Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 1: PBNC 2022, 1 - 4 November, Beijing & Chengdu, China (Springer Proceedings in Physics, 283)

This is the first 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 in the field, but also a useful guideline for the researchers, engineers and graduate students. This is an open access book. Acknowledgment Contents Research on the Public Participation of Nuclear Safety Based on Social Psychology 1 Introduction 2 Relationship Between Public Participation in Nuclear Safety and Social Psychology 3 Current Situation and Problems of Public Participation in Nuclear Safety 3.1 Current Situation of Public Participation in Nuclear Safety in China 3.2 Problems of Public Participation in Nuclear Safety 4 Conclusions 4.1 Understand the Conformity Among Individuals 4.2 Apply Various Measures to Engage People from Different Groups to Improve the Effectiveness of Public Participation 4.3 Encourage Extensive Participation to Create Synergy 4.4 Step up International Cooperation to Promote Public Participation References Development Prospect and Application of Nuclear District Heating in China 1 Introduction 2 Development Status of Nuclear District Heating at Home and Abroad 3 Advantages of Nuclear District Heating 3.1 Technical Advantages 3.2 Environmental Protection Advantages 3.3 Energy Utilization Advantages 4 Problems and Solutions of Nuclear District Heating 4.1 Selection of Reactor Type Scheme 4.2 Construction of District Heating Network 4.3 Operation and Coupling of Nuclear Power Plant 4.4 Safety of Nuclear Power Plant 4.5 Economy of Nuclear Power Plant 5 Conclusions References Application of MC-MC Coupled Method in Neutron Shielding Analysis of Reactor Pit in Reactor Building 1 Introduction 2 Development of Neutron Shielding Design for Reactor Pit 2.1 Methodology Development of Neutron Shielding Analysis 2.2 Development of Neutron Shielding in Reactor Pit 3 Establishment of MC-MC Coupled Method 3.1 Process of MC-MC Coupled Method 3.2 Selection Principle of Continuation Surface 4 Application of MC-MC Coupled Method for Reactor Pit Shielding Design 4.1 Calculation Assumption and Modeling 4.2 Calculation Process and Result Analysis 5 Conclusion References Study on the Effects from Spacer Wires on Coolant Flow Within a Fuel Assembly Used in the CiADS Core 1 Introduction 2 Models and Methods 2.1 Geometric Model 2.2 Grid Division 2.3 Boundary Condition Setting 2.4 Coolant Thermal Physical Parameters and Turbulence Model 2.5 Grid Independence Analysis 2.6 Solver Validation 3 Results and Discussion 3.1 Pressure Distribution Characteristics 3.2 Velocity Distribution Characteristics 3.3 Temperature Distribution Characteristics 4 Conclusion References Research of Corrosion Products Migration Behavior in PWR Primary Circuit Under Extended Low Power Operation Mode 1 Introduction 2 Theoretical Model 2.1 Migration Model of Corrosion Products 2.2 Source Term Model 3 Calculation Results and Analysis 3.1 Analytical Methods 3.2 Migration of Corrosion Products 3.3 Distribution of Primary Loop Source Terms 4 Conclusions References Structure Design and Optimization of the Mass Flow Distribution Device of Downcomer for Fluoride-Salt-Cooled High-Temperature Advanced Reactor – FuSTAR 1 Introduction 2 Methodologies 2.1 Thermodynamic and Geometry Boundaries 2.2 Design and Optimization Method 3 Results and Discussion 3.1 Preliminary Analysis 3.2 Sensitivity Weakening and Structural Optimization 4 Conclusions References Study on the Influence of Stretch-Out Operation on the Deposition of Corrosion Products and Source Term Level in the Primary Circuit of Pressurized Water Reactor 1 Introduction 2 Theoretical Model 2.1 Hydrochemical Model 2.2 CRUD Deposition Model 2.3 Source Term Model 2.4 Mass Conservation of Corrosion Products in Primary Circuit 3 Calculation Results and Analysis 3.1 Input Parameters 3.2 Discussion on Calculation Results 4 Conclusion References Study and Resolution of Pressurizer Pressure Great Fluctuation Problem in CRP1000 RGL04 Test 1 Introduction 2 Description of RGL04 Test 3 The Problem of Pressurizer Pressure Greatly Fluctuation 4 Solution 4.1 Increasing System Pressure in Test 4.2 Decreasing Power Reduction Rate in Test 4.3 The Influence of Core Overheating 4.4 Strategy 5 Conclusion References Group Constants Generation Based on NECP-MCX Monte Carlo Code 1 Introduction 2 Methodology 2.1 Homogenization Method 2.2 Generation of Diffusion Coefficient 2.3 Leakage Correction 2.4 Assembly Discontinuous Factor 2.5 Overall Calculation Flow 3 Verification 3.1 Critical Boron Concentration 3.2 Isothermal Temperature Coefficient 3.3 Control Rod Bank Worth 4 Conclusion and Discussion References Preliminary Application of CT Technology in Non-destructive Testing of Nuclear Fuel Elements 1 Introduction 2 DR and CT Systems 2.1 Overview of DR Imaging System 2.2 CT Transformation 3 CT Imaging Experiments 3.1 CT Imaging and Artifacts 3.2 CT Imaging of Typical Work Piece 3.3 Key Factor Analysis of CT Imaging 4 Conclusions References The Investigation of Overpower ΔT Triggered Mechanism and Optimizing Strategy During Reactor Trip Experiment 1 Introduction 2 Reason Analysis of Triggering Overpower ΔT Protection Signal 3 Modeling the Physics Process of Reactor Trip Test 3.1 SMART Model 3.2 Detector Influence 3.3 Control Banks Drop Curve 4 Investigation on Influence Factors of ΔI Change in Reactor Trip Test 4.1 Initial Axial Power Distribution 4.2 R Bank Position 4.3 Influence of Burnup 5 Improvement Method 6 Conclusion References Analysis of Nuclear Power Economy and Its Influencing Factors 1 Introduction 2 The Connotation of Nuclear Power Economics 2.1 Scope of Nuclear Power Economic Evaluation 2.2 Nuclear Power Economic Evaluation Indicators 3 The State of Nuclear Power Economics 4 Factors Affecting the Economics of Nuclear Power 4.1 Overview of Influencing Factors 4.2 Analysis of Typical Influencing Factors on Internal Economy 4.3 External Cost and System Cost 5 Conclusions References Local- and Small-Scale Atmospheric Dispersion Modeling Towards Complex Terrain and Building Layout Scenario Using Micro-Swift-Spray 1 Introduction 2 Materials and Methods 2.1 MSS Modeling 2.2 Wind Tunnel Experiment 2.3 Model Parameter Settings 2.4 Statistical Evaluation Methodology 3 Results and Discussion 3.1 Wind Field 3.2 Concentration Field 4 Conclusions References Discussion on the Reporting of Nuclear Safety Incident from the Perspective of Media Ecology 1 Introduction 2 Relationship Between Nuclear Safety-Related Events (Accident) and Other Events (Accident) 2.1 Nuclear Safety Incident/Accident 2.2 Safety Incidents (Accidents) 2.3 Public Emergencies and Disasters 2.4 Potential Relationship Between Incidents (Accidents) 3 Media Ecology and Characteristics of Accident Reports in China 3.1 Media Ecology 3.2 Evolution of the Concept of Accident Reporting 3.3 Reporting Basis and Present Situation of Nuclear Safety Event 4 Examples of Nuclear Safety Incident Reports 5 Thinking 6 Conclusions References Economic Analysis of the One Through Fuel Cycle Based on Equilibrium Mass Flow 1 Introduction 2 Characteristics and Material Flow Analysis of Nuclear Fuel Cycle 2.1 One Through Fuel Cycle Feature 2.2 Equilibrium Material Flow Analysis 3 Calculation Results and Discussion 3.1 Levelized Cost Analysis 3.2 Sensitivity Analysis 4 Conclusions References Analysis of Fast Power Reduction System for CPR1000 Nuclear Power Plants 1 Introduction 2 Function Introduction 3 Rod-Drop Strategy 3.1 RCCA Re-group Mode 3.2 Rod-Drop Group Pre-selection 4 Nuclear Design Analysis 5 Normal Transients Analysis 6 Safety Analysis 7 Conclusion References Calculation and Analysis of Polonium-210 Source Term in Primary Coolant System of Lead-Bismuth Fast Reactor 1 Introduction 2 The Production of Polonium 3 Calculation 3.1 Model 3.2 Sample 3.3 Results Analysis 4 Conclusion References Study on Resuspension Models Based on Force Balance 1 Introduction 2 Models for Resuspension 3 Evaluation for Resuspension Models Application 3.1 Verification Experiments 3.2 Comparison with Experiments 3.3 Discussion 4 Conclusions References Application of BIM Technology in Nuclear Power Construction Schedule Management 1 Introduction 2 Nuclear Power Schedule Management Process Based on BIM Technology 3 Preparation of Technical Schedule Based on BIM 4 Progress Tracking and Control Based on BIM Technology 5 4D Display and Application 6 Conclusions References Research on Calculation Method and Additionality of Carbon Emission Reduction of Nuclear Energy Heating Based on Project Perspective 1 Introduction 2 Literature Review 3 Methodology 3.1 Nuclear Energy Carbon Emission Reduction Calculation Method 3.2 Key Points of Nuclear Additionality Demonstration 4 Emprical Results and Analysis 4.1 Case Study Regions and Data Sources 4.2 Carbon Emission Reduction Calculation Results 4.3 Carbon Emission Reduction Calculation Results 5 Conclusions References Effect of β-Phase Heat Treatment on Microstructure of Zr-Sn-Nb-Fe Alloy 1 Introduction 2 Experimental 3 Results and Discussion 3.1 Microstructure Analysis 3.2 Component and Structure Analysis 4 Conclusions References The Main Reason of SG Thermal Power Imbalance Between Each Loop in CPR1000 Nuclear Power Plants 1 Introduction 2 Root Cause Analysis 2.1 Measurement Factors 2.2 Actual Deviation 2.3 The Influence of Core Power Distribution on Hot Leg Temperature 3 Weight Sensitivity Analysis 4 Conclusion References Mechanical and Numerical Simulation Analysis for the Insertion Section Sampling of Irradiation Charpy Specimen Reconstitution 1 Introduction 2 Experimental Procedure and Materials 2.1 Experiment 2.2 Numerical Simulation 3 Results and Discussion 3.1 Experiment 3.2 Numerical Simulation 3.3 Insert Length 4 Conclusions References Research on Atmospheric Dispersion Factor Used in the Calculation of Emergency Planning Zone 1 Introduction 2 Calculation and Division of Emergency Planning Zones at Home and Abroad 2.1 Calculation of Emergency Planning Zones Abroad 2.2 Calculation of Emergency Planning Zones at Home 2.3 Size of Emergency Planning Zones of Operating Nuclear Facilities at Home 3 General Method for Determining Emergency Planning Zone [8] 4 Introduction and Comparison of Different Calculation Models of Atmospheric Dispersion Factors 4.1 RG1.145 Model 4.2 NUREG/CR-6331 Model 4.3 NUREG/CR-4691 Model [10, 11] 4.4 Lagrange Gaussian Puff Model [12, 13] 4.5 Comparisons of Atmospheric Dispersion Factor Models 5 Weather Sampling 5.1 Introduction to Different Weather Sampling Methods [14] 5.2 Stratified Random Sampling of Weather Data 6 Conclusion References Effects of Eluting Volumes to Isolation Efficiencies in Manual Synthesis of Ga-68 Labelled FAPI-04 1 Introduction 2 Materials and Methods 3 Results 4 Discussion 5 Conclusion References Visualized Numerical Analysis of Fustar Reactor Based on Modelica Language 1 Introduction 2 Method and Modelling 3 Results and Discussion 3.1 Steady-State Calculation 3.2 Step Reactivity Insertion Transient Analysis 3.3 Increasing the Outlet Pressure of the Pump 4 Conclusion References The Potential Force Interface Tension Model in MPS Method for Stratification Simulation 1 Introduction 2 Numerical Methods 2.1 The Basis MPS Method 2.2 Boundary Condition 2.3 The Potential Force Surface Tension Model 3 Model Verification 3.1 Dam Break 3.2 Droplet Oscillation 3.3 Droplet on Solid Wall 3.4 Floating Droplet 4 Model Validation 5 Conclusions References A Multi-state Degradation Model for Reliability Assessment of Multi-component Nuclear Safety Systems Considering Degradation Dependency and Random Shocks 1 Introduction 2 Model Framwork 2.1 Assumptions 2.2 Multi-state Model Considering Multiple Dependent Degradation Processes and Random shocks 3 Model Validation Based on a Simple Case 4 Numerical Example 4.1 Degradation Modeling 4.2 Results and Analysis 5 Conclusions References Heat Pipe Temperature Oscillation Effects on Solid-State Reactor Operation 1 Introduction 2 Methodology 2.1 Point Kinetics Model 2.2 Reactivity Feedback Model 2.3 Zonal Multi-channel Thermal-Mechanical Model 3 Simulations and Analyses 3.1 Heat Pipe Temperature Oscillation 3.2 Effect of Heat Pipe Temperature Oscillation on the Core 4 Conclusions References Uncertainty Analysis and Sensitivity Evaluation of a Main Steam Line Break Accident on an Advanced PWR 1 Introduction 2 RELAP5 Nodalization 2.1 Steady-State Results 2.2 Transient Sequence and Results 3 Uncertainty and Sensitivity Analysis 3.1 Phenomena Identification and Ranking Tables 3.2 Input Parameters Selection 3.3 Uncertainty Results 3.4 Sensitivity Analysis 4 Conclusions References Hysteresis Behaviors of a Bump-Type Foil Bearing Structure with Amended LuGre Friction Model 1 Introduction 2 Modeling and Solution 2.1 Modeling of the Bump Foil Structure 2.2 Modeling of the Frictional Contact 2.3 System Coupling and Solution 3 Results and Discussions 3.1 Modeling Verification 3.2 Presliding Behavior 3.3 Stick-Slip States During Loading-Unloading Process 3.4 Stribeck Effect 4 Conclusions References Research on Re-extraction Technology for Uranium Refining Based on Fractionation Extraction 1 Introduction 2 Theory of Fractionation Extraction 3 Results and Discussion 3.1 Extraction Equilibrium Isotherms 3.2 Discussion of Operation Step Line 3.3 Continuous Operation and Stability Control Investigation 3.4 Purification Effect 4 Conclusion References Hazard Identification on the Process of High-Level Liquid Waste Concentration and Denitration in Spent Fuel Reprocessing by HAZOP 1 Introduction 2 Description of the C/D Process 2.1 Reprocessing and HLLW Management 2.2 C/D Process 3 Methodology and Framework 3.1 HAZOP Methodology 3.2 Risk Assessment 4 Results and Discussions 5 Conclusions References Development of Subchannel Code for Plate-Type Fuel Plus Verification 1 Introduction 1.1 Research Status of Flow and Heat Transfer in Rectangular Channel 1.2 Research Status of Plate-Type Fuel Code Development 2 Development of Plate-Type Fuel Subchannel Code 2.1 Basic Conservative Equations 2.2 Constitutive Models 2.3 Flow Distribution Model 2.4 Special Heat Conduction Treatment of Side Cladding 3 Verification of Plate-Type Fuel Subchannel Code 4 Subchannel Analysis of a MTR Bundle 5 Results References Multi-Physics Coupling Model for Thermal Hydraulics and Solute Transport in CRUD Deposits 1 Introduction 2 Model 2.1 Thermal Model 2.2 Capillary Flow Model 2.3 Solute Transport and Reaction Model 2.4 Numerical Approach and Coupling Scheme 3 Results 4 Discussion 4.1 Influence of CRUD Porosity 4.2 Influence of CRUD Thickness 4.3 Influence of CRUD Chimney Radius 4.4 Influence of CRUD Chimney Density 5 Conclusion References Study on Composition Design of Enamel Coating and Its Resistance to Active Metal Vapor Corrosion 1 Introduction 2 Enamel Coating Composition Design 2.1 Preparation Technology of Enamel Coating 2.2 Interface Between Enamel Coating and Stainless Steel 3 Enamel Coating Properties 3.1 Phase Characterization of Enamel Coating 3.2 Hardness of Enamel Coating 4 High Temperature Evaporation Performance 4.1 Interface Between Cerium Metal and Stainless Steel After Evaporation 4.2 Interface Between Cerium Metal and Enamel Coating After Evaporation 4.3 Enamel Coated Stainless Steel Plate Reuse 5 Conclusions References Discussion on Common Bolt Scuffing Factors and Control Measures in the Installation and Maintenance Stage of Nuclear Power Plant 1 Introduction 1.1 Research Background 1.2 Research Purpose and Method 2 Detailed Description 2.1 Case Analysis of Bolt Tension During Installation and Maintenance of Nuclear Power Plant 2.2 Specification and Operation Process of Bolt Tensioning During Installation and Maintenance of Nuclear Power Plant 3 Conclusions References Study on Unstructured-Mesh-Based Importance Sampling Method of Monte Carlo Simulation 1 Introduction 2 Method and Implementation 2.1 Description of Unstructured-Mesh CADIS Method 2.2 Implementation 3 Numerical Results 4 Conclusions References Research on Parameter Sensitivity for Deeply Embedment SSI Analysis Based on Sub-structuring Method 1 Introduction 2 Analysis Model 2.1 Finite Element Model of the Superstructure 2.2 Parameters of the Site 2.3 Seismic Input 2.4 Observation Nodes at Key Positions 3 Sensitivity Analysis Results 3.1 Selection of the Interaction Nodes 3.2 Radius of the Cylindrical Central Area 4 Conclusions References Study on the Cause and Solution of Quadrant Power Tilt Rate Alarm in a PWR Plant 1 Introduction 2 Root Cause Analysis 2.1 RPN Measurement Data Analysis 2.2 Filtering Effect Analysis 3 Research in Solution 4 Conclusions References Wetting Behavior of LBE on 316L and T91 Surfaces with Different Roughness 1 Introduction 2 Experimental 2.1 Samples Preparation 2.2 Wetting Test 3 Results and Discussions 3.1 Surface Morphology Analysis 3.2 Contact Angle 3.3 Contact Time Affects 4 Summary References Solid-Liquid Equilibria of Ternary Systems UO2(NO3)2 + HNO3 + H2O and UF4 + HF + H2O at 298 K 1 Introduction 2 Experimental Section 2.1 Reagents 2.2 Apparatus 2.3 Experimental Method 2.4 Analysis Method 3 Results and Discussion 3.1 Synthesis of UO2(NO3)2·6H2O and UF4 3.2 Phase Equilibrium for Ternary System UO2(NO3)2 + HNO3 + H2O at 298 K 3.3 Phase Equilibrium for Ternary System UF4(1) + HF(2) + H2O(3) at 298 K 4 Conclusions References A Moose-Based Neutron Diffusion Code with Application to a LMFR Benchmark 1 Introduction 2 Code and Method Introduction 2.1 MOOSE Introduction 2.2 MC-Based Few-Group Constants Generation 3 Code Verification 3.1 Benchmark Modeling Description 3.2 Computation and Results 4 LMFR Application 4.1 Homogenized Few-Group Constants Generation 4.2 Computation and Results 5 Conclusion References Research on High-Performance Concrete for Volute Region of PX Combined Pump Room in Hualong Nuclear Power Plant 1 Introduction 2 Experiment Design and Method 2.1 Raw Materials Selection 2.2 Design of Mix Proportion 2.3 Test Method 3 Results and Discussion 3.1 Workability 3.2 Compressive Strength 3.3 Chloride Permeability Coefficient and Shrinkage Rate 3.4 Evaluation of Concrete Compressive Strength Design Organization 4 Conclusions References Thermo-Physical Property Database of Fusion Materials and Thermo-Hydraulic Database of Breeder Blankets for CFETR 1 Introduction 2 Introduction of Blankets 2.1 Helium Cooled Solid Breeder Blanket (HCSB) 2.2 Water Cooled Ceramic Breeder Blanket (WCCB) 2.3 Dual-Functional Lithium-Lead (DFLL) 3 Databases 3.1 Thermo-Physical Property Database of Blanket Material 3.2 Thermo-Hydraulic Database for Blankets 4 The Testings of Database 4.1 Testing of Material Database 4.2 Testing for Thermo-Hydraulic Database 5 Conclusions References Development and Verification of a New Depletion, Activation and Radiation Source Term Calculation Code 1 Introduction 2 Theory 2.1 Generation of the Depletion and Activation Chain Library for TIST 2.2 The Solution of the Bateman Equations in TIST 2.3 Radiation Source Term Calculation Methods 3 Numerical Results 3.1 The Second International Activation Calculation Benchmark 3.2 The VERA Depletion Benchmark 3.3 Radiation Source Term of the Spent Nuclear Fuel 4 Conclusions References Derivation of Activity Concentration Upper Limits for Low Level Solid Radioactive Waste 1 Introduction 2 Approach to Deriving Activity Limits 2.1 Assessment Context 2.2 Dose Limit 2.3 Disposal Site and Nuclide Selection 2.4 Scenario Analysis and Choice 3 Derivation and Calculation of the Upper Limit of Activity Concentration 3.1 Assessment Context 3.2 Drilling Scenario Calculation 3.3 Post-drilling Scenario Calculation 3.4 Housing Scenario Calculation 4 Determination of Nuclide Activity Concentration Upper Limit for Low Level Radioactive Waste References Evaluation of Uncertainty for Determination of Trace Uranium in Biology by Laser Fluorescence Method 1 Introduction 2 Measurement Method and Measurement Model Analysis 3 Evaluation of Uncertainty 3.1 Uncertainty of Repeatability of Sample Fluorescence Intensity Measurement (u1rel) 3.2 Uncertainty of Concentration of 1.0 μg/mL Uranium Standard Solution (u2rel) 3.3 Uncertainty of 1.0 μg/mL Uranium Standard Solution Volume (u3rel) 3.4 Uncertainty of Sample Constant Volume (u4rel) 3.5 Uncertainty of Sample Volume (u5rel) 3.6 Uncertainty of Weighing Samples is (u6rel) 3.7 Uncertainty of Total Chemical Recovery(u7rel) 3.8 Uncertainty of the Ash/fresh Ratio (u8rel) 3.9 Uncertainty of Dilution Ratio (u9rel) 3.10 Total Measurement Uncertainty 4 Conclusions References Research on Thermal-Hydraulic Model and Characteristics of Lead Cooled Traveling Wave Reactor 1 Introduction 2 Thermal-Hydraulic Model 2.1 Model of Coolant 2.2 Model of Fuel Rod 2.3 Model of Flow Distribution 2.4 Model of Heat Transfer Between Assembles 3 Candle 4 Result Analysis 4.1 Axial Heat Transfer 4.2 Flow Distribution 4.3 Assembly Heat Transfer 5 Conclusion References Design and Application of γ-Ray Energy Spectrum Survey System Based on UAV 1 Introduction 2 System Design 2.1 Development of Measurement System Host 2.2 Development of Detector 2.3 Measurement Software Development 3 Application 3.1 Measurement Test of Fixed Wing UAV 3.2 Rotor UAV Measurement 4 Conclusions References Research on the Radioactive Waste Discharge Permit Regulation 1 Introduction 2 Relevant Regulations of Chinese Standards 2.1 GB18871 “Basic Standard for Protection Against Ionizing Radiation and for the Safety of Radiation Source” 2.2 GB6249 “Environmental Radiation Protection Regulations for Nuclear Power Plants” 3 Radioactive Waste Discharge Permits in China 3.1 Nuclear Technology Utilization Units 3.2 Associated Minerals 3.3 Situation Analysis 4 Conclusions References Preparation and Shielding Performance of Gamma Ray Shielding Composite Materials Based on 3D Printing Technology 1 Introduction 2 3D Printing Radiation Protection Material Design 3 Materials and Method 3.1 Raw Materials and Forming Process 3.2 Test and Analysis 4 Results and Discussion 4.1 Composite Powder Mixing Process 4.2 Shielding Performance Research 5 Conclusions References Dynamic Response Analysis of Floating Nuclear Power Plant Containment Under Marine Environment 1 Introduction 2 Theoretical Basis of Potential Flow 2.1 Small Scale Member 2.2 Large Scale Member 3 Wave Load and Structural Response in Frequency Domain 3.1 Wave Load in Frequency Domain 3.2 Structural Response Calculation of Wave Load 4 Wind Load and Structural Response 4.1 Wind Load 4.2 Structural Response Calculation of Wind Load 5 Flow Load and Structural Response 5.1 Current Loading 5.2 Structural Response Calculation of Flow Load 6 Conclusions References Research on Process Diagnosis of Severe Accidents Based on Deep Learning and Probabilistic Safety Analysis 1 Introduction 2 AI Application in Accident Diagnosis of NPPs 3 Traceback Accident Progression Methodology During Transition from EOP to SAMG 3.1 Traceback Methodology 3.2 Header Event Branches 4 Case Study – Medium Break LOCA (MBLOCA) in a Pressurized Water Reactor (PWR) 4.1 Event Tree Analysis and Header Events Selection 4.2 Event Tree Scenarios Simulation with Branches 4.3 DL Models Training 4.4 Trace Back Accident Progression 4.5 Application of Basic Scenario for SAMG Assessment 5 Conclusions References Study on Calculation Method of Corrosion Product Source Term in Lead-Bismuth Fast Reactor Coolant System 1 Introduction 2 Corrosion Source 2.1 Impurities in the Coolant 2.2 The Structural Material of the Coolant Channel 3 Method of Establishment 3.1 Coolant Migration Process 3.2 Computational Model 3.3 Example Description 3.4 Calculation Results and Comparative Analysis 4 Conclusions References Research on ΔI Control Strategy During Rapid Power Reduction 1 Introduction 2 Research Background of Rapid Power Reduction 3 Research Methods 3.1 Operation Technical Specifications 3.2 SCIENCE and SOPHORA Software 3.3 Overall Control Strategy 4 Optimization Results 4.1 Influence of Fuel Burnup 4.2 Impact of Low-Power Platforms 4.3 Influence of Boronization and Rod Insertion 4.4 Comprehensive Feasibility Analysis of Fuel Burnup, Low Power Platform and Boronization 5 Sensitivity Analysis of Control Rod Motion 5.1 Sensitivity Analysis of R Rod Action During Power Reduction Process 5.2 Sensitivity Analysis of GN Rod Motion of Low Power Platform 5.3 Sensitivity Analysis of R-rod Motion of Low-Power Platform 5.4 Summary of Sensitivity Analysis 6 Conclusion References Minor Actinides Transmutation in Thermal, Epithermal and Fast Molten Salt Reactors with Very Deep Burnup 1 Introduction 2 General Description of the Geometry Models and Calculation Tools 2.1 Description of the Thermal, Epithermal and Fast MSRs 2.2 Selection of Salt Compositions 2.3 Calculation Tools 3 Results and Discussion 3.1 Neutron Spectra Variation with Addition of MA into the Fuel Salt 3.2 Transmutation Capability in the Three MSR Cores 3.3 TRU Evolution and Radiotoxicity 3.4 Evaluation on Safety Parameters 4 Conclusions References Development and Preliminary Verification of a Neutronics-Thermal Hydraulics Coupling Code for Research Reactors with Unstructured Meshes 1 Introduction 2 Methodology 2.1 Triangular-Z Node Neutron Transport Model 2.2 Transient Neutronic Model 2.3 Thermal Hydraulics Model 3 Results and Discussion 3.1 TWLGL Benchmark Problem 3.2 3D-LMW Benchmark Problem 3.3 NEACRP Benchmark Problem 4 Conclusions References Preliminary Multi-physics Coupled Simulation of Small Helium-Xenon Cooled Mobile Nuclear Reactor 1 Introduction 2 Methodology 2.1 Method 2.2 Coupling Framework 2.3 Model 3 Results 3.1 Coupling Results 3.2 Thermal Results Analysis 4 Conclusion References Study on the Steady-State Performance of the Fuel Rod in M2LFR-1000 Using KMC-Fueltra 1 Introduction 2 Material Properties 2.1 MOX Fuel 2.2 T91 Cladding 3 Model Implementation 3.1 Description of M2LFR-1000 3.2 Introduction of KMC-Fueltra 3.3 Indicative Design Limits 4 Results and Discussions 4.1 Thermal Performance 4.2 Fission Gas Release 4.3 Mechanical Performance 5 Conclusions References Heterogeneous Reactivity Effect Analysis of Pu Spots Considering Grain Size Distribution Based on MOC 1 Introduction 2 Calculation Method and Condition 2.1 Calculation Flow 2.2 Calculation Condition 2.3 Estimation of Grain Size Distribution 3 Calculation Result 4 Conclusions References Preparation and Properties of Graphite Surface Vitrification Y2O3 Coating 1 Introduction 2 Test Materials and Methods 3 Experimental Results and Analysis 3.1 Coating SEM, XDR Analysis 3.2 Coating Bonding Strength Score 3.3 Terbium Metal Melting Test Coating Test 4 Conclusion References Numerical Study on the Mechanism of Oxygen Diffusion During Oxygen Control Process in Heavy Liquid Metals 1 Introduction 2 Numerical Modeling 2.1 Geometry and Mesh 2.2 Governing Equations and Boundary Conditions 3 Results and Discussion 4 Conclusions References Research of Steady-State Heat Transfer Performance of Heat Pipe Inside Mobile Heat Pipe Reactor 1 Introduction 2 Research Object 2.1 Geometric Model 2.2 Calculation Parameters 2.3 Grid Irrelevance Verification 3 Calculation Formula 4 Results and Discussion 4.1 Effect of Horizontal Acceleration on Heat Pipe Temperature 4.2 Effect of Horizontal Acceleration on Heat Transfer Performance of Heat Pipes 4.3 Influence of Input Thermal Power on Heat Pipe Temperature 4.4 Influence of Input Thermal Power on Heat Transfer Performance of Heat Pipe 5 Conclusion References Direct Contact Condensation Characteristics of Steam Injection into Cold-Water Pipe Under Rolling Condition 1 Introduction 2 Mathematic Model 2.1 Two-Phase Flow Mode 2.2 Condensation Phase Change Model 2.3 Rolling Motion Model 2.4 Defined Geometry and Mesh Generation 3 Results and Discussion 3.1 Mesh Independence Test 3.2 Validation of DCC Numerical Model 3.3 DCC Process Under Rolling Conditions 3.4 Effect of Rolling Motion on Condensation Rate 3.5 Effect of Rolling Motion on Pressure Behaviors 4 Conclusions References The Dynamic Response Analysis Method of Steel Containment in Floating Nuclear Power Plant 1 Introduction 2 Modeling and Theoretical Basis 2.1 ANSYS APDL Model Parameter Settings 2.2 Contact Algorithms and Contact Types 2.3 Workbench LS-DYNA Model Preprocessing 3 Comparison of Simulation Results 3.1 Equivalent Stress During Impact 3.2 Force Analysis of Supports During Impact 4 Conclusion References Three-Dimensional Pin-by-Pin Transient Analysis for PWR-Core 1 Introduction 2 Theoretical Models 2.1 Calculation of Neutron Dynamics 2.2 Calculation of Thermal Feedback 2.3 Coupling of Neutronics with Thermal-Hydraulics 2.4 Parallel Calculation 2.5 Interim Summary 3 Numerical Verification and Analysis 3.1 CNP1000 3.2 AP1000 4 Conclusion References S3R Advanced Training Simulator Core Model: Implementation and Validation 1 Introduction 2 Neutronic Model Description 2.1 Features 2.2 Nuclear Data 2.3 Decay Heat 2.4 Detectors 3 Coupling to System Code 4 Interfface with Executive 5 Cycle Update and Initial Conditions 6 Physics Testing 7 Core Monitoring 8 Additional Items 8.1 Decay Heat Reset 8.2 Xenon Worth 9 Conclusions References Study of Stress Analysis Method for Floating Nuclear Power Plant Containment Under Combined Multiple Loads 1 Introduction 2 Materials and Methods 2.1 Study Subjects 2.2 Combination of Working Conditions 2.3 Internal Pressure Loads and Temperature Loads 2.4 Wave Load 2.5 Crash Load 2.6 Stress Analysis Methods 3 Results 3.1 Stress Evaluation 3.2 Individual Load Conditions 3.3 Combined Load Conditions 4 Discussion References Analytical Method to Study the Ultimate Bearing Capacity of Containment for Floating Nuclear Power Plants Considering Wave Loads 1 Introduction 2 Nonlinear Analysis Method 2.1 Arc length method 2.2 Quasi Static Method 3 Calculation of Ultimate Bearing Capacity Under Different Working Conditions 3.1 Calculation and Analysis of Ultimate Bearing Capacity Under Internal Pressure Condition of Containment 3.2 Calculation and Analysis of Ultimate Bearing Capacity of Containment Vessel Under Combined Wave Load and Internal Pressure 4 Conclusions References Decoupling and Coupling Simulation Analysis in Small Nuclear Power Plant 1 Introduction 2 Model 2.1 Primary Loop Decoupling Model 2.2 Secondary Loop Decoupling Model 2.3 Primary and Secondary Loop Coupling Model 3 Simulation Analyses