11280nam 2200505 450 991056469480332120231110233405.0981-19-1181-9(MiAaPQ)EBC6954903(Au-PeEL)EBL6954903(CKB)21536299100041(PPN)262168294(EXLCZ)992153629910004120221120d2022 uy 0engurcnu||||||||txtrdacontentcrdamediacrrdacarrierNuclear power plants innovative technologies for, innovative technologies for instrumentation and control systems, the Sixth International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant (ISNPP) /edited by Yang Xu [and five others]Singapore :Springer,[2022]©20221 online resource (691 pages)Lecture Notes in Electrical Engineering ;v.883Print version: Xu, Yang Nuclear Power Plants: Innovative Technologies for Instrumentation and Control Systems Singapore : Springer,c2022 9789811911804 Intro -- Contents -- Two-Warehouse Inventory Models: Considering Lead Time and Continuous Review -- 1 Introduction -- 2 Notations and Assumptions -- 3 Mathematical Formulation -- 3.1 Model with constant lead time -- 3.2 The Proof Was Over -- 3.3 Model with Continuous Stochastic Lead Time -- 3.4 Model With Discrete Stochastic Lead Time -- 4 Numerical Examples -- 5 Conclusion -- References -- Cause Analysis and Improvement of Abnormal Triggering Event in Radiation Monitoring Channel of NPP -- 1 Introduction -- 2 Channel Introduction -- 3 Fault Process -- 4 Treatment Process -- 5 Cause Analysis -- 5.1 Channel Composition and Principle -- 5.2 Cause Analysis -- 6 Treatment Measures -- 6.1 Signal Circuit -- 6.2 Signal Transmission Mode -- 6.3 Drag Chain Cable -- 7 Conclusion -- References -- Discussion on Hydrogen Economy Solution Under Carbon Peak and Neutrality Background -- 1 Introduction -- 2 Development of Nuclear Power, Wind Power and Photoelectric Industry in China and America -- 3 Development of Hydrogen Energy Industry and Power Generation Costs -- 4 Current Status of Hydrogen Fuel Gas Turbine and Related Technologies -- 4.1 Physical Characteristics of Hydrogen Fuel -- 4.2 Current Status of Hydrogen Fuel Gas Turbine Technology -- 5 Analysis of Electric-Hydrogen-Electric Power Generation -- 6 Conclusion -- References -- Introduction of Network Architecture for Real-Time Information Management System in Nuclear Power Plant -- 1 Introduction -- 2 Network Architecture of Real-Time Information Management System -- 2.1 Classification of Cyber Security in Nuclear Power Plants -- 2.2 DCS OPC Interface -- 2.3 Proposed Network Architecture -- 3 Introduction for Multi-Control System Interface -- 4 Conclusion -- References -- Seismic Analysis and Qualification of Nuclear Safety Axial Flow Fan -- 1 Preface -- 2 Finite Element Model.3 Load Combination and Evaluation Criteria -- 4 Analysis -- 4.1 Modal Analysis -- 4.2 Seismic Safety Analysis -- 5 Result Evaluation -- 5.1 Shell and Plate Department -- 5.2 Impeller -- 5.3 Bolt -- 5.4 Operability -- 6 Conclusion -- References -- Application Verification of Wireless Sensor Network in Nuclear Power Plant -- 1 Introduction -- 2 Wireless Sensor Network Structure Design -- 2.1 Wireless Sensor Network System Framework -- 2.2 Wireless Sensors and Gateways -- 3 Test Verification -- 3.1 Functional and Performance Test -- 3.2 Environmental Test -- 3.3 Field Bench Test -- 4 Conclusion -- References -- Treatment of Flashing Primary Alarm of Scintillator Radiation Monitoring Device in NPP -- 1 Introduction -- 2 Principle of Detector and Main Functions of Equipment -- 2.1 Principle of Scintillator Detection -- 2.2 Major Function -- 3 Failure Mode Analysis -- 3.1 High Real Radioactivity -- 3.2 Equipment Collision -- 3.3 External Interference -- 3.4 Circuit Occasional Failure -- 3.5 Device Performance Degradation -- 3.6 Failure Mode Judgment -- 4 Data Analysis and Follow-Up Measures -- 4.1 Historical Events and Underlying Data Analysis -- 4.2 Four Point Two Inspection of Equipment Installation Site -- 4.3 Conclusion and Follow-Up Measures -- References -- Research on Cyber Security Standards of Nuclear Power Industry Control System -- 1 Introduction -- 2 American Standard -- 2.1 Federal Standards -- 2.2 NRC Standards -- 3 International Standards -- 4 Chinese Standards -- 4.1 Security Standards Related to SAC/TC 260 -- 4.2 Security Standards Related to SAC/TC 124 -- 4.3 Security Standards Related to SAC/TC 30 -- 5 Conclusions and Suggestions -- References -- Analysis and Treatment of Accidental Drop of Shutdown Bank -- 1 Introduction -- 1.1 A Brief Introduction -- 1.2 Introduction to Rod Cluster Control Assembly -- 2 Background Description.3 Incident Analysis -- 3.1 Cause Analysis of Accidental Drop -- 3.2 Plant Safety Analysis -- 3.3 Common Cause Failure Analysis -- 3.4 Full Scope Simulator Verification Analysis -- 3.5 Functional Analysis of Rod Drop -- 4 Problem Handling -- 5 Conclusion -- References -- The Software Modeling and Sensitivity Study of Computer Based I&amp -- C System in Probabilistic Safety Assessment of Nuclear Power Plant -- 1 Introduction -- 2 Method for Software Modelling -- 2.1 Failure Mode of Software -- 2.2 System Reliability Capability -- 2.3 Cut-off Value Modeling for Software -- 3 Method for Sensitivity Study of Software -- 3.1 Sensitivity Study Modelling -- 3.2 The Selection Sensitivity Study Value -- 4 Case Study for Software Modeling and Sensitivity Study -- 4.1 Configuration of Typical I&amp -- C Function in NPP -- 4.2 The Model of Typical I&amp -- C Function -- 4.3 The Analysis Result of Case Study -- 5 Conclusion -- References -- Research on Sensitivity of Axial Inductive Displacement Sensors with Constant Flux for Magnetic Bearings -- 1 Introduction -- 2 Working Principle of Axial Displacement Sensor with Constant Flux -- 3 The Influence of Mechanical Parameters on the Sensitivity -- 3.1 Theoretical Derivation -- 3.2 Simulation Result -- 3.3 Experiment Result -- 4 The Influence of Electrical Parameters on the Sensitivity -- 4.1 Theoretical Derivation -- 4.2 Experiment Result -- 5 Conclusions -- References -- A Primary Review on Team Performance in Automated Systems -- 1 Introduction -- 2 Issues Introduced by Automation -- 2.1 Use, Misuse, Disuse, and Abuse of Automation -- 2.2 Trust and Complacency -- 2.3 Levels of Automation and Related Models -- 3 Team and Automation -- 3.1 Models on Team Performance -- 3.2 Team Process and Performance Measurement -- 4 Team-Automation Model -- 5 Conclusions -- References.Economic Analysis of PROFIBUS Fieldbus Control System in Conventional Island of Nuclear Power Plant -- 1 Introduction -- 2 Fieldbus Application Strategy for Conventional Island in Nuclear Power Plants -- 3 Structure of the Fieldbus Control System -- 4 Economic Analysis of FCS System in the Partial Application Stage of Conventional Island -- 4.1 Description of System Configuration -- 4.2 Economic Analysis -- 5 Economic Analysis of FCS System in the Full Application Stage of Conventional Island -- 5.1 Description of System Configuration -- 5.2 Economic Analysis -- 6 Conclusion -- References -- Reliability Analysis of Tripping Solenoid Valve Power System Based on Dynamic Fault Tree and Sequential Monte Carlo -- 1 Introduction -- 2 Structure and Failure Principle of Trip System -- 2.1 System Structure and Failure Principle -- 2.2 Improvement Plan -- 3 Reliability Models of Various Distribution Schemes -- 3.1 Reliability Model Based on Dynamic Fault Tree -- 3.2 Monte Carlo Simulation -- 4 Reliability Analysis -- 5 Conclusion -- References -- Troubleshooting of Frequent False Alarms on Low-Low Speed of the Main Pump in Nuclear Power Plants -- 1 Introduction -- 2 Theory for the Main Pump Speed Measuring -- 3 Troubleshooting of Frequent False Alarms on Low-Low Speed of the Main Pump -- 3.1 Parameter Optimization of Speed Conditioning Modules -- 3.2 Software and Hardware Optimization -- 4 Conclusion -- References -- Research on Switch Signal Transmission System Based on Optical Fiber -- 1 Introduction -- 2 System Design -- 2.1 Multi-channel System Design -- 2.2 Dual-Channel System Design -- 3 Prototype Manufacturing and Integration -- 4 Functional Performance and Environmental Test -- 4.1 Multi-channel Prototype Transmission Function and Self-checking Function Test -- 4.2 Frequency Response Range Test of Multi-channel Prototype.4.3 Transmission Delay Test of Multi-channel Prototype -- 4.4 Reliability Test of Multi-channel Prototype -- 4.5 High-Low Temperature and Temperature Difference Test of Multi-channel Prototype -- 5 Anti-radiation Analysis of Optical Cable -- 6 Conclusion -- References -- Research on Transient Control Performance Improvement of Complex Control System in Nuclear Power Plant -- 1 Introduction -- 2 Causes and Phenomena of Insufficient Transient Performance in NPP -- 2.1 Failure of Level Control in Moisture Separator -- 2.2 Failure of Level Control System in Deaerator (ADG) -- 3 Transient Control Performance Optimization Method -- 4 Transient Control Performance Optimization Effect -- 4.1 Optimization Analysis of Moisture Separator Reheater -- 4.2 Optimization Analysis of Deaerator Level -- 4.3 Results Analysis -- 5 Conclusion -- References -- Analysis of the Influence of Decision Module Performance on Transient Events in Steam Generator Level Control -- 1 Introduction -- 2 Steam Generator Level Control System -- 2.1 Main Water Control and Bypass Feed Water Control -- 2.2 Feed Water Pump Speed Control -- 3 Decision Module Function Introduction -- 3.1 Function Introduction of Two-Input Decision Module VOT2 -- 3.2 Function Introduction of Three-Input Decision Module VOT3 -- 3.3 Common Configuration Structure of Decision Module and Controller -- 4 Application of Decision Module and Transient Event -- 4.1 Transient of Level Approaching Trip Value by Decision Failure -- 4.2 Transient of Unexpected Reactor Trip Transient by Decision Failure -- 4.3 Analysis of Transient Events -- 5 Optimization of Decision Module According to Transient Response -- 6 Conclusions -- References -- Research on Fault Diagnosis Method of Bus Type Intelligent Electric Valve in Nuclear Power Plant -- 1 Introduction -- 2 Failure Modes and Causes Analysis of Electric Valve.3 Signal Acquisition of Bus Type Electric Valve.Lecture Notes in Electrical Engineering Nuclear power plantsSafety measuresNuclear power plantsInstrumentsNuclear power plantsSafety measures.Nuclear power plantsInstruments.621.483Xu YangMiAaPQMiAaPQMiAaPQBOOK9910564694803321Nuclear Power Plants2035373UNINA