Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3 : PBNC 2022, 1 - 4 November, Beijing & Chengdu, China

This is the third in a series of three volumes of proceedings of the 23rd Pacific Basin Nuclear Conference (PBNC 2022) which was held by Chinese Nuclear Society. As one in the most important and influential conference series of nuclear science and technology, the 23rd PBNC was held in Beijing and Chengdu, China in 2022 with the theme “Nuclear Innovation for Zero-carbon Future”. For taking solid steps toward the goals of achieving peak carbon emissions and carbon neutrality, future-oriented nuclear energy should be developed in an innovative way for meeting global energy demands and coordinating the deployment mechanism. It brought together outstanding nuclear scientists and technical experts, senior industry executives, senior government officials and international energy organization leaders from all across the world. The proceedings highlight the latest scientific, technological and industrial advances in Nuclear Safety and Security, Operations and Maintenance, New Builds, Waste Management, Spent Fuel, Decommissioning, Supply Capability and Quality Management, Fuel Cycles, Digital Reactor and New Technology, Innovative Reactors and New Applications, Irradiation Effects, Public Acceptance and Education, Economics, Medical and Biological Applications, and also the student program that intends to raise students’ awareness in fully engaging in this career and keep them updated on the current situation and future trends. These proceedings are not only a good summary of the new developments nuclear science and technology, but also a useful guideline for the researchers, engineers and graduate students. Acknowledgement Contents Contributors On the Issues for Legislation of Spent Fuel in China 1 Introduction to the Current Administration and Legislation of Spent Fuel in China 2 The Deficiencies of Current Legislation for the Administration of Spent Fuel 2.1 The Regulation on the Administration of Spent Fuel Has not Yet Been Established 2.2 The Ownership of Spent Fuel and Its Reprocessing Products Are Still Undefined 2.3 It Lacks a Value Preservation and Appreciation Mechanism for Spent Fuel Fund 2.4 The Role of Public Influenced Is not of Enough Significance in the Whole Process of Spent Fuel Management 3 Suggestions to Improve the Legal System of Spent Fuel in China 3.1 Draft and Enact the Regulation on the Administration of Spent Fuel 3.2 Define the Ownership of Spent Fuel and Its Reprocessing Products Explicitly 3.3 Establish a Value Preservation and Appreciation Mechanism for Spent Fuel Fund 3.4 Give Full Attention to the Influenced Public in the Whole Management Process of Spent Fuel 4 Conclusions References Identification and Investigation on Thermal Hydraulic Phenomena Related to Core Make-Up Tank 1 Introduction 2 CMT Design and Function Overview 3 Phenomenon Identification Based on CMT Overall Effect Test 4 Analysis of Thermal Hydraulic Phenomena in CMT 5 Summary and Suggestions on Thermal Hydraylic Phenomena Related to CMT References Alara Methodology for Reactor Building Shielding Design in HPR1000 PWR 1 Introduction 2 Review of In-Service Reactor Building Shielding Design 3 ALARA Methodology of Reactor Building Shielding Design 3.1 Overall Review 3.2 Specific Analysis 3.3 Evaluation Review 4 Application of ALARA Methodology for Reactor Building Shielding Design 4.1 Overall Review 4.2 Specific Analysis 4.3 Evaluation Review 5 Conclusion References The Study of Shielding Benchmark of Heating Exchanger for Operating NPP 1 Introduction 2 Development of Shielding Benchmark 3 Methodology of Shielding Benchmark Establishment 3.1 Introduction of Simulation Software 3.2 Establishment Process of Shielding Benchmark 4 Establishment of Heating Exchanger Shielding Benchmark 4.1 Measurement of Source Term and Effective Dose Rate 4.2 Modeling of Shielding Benchmark 4.3 Shielding Benchmark Establishment and Validation 5 Conclusion References An Anisotropic Porous Model for Heat Exchanger Modeling of Fluoride-Salt-Cooled High-Temperature Advanced Reactor -- FuSTAR 1 Introduction 2 Methodologies 2.1 Mathematical and Physical Model 2.2 Description of Calculation Case 3 Results and Discussion 3.1 Comparison of 2D Shear Flow Case 3.2 Comparison of Anisotropic Flow in PCHE 4 Conclusions References Study on the Prediction of Critical Heat Flux in Uniformly Heated Round Tube by Multilayer Perceptron 1 Introduction 2 MLP Model 3 Training Dataset 3.1 Experiment Data 3.2 Data Processing 4 Training and Inference 4.1 Uniform MLP 4.2 Un-Uniform MLP 5 Conclusions References Neutronics and Thermal-Hydraulics Coupling Analysis of Integral Inherently Safe Fluoride-Salt-Cooled High-Temperature Advanced Reactor - Fustar 1 Introduction 2 Layout oF FuSTAR 3 Coupling Scheme and Mathematics 3.1 The Coupling Scheme 3.2 Mathematical Model and Pressure-Drop Correlation 4 CFD Modeling and Coupling Analysis 4.1 CFD Modeling 4.2 Coupling Analysis 5 Conclusions References Application of Light Curtain Test Technology in Dynamic Deformation Test of Rotating Machinery Rotor 1 Introduction 2 Overview of Light Curtain Test Device 3 Light Curtain Sensor Error Confirmation 4 Analysis of Test Results 4.1 Analysis of Radial Deformation Test Results 4.2 Axial Deformation Data Analysis 4.3 Measurement Uncertainty 4.4 Comparison Between Test Results and Numerical Calculation Results 5 Conclusions Reference Influence of Social Responsibility of Nuclear Power Companies on Public Acceptance 1 Introduction 2 Materials and Methods 2.1 Scales 2.2 Subjects 2.3 Reliability and Validity Analysis 3 Results and Discussion 3.1 Common Method Deviation Test 3.2 Correlation Analysis 3.3 Mediating Effect Test 3.4 Results 4 Additional Experiment 4.1 Experiment Design 4.2 Experiment Results 5 Discussion 6 Conclusion Appendix References Local Correlation and NpNn Linearity of Nuclear Electric Moments 1 Introduction 2 Local Correlation of Electric Moments 3 Linear Evolution of Electric Moment in NpNn Logarithmic Coordinates 4 Conclusions References Research on Financial Risk Analysis of Nuclear Power Project Based on Monte Carlo Simulation 1 Introduction 2 Introduction to Monte Carlo Simulation 3 Financial Risk Analysis Model of Nuclear Power Project Based on Monte Carlo Simulation 4 Case Analysis 5 Conclusions References Research on Low Carbon and Energy Saving Technology Path of Nuclear Power HVAC System 1 Introduction 2 Cooling Heat Recovery 3 Hot and Cold Air Distribution 4 Cold Storage 5 Conclusion References Multi-objective Optimization Design of Plate Heat Exchanger for Spent Fuel Pool Cooling System 1 Introduction 2 The Establishment of Evaluation Model for Heat Exchanger 2.1 Establishment of Mathematical Model of Heat Exchanger 2.2 Investment Cost Calculation Model 2.3 Establishment of Evaluation Model Program 2.4 Validation of Evaluation Model Procedures 3 Optimization Algorithm Program 4 Optimization Example and Result Analysis 4.1 Selection of Optimization Variables 4.2 Optimization Results and Analysis 4.3 Sensitivity Analysis 4.4 Selection and Analysis of Optimization Scheme 5 Conclusion References Fuel Economy Analysis of ATF Assembly with SiC Cladding and UO2(BeO) Pellets in CPR1000 1 Introduction 2 Model and Calculation Method 3 Design Criteria and Method 3.1 Design Criteria 3.2 Method 4 Fuel Management Design 4.1 Design of Benchmark Loading Pattern with M5 AFA3G Fuel 4.2 Design of the ATF Core 4.3 Fuel Management Calculation Results 5 Fuel Management Economy Analysis 5.1 Batch Discharging Burn-Up Analysis 5.2 Analysis of Uranium Consumption 5.3 Annual Consumption Assemblies Assessment 6 Summary 7 Conclusion References Thermodynamic Analysis and Optimization of Nuclear Closed Air Brayton Cycle 1 Introduction 2 Methodology 3 Results and Discussion 4 Conclusion References Affecting Factors and Aspects for Improving Customized Nuclear Public Acceptance Strategies 1 Characteristics of Public Perception in the International Nuclear Power 1.1 Categories of Nuclear Power Markets Worldwide 1.2 Characteristic of Public Perception in Developed Countries 1.3 Characteristic of Public Perception in Nuclear Emerging Countries 2 Good Practices and Strategies for Improving Public Acceptance 2.1 Focus on the Analysis of Energy Transformation to Enhance the Public's Rational Understanding of Nuclear Energy 2.2 Focus on Improvement of Nuclear Legislation and Consolidation on the Responsibilities of All Stakeholders 3 Enhancement of Technology and Management to Ensure Steady and Sustainable Development of Nuclear Energy 4 Promotion of Education and Diversification of Communication Channels 5 Conclusion References Initial Response Study of Nuclear Power Plant Operations After Local COVID-19 Outbreak 1 Unit Safety Control 1.1 Operations Scheduling Adjustment 1.2 Operations Plan Adjustment 1.3 Operations Risk Control 1.4 Unit Defects Assessment 1.5 Production Material Guarantee 2 Personnel Safety Guarantee 2.1 Arrival of Key Personnel 2.2 The Arrival of the Personnel in the Secondary Key Positions 2.3 Alternate Shift Arrangements 2.4 All Staff Was Screened for Covid-19 3 NPP Site Partition Control 3.1 NPP Site Partition Control 3.2 Operators Stay in the Dormitory for Shift Personnel 3.3 Closed Management for Shift Personnel at Work 4 Refined and Graded Management of Epidemic Prevention and Control 5 Conclusion References Discussion on Nuclear Arms Control Based on the International Situation in 2022 1 Introduction 2 Analysis of International Nuclear Arms Control 2.1 Introduction of International Situation of Nuclear Arms Control 2.2 Analysis of International Situation of Nuclear Arms Control 3 Some Current Research in Nuclear Arms Control 4 Conclusions References SNSTC’s Capabilities and Practices on Performance Testing for Nuclear Security System and Equipment 1 Introduction 2 Testing Methods and Industry Standards 3 Testing of RPMs 4 Coordinated Research Projects of IAEA 5 Summary Practical Analysis of Radon Protection Methods in an Underground Project 1 Harm Caused by Radon 2 Effect Analysis of Three Common Radon Protection Measures 2.1 Ventilation 2.2 Shield 2.3 Adsorption 3 Conclusions References Numerical Calculation of Flow Heat Transfer in a Single Square Tube Under a Blockage Accident 1 Introduction 2 Numerical Methods 2.1 Basic Parameters 2.2 Geometrical Model 2.3 Blockage Simulation Method 2.4 Method Mesh Sensitivity Analysis and Fully Develop Turbulence Test 3 Results and Discussion 3.1 Blockage Material 3.2 Blockage Thickness 3.3 Blockage Area Proportion 3.4 Blockage Shape 4 Conclusion References Research on the Siting Problem of Economy-Oriented Small Heating Nuclear Reactor Based on System Dynamics 1 Introduction 2 Literature Review 3 Methodology 3.1 Model Method and Assumptions 3.2 General Form of EOSSD Model 4 Empirical Analysis 4.1 The Problem of Location Selection When the Rate Is Linear 4.2 The Problem of Location Selection When the Rate Is Non-linear 5 Conclusions References Technical and Economic Analysis of Nuclear Heating Based on HPR1000 1 Introduction 2 Potential Market Analysis 3 Technical Feasibility 3.1 Site Layout Requirements 3.2 Heating Scheme 3.3 Feasibility Analysis of Key Technologies 3.4 Environmental Safety Impacts 4 Economic Analysis 4.1 Economic Analysis of the Heating Scheme 4.2 Economic Analysis of Steam Supply Scheme 4.3 Brief Summary 5 Conclusions References The Application of Renal Dynamic Imaging in Measuring Renal Function of En-Bloc Pediatric Kidneys Transplanted into Recipients 1 Introduction 2 Materials and Methods 2.1 Patients 2.2 99mTc-DTPA-based Renal Dynamic Imaging (GATE’s Method) 2.3 Estimated Glomerular Filtration Rate (eGFR) 2.4 Kidney Transplant Biopsy 3 Statistical Analysis 4 Results 4.1 Subject Characteristics 4.2 Correlation Analysis 4.3 Comparison of Main Indexes and Renal Function Early and Late After Transplantation 4.4 Renal Function Assessed by Serum Creatinine and gGFR 4.5 Impact of the Occurrence of Complications and Kidney Biopsy on Renal Function 5 Discussion 6 Conclusions References Study of Cost Index System for Nuclear Power Plant 1 Introduction 2 Cost Index System for General Design 2.1 Guidelines of Establishing the List of Cost Accounts 2.2 Guidelines of Calculating the Unit Cost of Accounts 2.3 Guidelines of Establishing Major Equipments and Materials Index 3 Conclusion and Future Work References Application of Intelligent Innovation in Accident Procedure of Nuclear Power Plant 1 Introduction 2 Accident Procedure of Nuclear Power Plant 3 Intelligent Requirements for Accident Procedures 4 System Structure 4.1 System Hardware Structure 4.2 System Software 5 System Running 6 Feedback 7 Conclusion References Experimental Study on Thermal-Hydraulic Characteristics of Air Heat Exchanger for Sodium Cooled Fast Reactor 1 Introduction 2 Theoretical Calculation Method 3 Experimental Device 4 Experimental Research and Result Analysis 4.1 Experimental Content and Experimental Conditions 4.2 Data Processing 4.3 Experimental Results and Analysis 5 Conclusion References Effect of Coating Temperature on Microstructure and Properties of the SiC Layer in TRISO-Coated Particles 1 Introduction 2 Experimental Procedure 2.1 Preparation of TRISO-Coated Particles 2.2 Characterization Methods 3 Results and Discussion 3.1 Microscopic Structures and Densities 3.2 Mechanical Properties 4 Conclusions References An Improved Super-Resolution Model for Bubble Feature Extraction Process 1 Introduction 2 Related Work 3 Architecture Specification 3.1 High-Order Degradation Model 3.2 Gradient Map Loss 3.3 Generator Architecture 4 Experiment 4.1 Datasets and Evaluation Metrics 4.2 Training Details 4.3 Qualitative Results 4.4 Preprocessing Process of 2D Bubble Images 4.5 Contour Extraction Results 5 Conclusion References Analysis of Current Status and Development Trend of Nuclear District Heating 1 Introduction 2 Development Status and Trend of Central Heating in China 3 Nuclear Heating Faces Major Opportunities 3.1 China Supports Nuclear Heating 3.2 Rapid Development of Urban Central Heating Area 3.3 China Has Good Nuclear Heating Practice 4 Overview of Nuclear Heating 4.1 Single Nuclear Heating Mode 4.2 Cogeneration Heating Mode 5 Advantages and Industrialization Promotion of Nuclear Heating 5.1 Good Environmental Benefits 5.2 Nuclear Heating is Economically Competitive 5.3 Promotion and Trend Analysis of Nuclear Heating Industrialization 6 Problems in the Development of Nuclear Heating 7 Conclusion Research on High-Speed Cold Cutting Technology for Combined Spider 1 Introduction 2 Research Subjects 2.1 Combined Spider 2.2 Choice of Precision Cold Cutting Technology 3 Research Results 3.1 Test Conditions 3.2 Water Jet Scheme and Part Design 3.3 Water Jet Surface Quality Tests 3.4 Brazing Performance Test of Water Jet Surface 3.5 Water Jet Process Parameters 3.6 Water Jet Accuracy Control 3.7 Results of Small Batch Cutting Studies 4 Conclusions References Research and Development Practice of Equipment Condition Monitoring and Intelligent Diagnosis Platform Based on Big Data and AI at TNPS 1 Introduction 2 Typical Algorithms 3 Overall Architecture 4 Functional Structure 5 Typical Functions 6 Conclusion References Study on the Design Standard of Water-Intake Breakwaters in Coastal Nuclear Power Plants 1 Introduction 2 Provisions by Safety Guides and Codes 3 Determination of the Design Standard 4 Engineering Example 5 Conclusions References A Study of Stability and Coagulation Behavior of Broth Based the Internal Gelation Process for Uranium Dioxide Microspheres 1 Introduction 2 Experiment 3 Results and Discussion 3.1 The Effect of the Preparation and Storage Temperature on the Stability of the Broth 3.2 Analysis of Causes of Broth Solidification 3.3 The Effect of Urea/U on the Stability of the Broth 3.4 Analysis of Post-treatment of Scrapped Broth 4 Conclusions References The Preliminary Thermo-hydraulics Calculation of Unfolding Process of the Lotus Reactor 1 Introduction 2 Modelling and Methodology 2.1 Tools 2.2 Overset Mesh 2.3 Subcooled Boiling 2.4 Modeling 3 Results and Discussion 3.1 Steady-State Simulation 3.2 Transient Simulation 4 Conclusion References Key Technology of a New Potential Economical Desalination Method for Small Nuclear Power 1 Introduction 2 Methodology 2.1 Expert Knowledge and Comparative Analysis 2.2 Hydrate Equilibrium Prediction 3 Result and Discussion 4 Conclusions References Research on On-Line Measurement Technology of Fuel Rod Deformation Based on LVDT 1 Introduction 2 Methods and Principles 3 Results and Discussion 4 Conclusion References Numerical Study on Flow Distribution Characteristics of Parallel Square Flow Channels Under Blockage 1 Introduction 2 Numerical Methods 2.1 Geometrical Model 2.2 Mesh Sensitivity Analysis and Fully Develop Turbulence Test 3 Results and Discussion 3.1 Inlet Header Sizes 3.2 Different Blockage Location 3.3 Different Blockage Ratio at the Inlet 3.4 Maximum Wall Temperature 4 Conclusion References Computer Package for Calculating the Fast-Neutron Fluence in Reactor Pit Based on the Reactor Operational History and the Monte-Carlo Method 1 Introduction 2 Calculation Mothod and Models 2.1 Calculation Process 2.2 Input Data Preprocessing 3 Verification 4 Conclusion References Research on Classification and Coding of Nuclear Power Plant Status Reports Based on Machine Learning 1 Introduction 2 Classification and Coding System for Nuclear Power Plant Status Reports 3 Experiments and Analysis of Results 3.1 Experimental Preparation 3.2 Classification Model Evaluation Indicators 3.3 The Effect of Training Set Sample Size on Model Classification Performance 3.4 The Effect of Learning Objects on Model Classification Performance 3.5 The Effect of Word Segmentation Mode on Model Classification Performance 4 Conclusions References Atomic Scale Simulation on Liquid Metal Embrittlement Induced by Segregation of Lead Element in Lead-Cooled Fast Reactor 1 Introduction 2 Simulation Methods 3 Results and Discussion 3.1 Results for PB Segregation 3.2 Results for Uniaxial Tensile Loading Test 3.3 Effects of Pb Segregation on the Mechanical Properties of Ferritic Steels 4 Conclusion References Application of Construction Phase Process Cost Management in Nuclear Power Projects 1 Introduction 2 Overview of Construction Process Cost Control Methods 3 On-Budget Cost Management 4 Off-Budget Expense Management 5 Conclusion References Characterization of Residual Uranium Resources in the Decommissioned Final Mining Area of a Uranium Deposit in Xinjiang 1 Introduction 1.1 A Subsection Sample 2 Research Background 2.1 Hydrogeological Setting of the Deposit 2.2 Production History and Problems 3 Characterization and Analysis of Uranium Resources in the Target Mining Area Zxcvbnm 3.1 Selection of Target Area and Drilling 3.2 Analysis of the Distribution of Residual Uranium Resources 3.3 The Validity Analysis of Logging Curves 4 Secondary Development Potential Analysis 5 Conclusion References Study on Influence of Process Parameters on Image Quality in X-ray Digital Radiography Inspection of Fuel Rod Weld 1 Introduction 2 Process Experiment 2.1 Equipment of Experiment 2.2 Process Experiment 2.3 Indicators of Evaluation 3 Results and Discussion 3.1 The Multi-index Comprehensive Balance Analysis 3.2 Range Analysis 3.3 The Variance Analysis 3.4 Analysis of the Influence of Factors on Image Quality 4 Verification Experiment 5 Conclusions References Construction of CDS/TIO2/HGS Composite Materials and Photocatalytic Reduction of Hexavalent Uranium in Wastewater 1 Introduction 2 Experimental 2.1 Materials 2.2 Catalysts Preparation 2.3 Characterization 2.4 Photocatalysis Activity 3 Results and Discussion 3.1 Characterization of Materials 3.2 Photocatalysis Test 3.3 Mechanism of Photocatalytic Reduction 4 Conclusions References Experimental Study on Shell Side Flow Distribution of Fast Reactor Steam Generator 1 Introduction 2 Experimental Set-Up 3 LDV Measuring Device and Measuring Point Layout 3.1 LDV Measuring Device 3.2 Layout of Measuring Points 4 Test Results and Analysis 4.1 Results of Cross Flow Velocity in Tube Bundle Area 4.2 Results of Axial Flow Velocity in Tube Bundle Area 4.3 Results of Three-Dimensional Velocity Distribution at the Outlet of Porous Ring Plate 5 Conclusions References Vibration Analysis of Heating-Used Steam Extraction Pipelines in Nuclear Power Plant 1 Introduction 1.1 A Subsection Sample 2 Two-Phase Flow Induced Vibration in the Extraction Pipeline 3 Extraction Piping Vibration Monitoring 3.1 Layout of Monitoring Points 3.2 Monitoring Result 4 Analysis 4.1 Model Analysis 4.2 Exciting Sources 4.3 Drainage 5 Conclusions and Future Perspectives References Experimental Study on Aerosol Removal Effected by Spray Characterization 1 Introduction 2 Experimental Apparatus 2.1 Overview of the Facility 2.2 Experimental Parameters 3 Experimental Results 3.1 Spray Droplet Size Distribution 3.2 Aerosol Global Removal Efficiency 4 Aerosol Removal Model 4.1 Equation of Droplets Motion 4.2 Improved Aerosol Removal Model 4.3 Removal Efficiency of Mechanical Mechanisms 5 Conclusions References Study on Public Acceptance of Restart of Inland Nuclear Power Plants Based on TAM/TPB Integration Model 1 Introduction 2 Theoretical Framework and Research Hypotheses 2.1 Perceived Usefulness 2.2 Perceived Risk 2.3 Subjective Norms, Behavioral Attitudes, and Perceived Behavior Control 2.4 Trust 3 Research Methodology 3.1 Sample and Data Collection 3.2 Questionnaire Design and Variable Measurement 3.3 Reliability and Validity Tests 4 Data Analysis and Results 4.1 Measurement Model Test 4.2 Structural Model Test 5 Discussion 6 Conclusion and Policy Implications References Low Temperature Performance of LBE Oxygen Sensors with Different Reference Electrodes 1 Introduction 2 Experiment 3 Results and Discussions 3.1 Calculate of Theoretical E 3.2 Performance Test 4 Conclusion References The Development of the Combined Fission Matrix Theory in Burnup Calculation 1 Introduction 2 Method 2.1 Model 2.2 Fission Matrix Theory 2.3 Fission Matrix Combination Method 2.4 Correct Ratio 2.5 Fission Matrix Database 3 Result 4 Conclusion References Study of the Electric Device of RRI019/020VN in Qinshan Nuclear Power Plant Cannot Close Completely in Long Signal Valve Closing 1 RRI019/020VN Operation 2 Introduction of Valve Electric Device Control Mode 2.1 Limit Valve Closing Control 2.2 Torque Valve Closing Control 3 Troubleshooting Analysis of RRI019/020VN 4 Solution Analysis 5 Conclusion Reference Numerical Study of Influence of 15N Enrichment on Burnup Performances for a Heat Pipe Cooled Traveling Wave Reactor 1 Introduction 2 Core Design and Computational Tool 3 Results 3.1 Reactivity Analysis 3.2 Power Distribution and Burnup 3.3 Consumption and Breeding of Nuclear Fuel 4 Conclusions References Parallelization of Thermal Hydraulic Real-Time Simulation Program Based on Two-Phase Drift Flux Model 1 Introduction 2 Introduction and Performance Analysis THEATRe Program 2.1 Physical Model 2.2 Calculation Procedure 2.3 Hotspot Module of Serial THEATRe Program 3 Parallel Scheme 3.1 MPI Parallel Scheme 3.2 OpenMP Parallel Scheme 4 Effectiveness and Performance of Parallel THEATRe Code 4.1 Effectiveness of Parallel THEATRe Code 4.2 Performance of Parallel THEATRe Code 5 Conclusions References Simulation of Photon-Counting Detector Based on OpenModelica 1 Introduction 2 Method and Modeling 2.1 Introduction of OpenModelica 2.2 X-ray Tube 2.3 Semiconductor Detector 2.4 Preamplifier 2.5 Pulse Shaper 2.6 Pile-Up Rejection Circuit 2.7 Overall Structure 3 Results 3.1 Collection Efficiency 3.2 PREamplifier’s and Pulse SHAper’s Response 3.3 Test of Pile-Up Rejection Circuit 4 Conclusion References Research on Boiling and Coupled Heat Transfer of OTSG with Drift Flow Single Fluid Model 1 Introduction 2 Improved Drift Flow Single Fluid Model 2.1 Governing Equation 2.2 Slip Velocity Model 2.3 Interphase Mass Transfer Model 2.4 Flow Pattern Identification and Heat Transfer Model 3 Model Validation 3.1 Simulation Description 3.2 Result Analysis 4 Conclusions References Study on the Crystallization Rate of Uranium Peroxide Based on Ultrasound and Microchannel Technology 1 Introduction 2 Materials and Methods 2.1 Experiment Reagent 2.2 Experimental Facility 2.3 Determination Method of Nucleation Rate and Growth-Rate 2.4 Analytical Method 3 Results and Discussion 3.1 Effect of Ultrasonic Power on Nucleation Rate and Growth Rate of Uranium Peroxide Crystal in Tubular Process 3.2 Effect of Ultrasonic Power on Nucleation Rate and Growth Rate of Uranium Peroxide Crystal in Microchannel Process 3.3 Comparison of Crystallization Process Under Different Mixing Modes and Ultrasonic Power Conditions 4 Conclusion References Construction of Nuclear Emergency Awareness System Based on “Cloud-Edge-Terminal” 1 Introduction 2 Problems Existing in the Construction of Intelligent Nuclear Emergency 3 Edge Computing Technology 4 Intelligent Emergency Awareness Architecture of “CLoud-Edge-Terminal”collaboration 5 Conclusions References Sodium Spray Fire Analysis with Combustion Space Multi-node Model for Sodium-Cooled Fast Reactor 1 Introduction 2 Model 2.1 Droplet Combustion Model 2.2 Motion Model 2.3 Combustion Space Multi-nodes Model 3 Model Validation 3.1 FAUNA Experiments 3.2 SNL T3 Experiments 4 Conclusions References Analysis of Fission Product Diffusion Behavior of Fully Ceramic Micro-encapsulated Fuel 1 Introduction 2 Sensitivity Analysis of TRISO Particle Parameters 2.1 UO2 Kernel Diameter 2.2 Buffer Layer Thickness 2.3 IPyC Layer Thickness 2.4 SiC Layer Thickness 2.5 OPyC Layer Thickness 3 Sensitivity Analysis of SiC Matrix Parameters 3.1 Diffusion Coefficient of Fission Products in SiC Matrix 3.2 Fuel Pellet Diameter 3.3 Thickness of Fuel-Free Zone 4 Summary References Optimization of Sintering Parameters of Lead Oxide Particles for Solid Oxygen Control in Lead Cooled Fast Reactor 1 Introduction 2 Experimental 2.1 Material Preparation 2.2 Characterization Methods 3 Resulis and Discussion 3.1 Relative Density 3.2 Hardness 3.3 Flexural Strength 3.4 SEM Micrographs 3.5 Optimum Sintering Parameter 4 Conclusions References Research on Fission Products Selection in the Primary Coolant of PWR During Normal Operation 1 Introduction 2 Fission Products Selection Methodology 3 Radionuclides Selected 3.1 Generation Mechanisms 3.2 Selection Based on Radionuclides Half-Life and Activity Levels 3.3 Selection Based on RGP (Relevant Good Practice) 3.4 Insights from OPEX 3.5 Recognition of Technical Users ‘Needs’ 4 List of Selected Fission Products 5 Comparison 6 Conclusions References Development of a Depletion Code with a Control-Rod-Adjusting Program Based on OpenMC 1 Introduction 2 Development of Automatic Control-Rod-Adjusting Depletion Calculation Program 2.1 OpenMC Depletion Calculation Module 2.2 Development of Critical Control Rod Position Search 2.3 Development of Depletion Element Update and Physical Parameter Storage 2.4 Coupling of Critical Control Rod Position Search and Depletion 3 Verification and Applications 3.1 Verification Model 3.2 Critical Control Rod Position Update 3.3 Nuclear Data Storage 4 Conclusions References Study of Fine Particle Deposition of Porous Medium in Heat Pipe of Heat Pipe Reactor Under Gravity 1 Introduction 2 Research Subject 2.1 Geometric Models 2.2 Structure and Medium Parameters 2.3 Concentration Parameters 2.4 Grid-Independent Validation 3 Calculation Formula 3.1 Equation for the Flow of a Working Mass 3.2 Equation for Particle Movement 3.3 The Equation for Particle Deposition Volume Calculation 4 Calculation Results and Analysis 4.1 Calculation of Deposition Volume with Time and Concentration for Vertical Placement 4.2 Calculation of Deposition Volume with Time and Particle Concentration When Placed Horizontally 4.3 Comparative Calculation of Deposition in Different Cases of Heat Pipe Porous Medium 5 Conclusion References Recommendations to Improve the Public Acceptance of Nuclear Environmental Protection 1 Introduction 2 People’s Acceptance of Nuclear Environmental Protection 3 Recommendations 3.1 Enhance the Publicity of Nuclear 3.2 Strengthen the Education on Nuclear Environmental Protection 3.3 Promote Programs of Nuclear Environmental Protection 4 Conclusions References Coupled Neutronics and Thermal-Fluid Calculation for Prismatic High-Temperature Gas-Cooled Reactor Core at Steady State 1 Introduction 2 Method for Steady-State Neutronics and Thermal-Hydraulics Coupling of the Core 3 Moose-Based Development of Steady-State Neutronics and Thermal-Hydraulics Coupling Program 3.1 Development of the Core Neutron Diffusion Module 3.2 Development of the Core Thermal-Fluid Module 3.3 Multiapp Development 3.4 Data Exchange Between Modules 3.5 Two-Dimensional Cross-Section Interpolation Method 4 Calculation of MHTGR-350MW Benchmark 4.1 Three-Dimensional Coupling Model 4.2 Calculation Conditions 4.3 Calculation Results 5 Conclusion References Study on the Preparation of Metallographic Samples and the Characterization of Volume Content and Size Distribution of Inclusions in Uranium Metal 1 Introduction 2 Experiment 2.1 Experimental Program 2.2 Sample Preparation 3 Results and Analysis 3.1 Comparison of Different Metallographic Sample Preparation Methods for Inclusions Showing 3.2 Identification of Inclusions 3.3 Quantitative Metallographic Study on the Volume Fraction and Size Distribution of Inclusions 4 Conclusions References Development Background and Research Progress of UN-U3Si2 Composite Fuel 1 Introduction 2 Properties of UN, U3Si2 and UN-U3Si2 Composite Pellet 3 Research Progress of UN-U3Si2 Composite Fuel 4 Conclusions and Prospects References Study on Fabrication and Characterization of SiCf/SiC Composite Cladding 1 Introduction 2 Experimental Process 2.1 Preparation of Interface Layer 2.2 CVI Densification 2.3 Performance Characterization 3 Results and Analysis 3.1 Interface Layer 3.2 Micro-morphology and Structure 3.3 Density 3.4 Tensile Strength and Elongation 4 Conclusions References Life-Cycle Cost Study for a Near-Surface Disposal Repository of Low-Level Waste in China 1 Introduction 1.1 Background 1.2 Research Status 1.3 Research Aims and Significance 2 Life-Cycle Cost Components and Calculation Model for LLRW Disposal Repository in China 2.1 Construction Cost 2.2 Operating Costs 2.3 Closure Costs 3 Life-Cycle Cost of a LLRW Disposal Repository in China 3.1 Introduction 3.2 Calculated Boundaries 3.3 Cost Entries 4 Conclusion References Numerical Study on External Environmental Radiation of Nuclear Ramjet Reactor 1 Introduction 1.1 A Subsection Sample 2 System Description 3 Numerical Method 3.1 Mathematical Model 3.2 Modeling Method 4 Results and Discussion 4.1 Source Term Analysis 4.2 Radiation Analysis 5 Conclusion References Optimization on Design of Logic Degradation for Safety I&C System of Nuclear Power Plant 1 Introduction 2 The Safety I&C System of Nuclear Power Plant 3 Logic Degradation Design 4 Problems in Logic Degradation Design 4.1 Applicable Status/Condition Is Not Considered 4.2 The Influence of Unit Conditions on Measurement Is Not Considered 4.3 Degradation Logic Is Not Separated from the Shutdown Protection Logic 5 Improvement of the Logic Degradation 5.1 Coolant Pump Power 5.2 DNBR 5.3 Liquid Level of Pressurizer (Narrow Range) 5.4 Separation of Degradation Logic and Shutdown Protection Logic 6 Summary References Study on Gamma-Ray Spectra Feature Recognition and Isotope Composition Analysis of Plutonium Based on Convolutional Neural Networks 1 Introduction 2 Machine Learning and Convolutional Neural Network 3 Data Set