation System and Physical System
		4.2 Optimization
		4.3 Analysis of Optimization Case
	5 Conclusion
	References
Reliability Allocation Based on Importance Measures
	Abstract
	1 Introduction
	2 Why Reliability Allocation Based on Importance Measures Is Needed?
		2.1 A Simple Example
		2.2 One Fact
		2.3 An Idea
	3 The Model of Reliability Allocation Based on Importance Measures
		3.1 The General Model
		3.2 The Forms of f(·)
	4 Relation with Conventional Models of Reliability Allocation
		4.1 Traditional Models of Reliability Allocation
		4.2 Cost-Related Importance Measure
		4.3 Relationship of the Two Reliability Allocation Methods
	5 Case Study
	6 Conclusion
	References
Discussion on Traceability Analysis Method of Safety Software in Nuclear Power Plants
	Abstract
	1 Introduction
	2 Software Verification and Validation
	3 Requirement Items
	4 Traceability Analysis Method
	5 Summary
	References
The Application of LSTM Model to the Prediction of Abnormal Condition in Nuclear Power Plants
	Abstract
	1 Introduction
	2 Prediction Methods: Past and Present
		2.1 A Traditional Statistical Attempt: Kalman Filter
		2.2 Traditional RNN Attempts: Struggling Against the Timeline
		2.3 The LSTM Model: Keeping Critical Info for Prediction
			2.3.1 LSTM Model
			2.3.2 Rolling Update Mechanism
			2.3.3 Data Normalization
			2.3.4 Dropout Method
			2.3.5 MSE
	3 Experiment Preparation: Data, Parameters, and Training
		3.1 Data Normalization
			3.1.1 Steam Generator Pressure Adjustment
			3.1.2 Small LOCA
		3.2 Model Configuration
		3.3 Model Training
	4 Results and Analysis
		4.1 Comparison Between RNN and LSTM
		4.2 Prediction of Small LOCA Accident
	5 Conclusion
	References
Development and Application of Undisturbed Online Downloads in the FirmSys
	Abstract
	1 Introduction
	2 Requirement Analysis of the Online Downloading
		2.1 Configuration Modification Supported by Online Download
		2.2 Control Station Function Requirements During Online Download Process
		2.3 Online Downloading Tool Requirements
		2.4 Performance Specifications
		2.5 Safety Requirement
	3 Schematic Design
		3.1 The Online Downloading in General Industrial Control System
		3.2 Overall Design of the Downloading
		3.3 Implementation of Each Step
			3.3.1 S1: Download VC
			3.3.2 S2: Switch B to RUN
			3.3.3 S3: Synchronize with the Counter-Partner
			3.3.4 S4: Operate as Slave
			3.3.5 SWAB: Switch Master-Slave
		3.4 Tool-Related Design
			3.4.1 Compiling
			3.4.2 Download
			3.4.3 Version Comparison
		3.5 Design Standard Compliance Analysis
	4 Implementation and Application
	5 Conclusion
	References
The Study on Automatic Control of Pressure and Temperature for the Pressure Water Reactor Nuclear Power Plant
	Abstract
	1 Introduction
	2 Algorithm Analysis and Development of Temperature Control Module
	3 Logic Design and Implementation of Automatic Temperature Control
		3.1 Logic Design of Temperature Control of Steam Generator
		3.2 Logic Design of Normal Residual Heat Removal of Temperature Control
		3.3 Logic Design of Pressure Control
	4 Verification of Results and Analysis
		4.1 Verification of Temperature and Pressure Reduction in Normal Intermediate Shutdown
		4.2 Verification of Cooling Control After RHR Shutdown
		4.3 Analyses of Results
	5 Conclusion
	References
A Hierarchical Task Analysis Approach for Static Human Factors Engineering Verification and Validation of Human-System Interface
	Abstract
	1 Introduction
		1.1 A Subsection Sample
	2 Concept of V&V
	3 A Hierarchical Approach for Task Analysis
	4 Case Study
	5 Conclusions
	References
Research on Static Testing Technology of Nuclear Safety-Critical Software Based on FPGA Technology
	Abstract
	1 Introduction
	2 Nuclear Safety-Critical FPGA Software Programming Rules Requirements
	3 Research on Static Test Framework of Nuclear Security Level FPGA Software
		3.1 Applicability and Limitations of Test Tools
	4 Static Test Framework
		4.1 Static Test Basic Process
	5 Practice
	6 Conclusion
	References
Features Extraction Based on Deep Analysis of Network Packets in Industrial Control Systems
	Abstract
	1 Introduction
	2 Related Work
	3 Analysis of Network Packets
		3.1 Packets Capture
		3.2 Structure of Network Packets
	4 IT Network Feature Extraction
	5 Industrial Control Feature Extraction
		5.1 Conversation Correspondence
		5.2 Feature Extraction
	6 Application in Neural Network Approach
	7 Conclusion
	Acknowledgments
	References
An Optimum Solutions for Venturi Used for Main Feedwater Flowrate Measurement in Nuclear Power Plant
	Abstract
	1 Introduction
		1.1 Working Principle and Structure of Venturi Tube
	2 Structures and Problems Found in the Venturi Tube
	3 Causes of Problems and Analysis of Structural Defects
	4 Optimum Design Scheme
	5 The Advantages and Disadvantages of the Optimization Program
	6 Venturi Optimization Program Performance
	7 Conclusion
	References
Research and Application of Software Reliability Analysis Method for Safety I&C System in NPPs
	Abstract
	1 Introduction
	2 Software FMEA and FTA Comprehensive Analysis
		2.1 The Advantages and Disadvantages of the Analysis Methods
		2.2 The Principle of the Comprehensive Analysis
	3 Modeling and Application
		3.1 System Function and Structure
		3.2 Basic Conditions and Constraints
		3.3 FMEA and FTA Comprehensive Analysis
		3.4 Solve the Minimum Cut Set
		3.5 Develop Control or Improvement Measures
	4 Conclusions
	References
Development of Closed-Circuit Television Inspection System for Steam Generators in Nuclear Power Plants
	Abstract
	1 Introduction
	2 Inspection Scope and Inspection Requirement
	3 Mechanical System
	4 Drive Control System
	5 Software System
	6 Conclusion
	References
Research on the Security Technology of the Internet of Things in Nuclear Power Plant
	Abstract
	1 Introduction
	2 Internet of Things Threats at Nuclear Power Plant
	3 The Security Analysis of Nuclear Power Plant Internet of Things
	4 The Security Measures of Nuclear Power Plant Internet of Things
	5 Conclusions
	References
A Study About Safety Technology of Control System and Information System in Nuclear Power Plant
	Abstract
	1 Introduction
	2 Research on the NPP Control System and Information System Security Technology
	3 Conclusion
	References
Author Index