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This book is the 2nd volume of proceedings of the 1st Smart Nuclear Power Technology Forum and the 8th China Nuclear Power Plant Digital Technology and Application Seminar held in Shenzhen, China in June 2024. This seminar aims to explore the software and hardware of digital and instrument control (I&ampC) systems in nuclear power plants, such as inspection, testing, certification and research of sensors, actuators and control systems, and the application of electrical and intelligent operation and maintenance technologies. It aims to provide a platform for experts, scholars and nuclear power practitioners to exchange technology and share experience. At the same time, it also provides a platform for the combination of universities and enterprises in the aspects of production, education and research, and promotes the safe development of nuclear power plants. In addition, readers will encounter new ideas to achieve more efficient and safer instruments and control systems.
Preface.
Research on Quantitative Hazard Analysis Method of Safety-Level I&ampC System Based on Fault Tree.
Exploration of Factory Testing Requirements Analysis Methods for Nuclear Safety Class DCS.
Simulation of Wear Fault of Drum Filter Gear Transmission System Based on Rigid-Flexible Coupling.
Response Time Measurement of Resistance Temperature Detector in Nuclear Power Plants Based on Noise Analysis.
Application of Systems Engineering Approach to Complex Multi-interface Technology Management in Nuclear Power Plant.
Improvement and Application of Technical Scheme for Power Variations Test of HPR Nuclear Power Plant.
A Method for Cable Tray Filling Rate Check.
Coupling Effect Analysis and Optimization Strategy of Pressure and Water Level Control in PWR Pressurizer.
Design and Simulation of Multi-gradient Negative Pressure Control System in Confined Space.
Research on Implementation Strategy of Overall Refurbishment of Digital Instrument Control System in Nuclear Power Plant.
Research and Application of SIS Design and Fault Tree Analysis of Nuclear Power Plant.
Nuclear Safety-Class DCS Design Based on Simulation with Independent Stations of Same-Configuration Technology.
Research on Improving the Engineering Design of Nuclear Safety-Class DCS Based on Process Optimization.
Discussion on the Verification and Validation Technology of Nuclear Safety Level Software Based on Bayesian Belief Network.
Optimization and Application of Task Scheduling in Virtual Testing Platforms.
Application of Machine Vision Technology in Intelligent Testing of Nuclear Power DCS Human-Machine Interaction.
Research on Key Technologies for the Transformation of Emergency Diesel Generator Control System in a Certain Nuclear Facility.
Application of CNN-LSTM in Predicting the Status of Control Drive Plug-Ins.
Design and Implementation of Security Audit System for Nuclear Safety-Class DCS.
Case Study on RPN Neutron Flux Change Rate High R.T. in PWR NPP.
Application of Fuzzy PID in Fluoride Salt Cooled High Temperature Reactor’s Nuclear Power Level Control.
Control Strategy Research on HOTSG Hydrodynamic Instability During ELPO Mode for Two-Loop SMR.
Simulation of Main Pump Two-Speed Start-Up Strategy of Advanced Small Reactor Based on Stable operation of Once-Through Steam Generator.
Research on Improvement of C2 Signal Alarm in Nuclear Instrument System of PWR Nuclear Power Plant.
Research on Fast Opening Setpoint of Turbine Bypass Discharge Valve in Nuclear Power Plant.
Analysis of the Influence of G Rods Calibration Curve Deviation on RRC Load Change Transients.
Simulation on Reactor Coolant System Pump Coastdown Transient of PWR and Test Criteria Optimization.
Simulation of Operation Characteristics of Helical Coiled Once-Through Steam Generator in Start-Up Stage.
The Study on the Effect of Core Neutron Parameters on the Maximum Linear Power Density During Condition II PCI Transients.
Simulation of Fouling Effect on OTSG Flow and Heat Transfer Performance.
Overpressure Analysis of Second-Class Low Temperature Water Compaction in HPR1000.
Study on the Influence of Ultra-Long ELPO for CPR1000 Unit on Rod Drop Accident.
Research on a Numerical Analysis Method of Two-Phase Flow Instability in HOTSG.
Research on Transient Analysis Method Based on 3D Neutronic/Thermal-Hydraulic Coupling Calculation.
Thermal Analysis on Accident Conditions of Spent Fuel Transport Containers.
Study of Industrial Steam Supply on PWR Nuclear Power Plant Safety Analysis.
Theoretical Model and Verification of OTSG Coupled Heat Transfer.
Research on Significant Isotopes Selection of Postulated Siting Accident.
Prediction of Electromagnetic Shielding Effectiveness of DCS Cabinet Based on LS-SVM.
Research on the Design of Nuclear Safety-Class DCS Maintenance Test Platform.
Research on Decoupling and Isolation Design of Nuclear Safety-Class DCS.
A Design for Expanding Non-safety DCS Server Based on Microservices in Nuclear Power Plants.
Research on Data Classification and Grading of Inherent Safety in Nuclear Power DCS Platform.
Research on Digital Requirements Management for Nuclear Safety-Class DCS System Design.
Comparative Analysis and Research on Fire Distribution Design of Nuclear Power Plants and Civil Buildings.
Research and Design of RS Signal Module’s K3 Qualification for RPR System in Nuclear Power Station.
Fault Diagnosis Expert System for Medium Voltage Three-Phase Asynchronous Motors Based on Fuzzy Neural Nets.
A New Fault Diagnosis Method for Reactor System Based on WT-PCA-SDG.
Author Index