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

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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 Creation
4 Result and Discussion
5 Conclusions
References
Study on the Coupled Heat Transfer Characteristics of Liquid Lead-Bismuth Eutectic and Supercritical CO2
1 Introduction
2 Research Object
2.1 Analysis Model
2.2 Calculate Parameters and Boundary Conditions
2.3 Meshing and Independent Verification
3 Computational Model
3.1 Governing Equation
3.2 Turbulence Model
3.3 Heat Transfer Equation
4 Results and Analysis
4.1 Temperature Distribution
4.2 Heat Exchange
4.3 Heat Transfer Coefficient
4.4 Pressure Drop
5 Conclusion
References
Adsorption Behaviors of Hydrogen on Equal Atomic Ratio TiZrV Film Applied in AB-BNCT by Density Functional Theory Study
1 Introduction
2 Model
3 Hydrogen Adsorption
4 Conclusion
References
Research on Interface Technology of Coupling Thermal-Hydraulics and Other Codes
1 Introduction
2 Coupling Platform
3 Coupling Schemes
3.1 Coupling Methods
3.2 Spatial Mesh Correspondence
3.3 Time Step Coupling
3.4 Coupled with Other Software
4 Tests
4.1 Test Data
4.2 Test Results
5 Conclusion
References
Development and Verification of Transport-Activation Coupling Capability in CosRMC
1 Introduction
2 Internal Coupling Transport-Activation Calculation Function Development
3 Computational Model and Comparison Code
4 Calculation Results and Analysis
4.1 Constant Energy Spectrum
4.2 Constant/Variable Energy Spectrum
4.3 Continuous Energy/Multi-group Cross Section
5 Conclusions
References
Research on Shielding Deep Penetration Calculation Based on MC Variance Reduction Techniques
1 Introduction
2 Geometric Model of Particle Transport
3 Application of Variance Reduction Techniques
4 Calculation Results and Analysis
4.1 Single Variance Reduction Technique
4.2 Combined Variance Reduction Techniques
5 Conclusions
References
Prospects for Next Generation Nuclear Power System
1 Introduction
2 Basic Design Considerations
2.1 Economic
2.2 Safety
2.3 Environment-Friendly
2.4 Resource Utilization
3 Features of Next Generation Nuclear Power System
4 Conceptual Design of Next Nuclear Power System
4.1 Intrinsically Safe Multipurpose Lead Cold Traveling Wave Reactor
4.2 Technical and Research Difficulties
5 Conclusions
References
Safety Analysis of Internal Flooding Under Main Feedwater Pipeline Rupture Accident Based on Small Modular Reactor ACP 100
1 Introduction
2 Method
2.1 Internal Flooding Safety Evaluation
2.2 Application of CNIFA for Internal Flooding Safety Evaluation
2.3 Internal Flooding Analysis of Main Feedwater Supply Pipeline Rupture Accident
3 Result and Discussion
3.1 Simulation Results of Main Feedwater Supply Pipeline Accidents
3.2 Design Optimization and Improvement
3.3 Optimization and Improvement Results
4 Conclusions
References
Research on Nuclear Seawater Desalination Technology Based on Small Modular Reactor ACP100
1 Introduction
2 Method
2.1 Seawater Desalination Process
2.2 Radioactivity of Nuclear Desalination
2.3 Cost Calculation of Nuclear Desalination
3 Result and Discussion
3.1 Analysis of Radioactivity for MED Nuclear Desalination
3.2 Cost of Different Nuclear Desalination Methods
4 Conclusions
References
Research Status and Prospect of Comprehensive Utilization Technology of Nuclear Energy
1 Introduction
2 Comprehensive Utilization of Nuclear Energy
2.1 Nuclear Heating
2.2 Nuclear Steam Supply
2.3 Nuclear Desalination
2.4 Nuclear Hydrogen Production
2.5 Nuclear Energy-Storage-Renewable Energy Coupling
3 Scene Construction
4 Suggestions on the Development of Comprehensive Utilization of Nuclear Energy
4.1 Strengthen the Top-Level Design and Coordinate the Promotion of Comprehensive Nuclear Energy Utilization Planning
4.2 Improve Scientific and Technological Research and Development Capabilities and Make Breakthroughs in Key Technology Application Innovations
4.3 Promote the Reform of the System and Mechanism, and Improve the Construction of the Standard System for Comprehensive Utilization of Nuclear Energy
4.4 Strengthen Industry Supervision and Continuously Improve the Safety Performance of Nuclear Energy
References
Hydrogen Adsorption Mechanism of Non-equal Atomic Ratio TiZrV NEG Films Surface
1 Introduction
2 Model Building
3 Results and Disscussion
3.1 Adsorption Energy
3.2 Density of States
4 Conclusion
References
Study of Fast-Start Heat Transfer Characteristics of Potassium Heat Pipe
1 Introduction
2 Research Subject
2.1 Geometric Model
2.2 Calculation Parameters
2.3 Grid Irrelevance Verification
3 Calculation Formula
4 Results and Discussion
4.1 Heat Pipe Routine Start-Up Calculation
4.2 Heat Pipe Condensing Section External Heating Start-Up Calculation
4.3 Heat Pipe Internal Heating Start-Up Calculation
5 Conclusion
References
Prediction of CHF in Narrow Rectangular Channel Based on GA-BP Neural Network
1 Introduction
2 CHF Database
3 BP Neural Network
4 GA-BP Neural Network
5 Conclusions
References
Study on 131I Source Term in Reactor Coolant Under Shutdown Transient Condition
1 Introduction
2 Cause Analysis of 131I Peak Release
3 Analysis of 131I Peak Factor and Release Rate
3.1 Analysis of 131I Peak Factor
3.2 131I Release Analysis
4 Conclusions
References
Study on Aggregation Forming of Cathode Liquid Cerium Metal in Molten Salt Electrorefining Process
1 Introduction
2 Experimental Section
2.1 Experimental Materials and Equipment
2.2 Experimental Methods and Procedure
3 Analysis of Factors Affecting Cathodic Metal Cerium Forming
4 Results and Discussion
4.1 Passivation Film Confirmation and Electrode Structure Optimization
4.2 Study on Parameter Optimization of Four—Electrode System
5 Conclusions
References
Thermal Engineering Calculation of Control Drum Misoperation of Heat Pipe Reactor
1 Introduction
2 Research Object
2.1 Geometric Model
2.2 Calculation Parameters
3 Computational Model
3.1 Calculation Parameters
3.2 One Dimensional Heat Conduction Model
3.3 Reactivity Introduction and Feedback Model
3.4 Model Validation
4 Calculation Results and Analysis
4.1 Hottest Fuel Assembly Neutron Flux
4.2 Hottest Fuel Assembly Hot Spot Temperature
4.3 Normalized Power of Hottest Fuel Assembly
5 Conclusion
References
CFD Analysis on the Multiphase Flow of the Wickless Sodium Heat Pipe with Non-condensable Gas
1 Introduction
2 Experimental Apparatus
3 CFD Model and Solution Description
4 Results and Discussion
5 Conclusions
References
Influence of Impedance Characteristics of Perforated Plate on Pump-Induced Pulsation in Reactor
1 Introduction
2 Theory of Acoutisc Damping
2.1 Fluid Damping
2.2 Boundary Impedance Characteristics
3 Computational Model
3.1 Finite Element Model
3.2 Model Parameter
4 Results and Discussing
4.1 Modal Analysis
4.2 Sound Pressure Response Without Considering Impedance Boundaries
4.3 Sound Pressure Response Considering Impedance Boundaries
5 Conclusion
References
Development of Design and Verification Platform for Heat Pipe Cooled Nuclear Reactor
1 Introduction
2 Reactor Structure
2.1 Core Body System
2.2 Heat Pipe Thermoelectric Power Generation System
2.3 Residual Heat Removal System
3 Architecture of HPR Design Verification Platform
3.1 Introduction to Simulation Platform
3.2 System Models
3.3 Model Interface
4 Result of Coupling Calculation
5 Conclusion
References
Development of Curriculum for International Students in the Field of Nuclear Energy Engineering at Harbin Engineering University
1 Introduction
2 Analysis of International Students in the Field of Nuclear Energy Engineering
2.1 Background of International Students
2.2 Thinking and Countermeasures
3 Design of Curriculum for Master Program of Nuclear Energy Engineering
3.1 Common Course Modules
3.2 Professional Basic Course Modules
3.3 Professional Course Modules
3.4 Management Course Modules
3.5 Practice Modules
3.6 Curriculum
4 Conclusions
References
Technological Upgrading Analysis on Diversity Transformation of Reactor Protection System in a Fast Reactor Project
1 Introduction
2 Reactivity Control in Water Reactor
3 Design of Reactor Protection System of Other Fast Reactor
4 Design of Reactor Protection System of One Fast Reactor in China
5 Design and Optimization of Fast Reactor Protection System
6 Possible Upgrading Direction
7 Conclusions
References
Study on Top Architecture Design of Nuclear Power System Based on an Incremental Iteration Generation Method
1 Introduction
2 Method Introduction
3 Functional Architecture Generation for Nuclear Power System
4 Logical Architecture Generation for a Nuclear Power System
4.1 Functional and Logical Component Definitions
4.2 Logical Structure Inference of Nuclear Power System Based on Functional-Logical Mapping
4.3 Definition of Faults in the Logical Structure of Nuclear Power Systems
4.4 Internal Association of Logic Structure of Nuclear Power System
5 Case Study: Normal Residual Heat Removal System of Nuclear Heating Reactor
5.1 Functional Decomposition of Heating Reactor Under Normal Operating Conditions
5.2 Definition of Abnormal Conditions
5.3 Internal Associations of the System Logical Architecture
6 Summary
References
Study on Optimization of Economic Evaluation Methods for Generation III Reactors in China
1 Introduction
2 Overview of the 2011 Energy Standard
2.1 The Financial Evaluation Method
2.2 Evaluation Parameters
3 Economic Evaluation Method Improvement Analysis
3.1 Economic Evaluation Parameters
3.2 Nuclear-Related Expenses
3.3 Power Market Reform Factors
3.4 Operation and Maintenance Costs Division
4 Case Calculation
4.1 Evaluation Parameters
4.2 Evaluation Results
5 Conclusion
References
Preliminary Design and Thermal Analysis of Intermediate Heat Exchanger Based on Irradiation Test Loop with Alternative Coolants
1 Introduction
2 Structure Design and Key Parameters of the Heat Exchanger
2.1 Description of the Heat Exchanger Structure
2.2 Thermal Design Input
2.3 Key Design Parameters of Heat Exchanger
3 Method and Thermal Calculation
3.1 Convective Heat Transfer Coefficient of Tube Side
3.2 Convective Heat Transfer Coefficient of Shell-Side LBE
3.3 Heat Exchange Accounting
4 Thermal Analysis Under Alternative Coolants Conditions
4.1 Influence of Thermal Parameters Under Liquid Metal Conditions
4.2 Influence of Thermal Parameters Under Helium or Molten Salt Condition
5 Conclusions
References
Development of High-Fidelity Neutron Transport Solver of Alpha
1 Introduction
2 Theory
2.1 Methodology of MOC-EX
2.2 Methodology of 3D CMFD
3 Implementation
3.1 Parallel Planar MOC Algorithm
3.2 Parallel Planar MOC Algorithm
4 Numerical Results
4.1 The 3D C5G7 MOX Benchmark Problem
4.2 The 3D KAIST Benchmark Problem
5 Conclusions
References
Study on Welding Process Between the Hexagonal Tube and the Grid Frame Component of MOX Fuel Assembly in CEFR
1 Introduction
2 Materials and Equipments
2.1 Experimental Materials
2.2 Experimental Equipment
3 Quality Requirements and Experimental Methods
3.1 Welding Quality Requirements
3.2 Experimental Method
4 The Results and Welding Procedure Qualification
4.1 Influence of Welding Current
4.2 Influence of Electrode Pressure
4.3 Influence of Welding Time
4.4 Welding Procedure Qualification
5 Conclusions
References
Unattended Monitoring Apparatus Data Analysis Technicals Used for Nuclear Safeguards
1 Introduction
2 Basic Concepts of Unattended Monitoring of Nuclear Safeguards
3 Research on Unattended Data Analysis Techniques for Nuclear Material Management
3.1 Data Acquisition and Exchange Systems
3.2 Data Information Management System
4 Conclusions
References
Economic Analysis of Nuclear Cogeneration System Based on High-Temperature Gas-Cooled Reactor
1 Introduction
2 Thermal Economic Model of HTGR Cogeneration System
3 Results and Discussion
3.1 Thermal Economic Analysis of Thermo-power Cogeneration System
3.2 Thermal Economic Analysis of Hydrogen-Power Cogeneration System
4 Conclusions
References
Study on Social Stability Risk Assessment of Nuclear Facilities
1 Introduction
2 SSRA Procedure
3 SSRA Contents
4 SSRA Scope and Methods
5 SSRA Risk Index Database
6 SSRA Evaluation Criteria and Weight Calculation
6.1 SSRA Evaluation Criteria
6.2 SSRA Weight Calculation
7 Case Analysis
8 Conclusion
References
Investigation on the Fabrication of High-Density Micro Pits on Zirconium Alloy by Micro Imprinting
1 Introduction
2 Experimental
2.1 Sample Preparation
2.2 Fabrication of Die
2.3 Imprinting Process
3 Results and Discussion
3.1 Traditional Imprinting Forming
3.2 “Step by Step” Imprinting Process
4 Conclusions
References
Application and Analysis of Airborne Electromagnetic Method in Engineering Exploration of High-Level Radioactive Waste Repository
1 Introduction
2 Introduction of Airborne Electromagnetic Method in Exploration of Qinghai Province
3 Analysis of the Ability of Airborne Electromagnetic Method to Solve Geological Problems
4 Application Prospect of Airborne Electromagnetic Method in Exploration of High-Level Radioactive Waste Disposal Repository
5 Conclusion
References
Optimization of Power Supply Scheme and Economic Benefit Analysis of a Project in a Newly-Built Large Nuclear Chemical Plant
1 Introduction
2 Load Analysis
2.1 Project Overview
2.2 Load Analysis
2.3 Safety Level Loads
3 Power Supply Scheme and Economic Benefit Analysis
3.1 Power Supply Scheme
3.2 Innovation and Comparison
3.3 Economic Benefits
4 Conclusion
References
Air-Cooler Structure Optimization of HTGR Passive Cavity Cooling System
1 Introduction
2 PCCS Air Cooler
3 Numerical Simulation
3.1 Grid
3.2 Numerical Methods
3.3 Data Reduction
3.4 Grid Independence Analysis
4 Flow Uniformity of PCCS Air Cooler
4.1 Flow Uniformity Comparison
4.2 Static Pressure Recovery
4.3 Flow Field Comparison
4.4 Optimization Analysis of Central-Type Arrangement
5 Conclusions
References
Research on the Innovative Development Trend and Competition Pattern of Domestic Nuclear Heating from the Perspective of Patents
1 Introduction
2 Research Methods
2.1 The Patent Search Process
2.2 The Patent Search Strategy
2.3 The Selection of Patent Information Features
2.4 The Determination of Competitive Situation Analysis Dimension
3 Conclusions
4 Proposal
References
Study on Beam Trajectory Deflection and Spatial Dose Distribution in Magnetic Resonance-Guided Proton Therapy
1 Introduction
2 Materials and Methods
2.1 Simulation Model
2.2 Magnetic Field Distribution Data
3 Results
3.1 Beam Trajectory Deflection with Fringe Magnetic Field
3.2 Study on the Spatial Dose Distribution of Secondary Particles Guided by Magnetic Fields
3.3 Study on Spatial Dose Distribution Before and After Beam Trajectory Correction
4 Conclusions
References
Analysis on the Global Competition of Digital Reactor from the Perspective of Patents
1 Introduction
2 Research Method
3 Research Contents
3.1 Global Patent Competition Landscape
3.2 Patent Competition Pattern in China
3.3 Patents in Key Technical Fields
4 Conclusions
References
A Monte Carlo Code Developed for Radiation Shielding Calculations Based on RMC
1 Introduction
2 Features Suited for Shielding Calculation
2.1 Gamma Transport and Coupled Transport
2.2 Flexible Fixed Source Definition and Calculation
2.3 Variance Reduction Function
2.4 Others
3 Validation and Application
3.1 PWR Model
3.2 Results
4 Summary
References
Performance Analysis and Optimization of Heat Pipe-Based Radiator for Space Fission Power System Thermal Management
1 Introduction
2 Design of Heat Pipe Radiator
3 Analysis of Heat Dissipation Process of Heat Pipe-Fin Unit
4 The Influence of Design Parameters on the Weight of Radiator
4.1 The Influence of lhpc on Radiator Weight
4.2 The Influence of lf on Radiator Weight
4.3 The Influence of Tf11 on Radiator Weight
5 Simulation Analysis of Heat Pipe Radiator
5.1 Analysis of Flow Characteristics of Alkali Metals
5.2 Analysis of Heat Transfer Characteristics of Alkali Metals
6 Conclusion
References
Study on Flow and Heat Transfer of Liquid Gallium
1 Introduction
2 Research Objectives
2.1 Geometric Model
2.2 Calculation Parameters
3 Heat Transfer Model
3.1 Liquid Gallium Physical Properties Calculation Model
3.2 Turbulence Model
3.3 Heat Transfer Model
4 Results and Discussion
4.1 Effect of Inlet Velocity
4.2 Effect of Heat Flux
4.3 Effect of Tube Diameter
4.4 Effect of Fluids
5 Conclusions
References
Assessing the Effect of Some ATF Materials and Uncertainties on Their Properties Under Normal Operation Conditions by Means of the Transuranus Code
1 Introduction
2 Material Properties Implemented in Transuranus
3 Case Description
4 Results and Discussion
4.1 Effect of ATF Materials
4.2 Uncertainty Analysis
5 Summary and Conclusions
References
Author Index