New Energy Power Generation Automation and Intelligent Technology: Proceedings of the Seventh Seminar on Digital Instrumentation and Control Technology for Nuclear Power Plant

Contents
Application of Lightning Protection Measures for Outdoor Instruments in Nuclear Power Plants
	1 Introduction
	2 Analysis of the Effect of Lightning Strikes on Instruments
	3 Optimization Plan and Analysis
		3.1 Improve Circuit Grounding
		3.2 Add Signal Isolation Device
		3.3 Add Lightning Protection Device
		3.4 Add Lightning Protection Device and Signal Isolation Device
	4 Analysis and Implementation
		4.1 Comparison and Confirmation of Different Schemes
		4.2 Effect Analysis
	5 Implementation
	6 Conclusion
	References
Study on High Flux at Shutdown Alarm Setpoint Automatic Update Logic
	1 Introduction
	2 High Flux at Shutdown Alarm
	3 Alarm Setpoint Automatic Update Logic
		3.1 Setpoint Update Manually During the Startup Phase
		3.2 Setpoint Update During Shutdown Phase
		3.3 Analysis of False Triggering of Alarm
	4 Measures to Avoid False Alarm of High Neutron Flux Rate in Shutdown
		4.1 Operational Administration
		4.2 Setpoint Update Logic Optimization
		4.3 Comparison of the Two Measures
	5 Conclusion
	References
Experimental Research on Data Management Method of Instrument and Control Emulation System
	1 Introduction
	2 Data Interaction Management in I&C Emulation System
		2.1 Data Interaction Management Between DMS and VCS
		2.2 Data Interaction Management Between VCS and Virtual Modules
		2.3 Data Interaction Management Between VCSs
		2.4 Data Interaction Management Between MS and VCS
		2.5 Data Synchronization Management Between VMPUs
	3 Data Interaction Management with Third-Party System
		3.1 Data Interaction Management with Process Model
		3.2 DataManagement of Saving and Loading IC
		3.3 DataManagement of IC Calibration Function
	4 Experimental Study
	5 Conclusion
	References
Analysis and Treatment on Control Rod Measured Position Fluctuation
	1 Introduction
	2 Control Rod Position Measurement Principle
	3 Reason Analysis for Rod Position Fluctuation
	4 Rod Position Detector Calibration
		4.1 Operation Guidelines for Rod Position Detector
		4.2 Rod Position Detector Calibration Principle
		4.3 Rod Position Detector Calibration Implementation
		4.4 Suggestions on the Optimization of the Power Supply
	5 Conclusion
	References
Anti-interference Study of Wireless Sensor Networks in Nuclear Power Plants
	1 Introduction
	2 Intelligent Anti-interference for Nuclear Power Plants Based on Machine Learning
		2.1 Intelligent Anti-interference Architecture
		2.2 Intelligent Interference with Cognition
		2.3 Anti-interference Intelligent Decision Making
		2.4 Multi-domain Anti-interference
	3 Simulation Verification
		3.1 Intelligent Interference Cognitive Simulation
		3.2 Anti-interference Intelligent Decision Simulation
	4 Conclusion
	References
Research on Application of High Temperature and High Pressure Radar Liquid Level Measurement in Nuclear Power Plant
	1 Introduction
	2 Frequency Modulated Continuous Radar Wave (FMCW) Split Guided Wave Radar Liquid Level Measurement Based on Frequency Domain Reflectometry (FDR)
		2.1 Large Dynamic Range Signal Reception Based on FM Interrupted Continuous Wave
		2.2 Large Dynamic Range Signal Reception Based on FM Interrupted Continuous Wave
		2.3 Long-Distance Signal Transmission and Signal Processing
	3 Analysis of Liquid Level Composition of Split Guided Wave Radar
		3.1 Electronics Unit
		3.2 Waveguide Rod
	4 Test and Validation
		4.1 Simulation Analysis
		4.2 Experimental Verification
	5 Conclusion
	References
Fault Analysis and Condition Monitoring of Drum Screens in Nuclear Power Plants
	1 Introduction
	2 Working Mechanism of Drum Screens
	3 Drum Screen Operation Event Analysis
		3.1 Corrosion of Metal Parts of Drum Screen
		3.2 Breakage and Looseness of Drum Screen Bolts
		3.3 Vibration of Drum Screen Driving Device
		3.4 Summary
	4 Optimization Analysis of the Condition Monitoring of Drum Screen
		4.1 Optimization Scheme of the Condition Monitoring of Drum Screen
		4.2 Feasibility Analysis of the Condition Monitoring of Drum Screen
	5 Conclusion
	References
Discussion on the Application of Advanced On-Line Monitoring Technology for Drum Screen in Nuclear Power Plant
	1 Background
	2 Introduction
	3 Online Monitoring Technology and Application Discussion
		3.1 Vibration/displacement Monitoring and Analysis Technology
		3.2 Optical Fiber/grating Sensing Technology
	4 Issues of Concern
	5 Conclusion
	References
Research on Source Range Channel Disturbance Diagnosis of Nuclear Instrumentation System
	1 Introduction
	2 The Principle of SRC
	3 Analysis of SRC Failure
		3.1 Electromagnetic Interference
		3.2 Changes in Temperature and Humidity
		3.3 Faulty Cable Connector
	4 Troubleshooting
		4.1 Electromagnetic Interference Countermeasures
		4.2 Measures to Deal with Changes in Temperature and Humidity
		4.3 Countermeasures for Cable Connector Failure
	5 Conclusion
	References
Analysis for Main Process Variables Control Function Categorization and System Classification in Nuclear Power Plant
	1 Introduction
	2 Design Scheme
		2.1 Function Categorization
		2.2 System Classification
		2.3 Reliability Claim
	3 Identified Difference
		3.1 Requirement of IEC 61226–2009
		3.2 Design Scheme of Other Projects
	4 Assessment
		4.1 Safety Analysis
		4.2 Reliability Claim Analysis
		4.3 PSA Analysis
	5 Conclusion
	References
Research on Pattern Recognition Method of Nuclear Power Production Data Based on Neural Network
	1 Introduction
	2 Research Status at Home and Abroad
	3 Pattern Matching of Nuclear Power Data Change Trend Based on Neural Network
		3.1 Input Layer
		3.2 Activation Function
		3.3 Output Layer
		3.4 Training Network
		3.5 Test Network
	4 Summary
	References
An Industrial Control System Vulnerability Analysis Method for Cyber Security in Nuclear Power Plant
	1 Introduction
	2 Research on Cyber Security Vulnerability
		2.1 Cyber Security Features of Industrial Control Systems
		2.2 Vulnerability Levels of Industrial Control Systems
	3 Cyber Security Vulnerability of Industrial System in Nuclear Power Plant
		3.1 Vulnerability Analysis Items
		3.2 Vulnerability Assessment Method Base on Influence of Functional Safety
	4 Conclusions
	References
Study of Optimization for Calibration of Nuclear Safety Classification Pressure Transmitter
	1 Introduction
	2 Current Circuit Analysis of Analog Pressure Transmitter
	3 Analysis of Current Calibration Principle of Analog Pressure Transmitter
	4 Optimization of Current Calibration Method for Analog Pressure Transmitter
	5 Experimental Verification
	6 Conclusion
	References
Modeling and Simulation of Secondary Loop Systems of a Pressurized Water Reactor Based on the 3KEYMASTER Platform
	1 Introduction
	2 A Secondary Loop Model Description
		2.1 The Steam Generator
		2.2 The Steam Turbine
		2.3 The Moisture Separator Reheater
		2.4 The Condensate System
		2.5 The Feedwater Heater System
		2.6 The Deaerator
	3 Simulation and Discussion
	4 Conclusions
	References
Treatment and Analysis of SG Level Control Problems in Nuclear Power Plant Startup and Low Power Stage
	1 Introduction
	2 SG Level Control Principle of ARE Start-Up Control Valve
		2.1 Stage Division of SG Level Control in the GEN-III Nuclear Power Plants
		2.2 Principle of SG Level Control by SCV
		2.3 Correction of Flow Characteristic Calculation
	3 Test Validation and Optimization
	4 Control Coupling Problem
	5 Solutions
		5.1 Change the Correction Logic
		5.2 Improve the Response Speed of Differential Pressure Control
		5.3 Final Solution
	6 Summary
	References
Weakness Analysis and Improvement on the Technical Galleries and Gutters Fire in CPR1000 Nuclear Power Plant
	1 Introduction
	2 Fire Characteristics of Comprehensive Technical Pipe Gallery
	3 Fire Design Status of Comprehensive Technical Pipe
		3.1 Cable Tray and Pipeline Layout
		3.2 Fire Compartment and Zoning
		3.3 Fire Detection Mode
		3.4 Fire Fighting Facilities
		3.5 Smoke Control and Lighting System
	4 Analysis of Weak Links in Fire Fighting
		4.1 Unreasonable Division of Fire Compartment
		4.2 Single Type of Fire Detection
		4.3 Insufficient Fire-Fighting Facilities and Single Form
		4.4 Insufficient Smoke Control Facilities
	5 Suggestions for Improvement Measures
		5.1 Optimize the Fire Zone Setting
		5.2 Optimize Fire Detection Methods
		5.3 Improve Fire Fighting Capacity
		5.4 Add Active Smoke Control System
	6 Conclusion
	References
Response Time Analysis Method of Safety-Level DCS in Nuclear Power Plant Based on Probability Theory
	1 Introduction
	2 Response Time Analysis
		2.1 Response Time Analysis Example
		2.2 Response Time Signal Path Analysis
		2.3 Probability Distribution of TMPU-I, TMPU-II
		2.4 Probability Distribution of TAI, TDO, TCOM-I, TCOM-II
		2.5 Probability Distribution of TES
	3 Response Time Calculation and Simulation
		3.1 Response Time Calculation
		3.2 Response Time Simulation
	4 Calculation and Simulation Results Verification
		4.1 Testing Environment
		4.2 Test Method
		4.3 Test Results
	5 Summary
	References
Rational Argument of the Closed Loop of the Reactor Spent Fuel
	1 Concept of Closed Nuclear Fuel Cycle
	2 Process Method and Case of International Advanced
		2.1 Process Method
		2.2 Hand Cases
	3 National Policy Orientation
	4 Current Situation, Successful Experience and Benefit in China
		4.1 Domestic Situation
		4.2 Successful Practice
		4.3 Benefits
	5 Conclusions
	References
Pressurizer Control Optimization with Deep Learning-Based Predictions
	1 Introduction
	2 The Pressurizer Pressure Control Model
		2.1 Theoretical Basis of the Pressure Control
		2.2 Pressure Control Loop in Simulink
	3 The Intelligent Control Using Deep Learning Method
		3.1 The Structure of the Intelligent Control Model
		3.2 Training and Implementation of the Intelligent Control Model
		3.3 Experiments and Results Analysis
	4 Conclusion
	References
Research and Application of Endogenous Security Active Defense Technology for Domestic Nuclear Safety-Level Gateway Equipment
	1 Research Background
	2 Information Security Requirements Analysis
	3 Gateway Equipment Information Security Protection Design
		3.1 Multi-dimensional Fine-Grained Access Control
		3.2 Trusted Calculation Design
	4 Conclusions
	References
I&C Design for Heat Supply Retrofit in Nuclear Power Plant
	1 Introduction
	2 Transformation of Mechanical System
	3 I&C Retrofit Design
		3.1 Main Design Principles
		3.2 I&C Overall Design Plan
		3.3 I&C Control Logic Scheme
	4 Evaluation of Existing I&C System
		4.1 DDB Impact Assessment
		4.2 Network Load Assessment
		4.3 Controller Performance Evaluation
	5 Conclusion
	References
Research and Application of Current Following Electrical Fire Monitoring Technology
	1 Introduction
	2 Electrical Fire Electrical Fault Analysis
		2.1 Short-Circuit
		2.2 Poor Heat Dissipation
		2.3 Poor Contact
		2.4 Overload
		2.5 Leakage
	3 Main Monitoring Means
		3.1 Residual Current
		3.2 Equipment and Ambient Temperature
		3.3 Fault Arc
		3.4 Pyrolysis Particles
	4 Residual Current Test Principle
	5 Residual Current Follow-Up Threshold Alarm Technology
	6 Conclusion
	References
Prediction of Electromagnetic Shielding Effectiveness of DCS Cabinet Based on Neural Network
	1 Introduction
	2 SE Calculation
	3 Algorithm Implementation
		3.1 Design of BP NN Algorithm
		3.2 SE Prediction Model Based on BP NN Algorithm
	4 Case Study
		4.1 Analysis Subjects
		4.2 Construction of BP NN Model
		4.3 Analysis of Experimental Results
	5 Conclusion
	References
Design and Implementation of DCS Design List Automatic Generation and Check System Based on LabVIEW
	1 Introduction
	2 Functional Requirements Analysis
		2.1 IO Variable Configuration Check Function
		2.2 Set Value List Generation Function
		2.3 Network Signal List Generation Function
	3 Solution
		3.1 IO Variable Configuration Check Function Design Implementation
		3.2 Set Value List Generation Function Design Implementation
		3.3 Network Signal List Generation Function Design Implementation
	4 Result
	5 Conclusion
	References
Reliability Analysis of Nuclear Safety-Class DCS ESFAS Based on FTA
	1 Introduction
	2 Research Object and Research Status
		2.1 Research Analysis
		2.2 Structural Analysis
	3 ESFAS System Reliably Model
		3.1 FTA Method
		3.2 Reliably Parameters Calculation Method
		3.3 FT Model
	4 Simulation Experiment
		4.1 Reliability Parameter Calculation
		4.2 Sub-system and System Reliability Simulation Analysis
		4.3 Minimum Cut Set and Importance Analysis
		4.4 Control Station Redundancy Design
		4.5 Maintenance Scheme Optimization
	5 Conclusion
	References
Research on Forward Design Process of Network Security Protection Design for Instrument and Control System in Nuclear Power Plant
	1 Introduction
	2 The Route Map of the Forward Design Process
	3 The Network Security Zone and Domain
	4 Grading Protection for Security Domain
	5 Identification and Protection for CDA
	6 Conclusion
	References
Application of Optocoupler Isolation in Rotation Speed Measuring Circuit of Maglev Blower
	1 Introduction
	2 Optocoupler
		2.1 Characteristics of the Optocoupler
		2.2 Operating Principle
		2.3 Voltage Regularization
		2.4 Suppression Interference
		2.5 Circuit Safety
	3 Application of Optocoupler Isolation in Measuring Circuit
		3.1 Voltage Regularization
		3.2 Suppression Interference
		3.3 Circuit Protection
	4 Conclusion
	References
Research and Practice on Hardware Failure Verification of Nuclear Instrument Control Platform
	1 Preface
	2 Background and Role
	3 Prediction and Calculation Method of Hardware Reliability of the Digital I&C System
		3.1 Prediction of Hardware Reliability of Digital I&C System
		3.2 Calculation of Two Basic Relationships of MTBF in Digital I&C System
	4 Prediction and Calculation Method of Hardware Reliability of Digital I&C System Module
		4.1 Digital I&C System Module Hardware FMEA Preparation
		4.2 Digital I&C System Module Hardware FMEA
		4.3 Module Hardware Component Level Failure Verification Process
	5 Concluding Remarks
	References
Research on Verification Method of PCIe IP Core Based on Programmable Logic
	1 Introduction
	2 Validation Platform Design
		2.1 IP Core Introduction
		2.2 Verification Framework
		2.3 Introduction to Verification Methods
	3 PCIe IP Core Verification
		3.1 Verification Platform Construction
		3.2 Determining the Interface Signal
		3.3 Constructing Test Incentive Data
		3.4 Sequence Scheduling
		3.5 Data Processing
	4 Validation Results
	5 Conclusions
	References
Determination of the Inputting Data Length for the Diagnosis of the Operation Trend Based on Wavelet Analysis
	1 Introduction
	2 Determination of Input Data Length for Operation Trend Diagnoses
		2.1 Resampling
		2.2 Wavelet Denoising
		2.3 Segmentation
		2.4 Input Data Length Determination
	3 Experimental Investigation
		3.1 Wavelet Denoising Performance
		3.2 Segmentation Performance
	4 Conclusion
	References
Research on Defence-in-Depth of Nuclear Power Plant DCS Based on Swiss Cheese Model
	1 Introduction
	2 Regulatory Requirements for Defence-in-depth
		2.1 IAEA
		2.2 WENRA
		2.3 NRC
	3 Swiss Cheese Model
	4 Model Application
		4.1 Defence-in-Depth Analysis of a Domestic Project
		4.2 Optimized Defence-In-Depth Analysis
	5 Conclusion
	References
Application Development and Research of 3D Parametric Intelligent Design System for Double Sheathed Liner Sumps
	1 Introduction
	2 Main Technical Scheme
		2.1 Toolkit Technology
		2.2 Model Parameterization
		2.3 Sorting Out the Relationship Between Model Size and Parameters [4]
		2.4 Automatic Assembly Method
	3 Scheme of 3D Parametric Intelligent Design System for Double Sheathed Liner Sumps
		3.1 System Framework
		3.2 Workflow
		3.3 Main Functions of the Interface
	4 Application Effect
	5 Conclusion
	References
Research on Software Reliability of Nuclear Power Plant Instrument Control System
	1 Introduction
	2 The Mechanism of Software Failure
		2.1 Definition of Software Failure
		2.2 Mathematical Description of Software Reliability
	3 Software Design Method
		3.1 Error Avoidance Design
		3.2 Fault-Tolerant Design
	4 Software Reliability Growth Model
		4.1 Overview
		4.2 Modeling and Application of Reliability Growth Model
	5 Summary
	References
An Algorithm of Nuclide Number Identification for Environmental Radioactivity Monitoring
	1 Introduction
	2 Portable γ Spectrometer
	3 Algorithm
		3.1 Acquire Array Signals
		3.2 Construct Incidence Matrix
		3.3 Calculate and Sort Eigenvalues
	4 Experiment and Analysis
		4.1 Analysis
	5 Conclusion
	References
Prevention and Treatment of Network Storm in Control Station of Digital I&C System in Nuclear Power Plants
	1 Introduction
	2 The Network Structure of DCS Systems and Analysis of Network Storm in Control Station
		2.1 The Network Structure of DCS Systems
		2.2 The Analysis of Network Storm
	3 The Design of the Master Processing Unit Identification Based on Improved Link Layer
		3.1 The Communication Design of Master Processing Unit
		3.2 The Design of Network Storm Resilience Mechanism
		3.3 The Processing of Packet Classification
	4 The Experimental Analysis and Results
	5 Conclusion
	References
Design of Robot System for Grinding the End of Reactor Core in Heavy Water Reactor Nuclear Power Plant
	1 Introduction
	2 Functional Requirement Analysis of Grinding the End of Reactor Core in Heavy Water Reactor Nuclear Power Plant
		2.1 Introduction of Heavy Water Reactor Nuclear Power Plant
		2.2 Functional Requirement Analysis of Grinding the End of Reactor Core in Heavy Water Reactor Nuclear Power Plant
	3 Analysis of the Design Scheme of Robot System for Grinding the End of Reactor Core in Heavy Water Reactor Nuclear Power Plant
		3.1 Difficulty Analysis
		3.2 Function Realization Method Analysis
		3.3 Advantage Analysis
	4 Design of Robot System for Grinding the End of Reactor Core in Heavy Water Reactor Nuclear Power Plant
		4.1 Grinding Robot Mechanism Function
		4.2 Video Part (Vision Sensor)
		4.3 Measurement Part
		4.4 Project Technology Breakthrough
	5 Dynamic Modeling of Robot System for Grinding the End of Reactor Core in Heavy Water Reactor Nuclear Power Plant
	6 Summary
	References
Research on Common Problems of Safety-Grade Batteries in Nuclear Power Plants
	1 Introduction of Lead-Acid Battery
	2 Common Problems of Safety-Grade Batteries
		2.1 The Problem that the Connection Resistance Measurement of the Safety-Grade Battery is not Carried Out After the Commissioning and Installation
		2.2 The Problem of the Lack of Quarterly Inspections in the Daily Regular Inspection of Safety-Grade Batteries
		2.3 The Problem of Lack of Operational Tests in Periodic Tests of Safety Grade Batteries
	3 Solution
		3.1 Solution for Safety-Grade Batteries Without Connection Resistance Measurement After Commissioning and Installation
		3.2 Solutions for Safety Grade Batteries Missing Quarterly Inspections in Routine Periodic Inspections
		3.3 The Solution for the Lack of Running Test in the Periodic Test of Safety Grade Battery
	4 Safety Significance
	References
Research and Application of Key Technologies of Nuclear Power Civil Engineering Design Platform
	1 Introduction
	2 Key Technology Research
		2.1 Standardized Management of Design Tasks and Calculation Activities
		2.2 Unified Management and Scheduling of Nuclear Civil Engineering Design Tools
		2.3 Research and Development of Civil Design Tools
		2.4 Structured Management and Intelligent Application of Design Data
		2.5 Data Connection with External Systems
	3 Conclusion
	References
Self-stability Analysis of Fluoride Salt Cooled High Temperature Reactor Based on Shifted-Ectropy Approach
	1 Introduction
	2 Nonlinear State-space model for FuSTAR
		2.1 Modeling
		2.2 Stability Analysis
	3 Construction of the Lyapunov function
	4 Self-stability analysis
	5 Conclusion
	References
Design of Static Semantic Analyzer for Code Generator Applied in Safety-Level I&C of NPPs
	1 Introduction
	2 The Synchronous Data Flow Language Lustre
		2.1 Lustre Syntax Features
		2.2 Lustre Special Function Operator
	3 The Design of Symbol Table
	4 The Design of Static Semantic Analyzer
		4.1 Identifier-Checking Declarations
		4.2 Identifier-Checking Programs
		4.3 Type-Checking Expressions and Equations
		4.4 Clock-checking Expressions and Equations
	5 Case Analysis
	6 Conclusions
	References
Main Instrumentation and Control Systems for Units 7&8 of Tianwan Nuclear Power Station
	1 Introduction
	2 Overall Main I&C Architecture for TNPS Units 7&8
	3 Main I&C System in TNPS Units 7&8
	4 Conclusion
	References
Study on Updating and Modification of Computer-Based Procedure System of Nuclear Power Plant
	1 Introduction
	2 Standard and Regulations
	3 Operating Experience
		3.1 Improvement of Automation Degree
		3.2 Improvement of Operation and Maintenance Management
	4 Analysis of Limitation Conditions of Modification
		4.1 Capability of Software and Hardware Platform
		4.2 Operator’s Operating Habits
		4.3 Architecture of Operation Procedure
		4.4 Plant Operation and Maintenance Plan
		4.5 Validation and Training
		4.6 Safety and Economic Benefits
	5 Updating and Modification of CPR1000 Plant
		5.1 Upgrading and Modification Plan
		5.2 Modification Design Principle
		5.3 Validation and Confirmation
	6 Future Study
	7 Conclusion
	References
Research and Application of BIM + GIS Technology for Underground Pipeline of Nuclear Power Plant
	1 Introduction
	2 BIM + GIS Advantage
	3 Key Technologies
		3.1 Model Data Optimization
		3.2 Model Data Transformation and Fusion
		3.3 Integrated Platform
	4 Application Cases
	5 Summary
	References
Author Index