Challenges and Recent Advancements in Nuclear Energy Systems

Name: Challenges and Recent Advancements in Nuclear Energy Systems | Proceedings of Saudi International Conference on Nuclear Power Engineering (SCOPE)
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Proceedings of Saudi International Conference on Nuclear Power Engineering (SCOPE)

Afaque Shams Khaled Al-Athel Iztok Tiselj Andreas Pautz Tomasz Kwiatkowski(Herausgeber*in)

Springer (Verlag)

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Erschienen am 20. Juli 2024

XIV, 845 Seiten

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Inhalt

Intro
Forward
Contents
Education and Training
Ready for Nuclear Energy? a Road to Peaceful Nuclear Power Generation Development in the Kingdom of Saudi Arabia: Vision 2030
1 Introduction
2 Milestones Approach: Successful Development of Nuclear Power Plant
3 Historical Overview of KSA Nuclear Power Generation Deployment:
4 Suggestions and Recommendations:
5 Conclusion
References
Sustainable Energy Transition: Role of Nuclear Power
1 Introduction
2 Nuclear Power and Energy Transition
3 Energy Technologies for Energy Transition: Multi-criteria Decision Analysis
3.1 AHP Analysis
4 Conclusions
References
Model-Driven Engineering for Optimal Project Delivery: Introducing the Project Delivery Model (PDM)
1 Introduction
2 Background
3 The Project Delivery Model (PDM)
3.1 PDM - The Metamodel
3.2 MBSE for PDM
3.3 Artificial Intelligence (AI)
4 PDM - Going Beyond Traditional KPIs
5 Implementation of PDM
6 PDM Building Blocks
7 PDM Benefits for Nuclear Projects and Discussion
8 Conclusions
References
The Role of Research Reactor in National Human Capacity Building for Nuclear Power
1 Introduction
2 Lack of Nuclear Human Resources
3 The Role of the Research Reactor
3.1 Design, Construction and Commission Phase
3.2 Operation Phase
4 Conclusions
References
Nuclear Applications and Radiation Processing
Development of Radionuclides for Theragnostic Applications at the Paul Scherrer Institut (PSI)
1 Introduction
2 Radionuclide Production
3 Conclusions
References
CNN-Based Detection of Welding Crack Defects in Radiographic Non-Destructive Testing
1 Introduction
1.1 Overview
1.2 Welding and Welding Defects
1.3 Radiographic Non-Destructive Testing:
2 Neural Networks
2.1 Deep Neural Networks (DNN)
2.2 Convolutional Neural Networks
2.3 Filters, Stride and Padding
2.4 Max Poling
3 Related Work
4 Materials and Methods
4.1 Dataset
4.2 Data Preparation
4.3 Data Augmentation
5 Results and Discussion
6 Conclusions
References
Simulation Study on X-Ray Radiographic Testing of Welds
1 Introduction
2 Materials and Methods
3 Results and Discussion
3.1 Flawed Carbon Steel Welded Plate
3.2 Flawed Carbon Steel Welded Pipe
4 Conclusions
References
Assessing Environmental Hazard Parameters of Natural Radioactivity in a High Background Area
1 Introduction
2 Experimental
2.1 Study Area
2.2 Analytical Methods
2.3 Implications of Environmental Hazards
3 Results and Discussion
3.1 Radionuclides Activity Concentrations
3.2 Environmental Hazard Impacts and Results
4 Conclusions
References
Conceptual Design for an Advanced High Field 30 MeV Superconducting Cyclotron for Medical Isotopes Production
1 Introduction
2 Magnet
2.1 Iron Yoke
2.2 Superconducting Coil
3 Conclusion
References
Production Radio-Chromic Films Dosimeter for Low and High Irradiation Dose Application
1 Introduction
2 Experiment Methods
2.1 Materials and Devices
2.2 Film Dosimeter Preparation
3 Result
3.1 Study of UV/Vis Measurement of Methyl Red Dye
3.2 Study of UV/Vis Measurement of Sudan Orange Dye
3.3 Study of UV/Vis Measurement of Solo Chrome Black Dye
3.4 Study of UV/Vis Measurement of Phenolrot Dye
4 Discussion
5 Conclusions
References
The Promising Use of Volcanic Silica as an Environmental Source for Diagnostic X-ray Shielding Applications
1 Introduction
2 Materials and Methods
2.1 Monte Carlo Simulation
2.2 Shielding Material
2.3 Silica Collection and Their Chemical Element Compositions
2.4 Procedures
3 Results and Discussion
4 Conclusions
References
Techno-Economic Model for Hydrogen Production Using Advanced Nuclear Power Plants in Saudi Arabia
1 Introduction
2 Methodology
2.1 Computational Tool and Financial Parameters
2.2 Inputs Data for HEEP
3 Results and Discussion
4 Conclusions
References
Experience with Delayed- and Prompt-Gamma Neutron Activation Analysis Using Accelerator-Based Neutrons at KFUPM: An Overview
1 Introduction
2 Experimental Setups
2.1 Delayed-Gamma NAA (NAA)
2.2 Prompt-Gamma NAA (PGNAA)
3 Conclusions
References
Nuclear Power, Photovoltaics, and Compressed Air Energy Storage: A Low-Cost, On-Demand Power Hub for Saudi Arabia
1 Introduction
2 Methods and Discussions
2.1 Exploring Nuclear Energy Storage as a Primary Solution Among Alternative Applications
2.2 Integrating NPP and PV into CAES
2.3 Energy Cost Estimate of the Integrated NPP-PV-CAES
3 Conclusions
References
Modeling of Compact ECR Ion Source for Electrostatic Storage Ring at KACST
1 Introduction
2 ECR Mechanical Design
3 LEBT Beam Line
4 Beam Line Modelling and Simulation
5 Conclusion
References
Phenazine Porous Polymers for Radioactive Iodine Capture
1 Introduction
2 Experimental
2.1 Materials and Instruments
2.2 Synthesis of Phenazine Based Porous Polymers
2.3 Volatile Iodine Uptake Experiments
2.4 Solution Iodine Uptake Experiments
3 Results and Discussion
3.1 Characterization of PHP, PHT and PHF Porous Polymers
3.2 Adsorption Properties of the Synthesized Polymers
4 Conclusions
References
Possible Deep Geological Repository Site for High-Level Radioactive Waste in the Kingdom of Saudi Arabia
1 Introduction
2 Literature Review
2.1 Cigéo
2.2 Gobi Desert
2.3 Onkalo
2.4 Yucca Mountain
2.5 High-Level Radioactive Waste Storage Feasibility for the Kingdom of Saudi Arabia
3 Methodology
4 Results and Discussion
5 Conclusion
References
Design and Optimization of a Directional Radiation Detection System
1 Introduction
2 Design
2.1 Overview
2.2 Mechanical Design
2.3 Radiation Detectors
2.4 Microprocessor
2.5 Electronics
2.6 Simulation
2.7 Graphical User Interface (GUI)
3 Results
3.1 Location Results
3.2 Geiger-Muller Efficiency
4 Discussion
4.1 Circuitry
4.2 Localization Algorithm
4.3 Simulation
5 Conclusion
6 Future Work
References
Characterization of the Direct and Scattered Neutron Flux Around Cyclotron Target
1 Introduction
2 Methods and Materials
2.1 Cyclotron Facility
2.2 Foil Monitor Technique and Foil Selection
2.3 Experiments
3 Results and Discussion
4 Conclusion
References
Nuclear Materials
Materials and Corrosion in Light Water Reactors
1 Overviews
1.1 Corrosion Basics
1.2 Nuclear Materials
2 Zirconium Cladding
3 Flow Accelerated Corrosion
4 Stress Corrosion Cracking
5 Conclusion
References
Visualization Experiments of Radiation Heating on the Eutectic Reaction Between B4C-SS and Its Relocation Behavior
1 Introduction
2 Eutectic Relocation with Radiating Heating Test Facility
2.1 Heating Method
2.2 Materials
2.3 Experimental Facility
2.4 Experimental Methodology
3 Results and Discussions
3.1 Visualization of Eutectic Reaction and Liquefication Process
4 Conclusions
References
Review of the Radiation Effect on the Cladding of Zirconium Alloy in Nuclear Reactors
1 Introduction
1.1 Neutron-zirconium Interaction
1.2 Displacement Energy in Zirconium
2 Background
3 Radiation Effect on Zirconium Alloys
3.1 Hydrogen Embrittlement
3.2 Irradiation Growth
3.3 Single Crystal Zirconium
3.4 The Effect of Fission Products
4 Conclusions
References
Hydrogen and Temper Embrittlement Effects on Fatigue Fracture Behaviour of 2.25Cr-1.0Mo Nuclear Reactor Pressure Vessel Steel
1 Introduction
2 Experimental
2.1 Materials and Heat Treatment
2.2 Metallography
2.3 Fatigue Crack Growth Test
2.4 Fractography
3 Results and Discussion
3.1 Microstructures
3.2 Role of HE on IGF
3.3 Embrittlent and Fatigue Crack Growth
4 Conclusions
References
Numerical Evaluation of Crack in the Nuclear Reactor Pressure Vessel Using Extended Finite Element Method Technique
1 Introduction
2 System Description
2.1 Semi-elliptic Surface Crack Inside Finite Plate
2.2 Semi-elliptic Surface Crack in RPV
3 Conclusion
References
Review of Neutronics, Thermal-Hydraulic, and Fuel Performance Research of Accident Tolerant Fuels for APR-1400 in United Arab Emirates Nuclear Power Plants
1 Introduction
2 ENTC Research Activities
2.1 Neutronics Analyses Research Activities
2.2 Thermal -Hydraulics Analyses Research Activities
2.3 Thermo-Mechanical Analyses Research Activities
3 Conclusion
References
Modifications of Alkaline-Earth Fluorides Using Slow Highly Charged Ions
1 Introduction
2 SHCI-Induced Nanostructures in Fluorides
2.1 Calcium Fluoride (CaF2)
2.2 Barium Fluoride (BaF2)
3 Summary
References
Hybrid Microwave Sintering of Yttria Stabilized Zirconia
1 Introduction
2 Materials and Experimental Work
3 Results and Discussion
4 Conclusion
References
Comparative Study of Deep Learning and Machine Learning Techniques for Corrosion and Cracks Detection in Nuclear Power Plants
1 Introduction
2 Types of Deep Learning Models and Methods
3 Applications of Deep Learning in Nuclear Power Plants
3.1 Computer Vision in Nuclear Power Plant
4 Deep Learning for Crack Detection
5 Conclusions
References
Finding Resolution and Efficiency for Multiple Gamma Energies for LYSO(Ce), CaF2(Eu), and NE102A Crystals Using SiPM
1 Introduction
2 Literature Review
2.1 Resolution
2.2 Efficiency
3 Materials and Methodology
4 Results and Discussion
4.1 Resolution
4.2 Efficiency
5 Conclusion
References
Understanding Stress Corrosion Cracking (SCC), Affecting Variables and Prevention Strategies in Nuclear Power Plants-A Review
1 Introduction
2 Mechanisms of Stress Corrosion Cracking
2.1 Active Path Dissolution and Film Rupture
2.2 Hydrogen Embrittlement Mechanism
3 Result and Discussion
3.1 Material
3.2 Stress
3.3 Environment
4 Stress Corrosion Cracking Prevention
5 Conclusion
References
Nuclear Thermal-Hydraulics
Safety Analysis During Low-Pressure Case in VVER-1000 with ASYST
1 Introduction
2 A Brief Description of VVER-1000
3 ASYST Application in Light Water Reactors
4 Modelling and Transient Simulation
4.1 Plant Geometrical Modelling
5 Steady State Calculation
6 Transient Results and Discussion
7 Conclusions
References
Towards the Development of a Comprehensive Nuclear System Analysis Code Based on Two Fluid Model: Starting with an Isentropic Approach
1 Introduction
2 One-Dimentional Two-Phase Two-Fluid Model
3 Numerical and Solution Method
4 Test Results
4.1 Ransom's Water Faucet Problem
4.2 Manometer Oscillation Problem
4.3 Phase Separation Problem or Sedimentation Problem
5 Conclusion
References
Validation of the SPACE Code Through Simulated Accident Scenarios in SMART-ITL: A Focus on Pressurizer Safety Valve Break and Safety Injection Line Break Concurrent with TLOSHR
1 Introduction
2 SBLOCA of PSV
2.1 Overview of SPACE
2.2 Overview of SMART-ITL
2.3 Overview of PSV LOCA
2.4 Nodalization of the SMART-ITL
2.5 Steady-State Condition
2.6 Results and Discussion
3 SBLOCA of SIL Concurrent with TLOSHR (DEC Scenario)
3.1 Overview of SIL LOCA
3.2 Nodalization of the SMART-ITL
3.3 Steady-State Condition
3.4 Results and Discussion
4 Conclusion
Appendix
References
CFD Validation of Forced and Natural Convection for the Open Phase of IAEA Benchmark CRP - I31038
1 Introduction
2 Benchmark Specification
3 Numerical Model and Results
4 Conclusions
References
A CFD Approach to Mimic the Molten Corium-Concrete Interaction Phenomena: Effects of the Thermal Boundary Conditions
1 Introduction
2 Model Description and Analysis
2.1 Modelling Concrete Melting with Molten Corium
3 Governing Equations
4 Multi-Region Coupling
5 Numerical Model Development
6 Numerical Setup and Mesh Independence Study
7 Numerical Model Validation with Experimental Data
8 Results and Discussions
9 Thermal Boundary Conditions
10 Summary and Conclusions
References
Bare Rod Bundles Fuel Assembly Coolant Flow Analysis Through a Hybrid-Based CFD Numerical Simulation
1 Introduction
1.1 The Hooper Case
1.2 Computational Fluid Dynamics (CFD)
1.3 Case Description
2 Numerical Methodology
2.1 Flow Configuration
2.2 Boundary Conditions
2.3 Mesh Generation
2.4 Turbulence Modelling
2.5 Flow Parameters
3 Results and Discussion
3.1 Qualitative Comparison
3.2 Velocity Field Qualitative Comparison
3.3 Velocity Profile Comparison
3.4 Power Spectral Density Comparison
4 Conclusion
References
Turbulent Heat Flux Modelling by Using Elliptic-Blending k-e-?-f RANS Model
1 Introduction
2 Modelling Rationale
3 Results
3.1 Differentially Heated Square Cavity
3.2 Rayleigh-Bénard Convection
4 Conclusions
References
Multi-layered Bubble Identification in an Air-Water Two-Phase Flow
1 Introduction
2 Experimental Facility and Data Analysis
2.1 Experimental Setup
2.2 Feature Extraction and Bubble Detection
3 Results and Discussion
4 Conclusion
References
Experimental Study of Isothermal Vertical Slug Flow
1 Introduction
2 Experimental Setup
3 Image Processing
4 Results - Time Averaged Taylor Bubble Shape
5 Results - Disturbance Waves on Bubble Surface
6 Conclusions
References
Flow Reconstruction of Single-Phase Planar Jet from Sparse Temperature Measurements
1 Introduction
2 Methodology
2.1 Turbulent Planar Flow and Data Generation
2.2 Flow Reconstruction by Data-Driven
2.3 Flow Reconstruction by PINN
2.4 Flow Reconstruction by PINN
3 Results and Discussion
3.1 Dimensionality Reduction and Sensor Arrangements
3.2 Framework by Data-Driven
3.3 Framework by PINN
4 Conclusions
References
Numerical Investigation of the Breath Figure Spot Characteristics in a Jet Impingement Condensation Process
1 Introduction
2 Numerical Modeling
2.1 Governing Equations
2.2 Grid Independence Test
2.3 Model Validation
3 Results and Discussion
3.1 Flow Field Characterization
3.2 Thermal and Species Field Characterization
4 Conclusion
References
A CFD Simulation of Bubble Burst at Free Surface
1 Introduction
2 Experimental Literature
2.1 Film Droplets
2.2 Jet Drop
3 CFD Simulation
3.1 Geometry, Meshing, and Configuration
3.2 Results and Challenges
4 Conclusions
References
Numerical Prediction of Mixed Convection Flow Regime in Low-Prandtl Number Fluids
1 Introduction
1.1 Analysis Methodology and Numerical Modelling
1.2 Implications of the Nondimensional Numbers
2 Case Description
2.1 Flow Parameters
2.2 Numerical Solution
2.3 Mesh Generation
3 Results and Discussion
3.1 Qualitative Results Assessment
3.2 Quantitative Results Assessment
4 Conclusions
References
Numerical Prediction of Heat Transfer for Supercritical Carbon Dioxide in Horizontal Circular Tubes
1 Introduction
2 Literature Review
3 Methodology
3.1 Geometry
3.2 Equations and Numerical Model
3.3 Enhanced Wall Treatments and y+ Values
3.4 Carbon Dioxide Properties
3.5 Boundary Conditions and Dataset for Validation
4 Results
5 Conclusions
References
An Efficient Approach for Benchmarking Axial Flow-Induced Vibration for Nuclear Applications
1 Introduction
2 Literature Review
3 Methodologies
3.1 Mathematical Models
3.2 Numerical Solutions
3.3 Experiment Setup
4 Results and Discussions
5 Conclusions
References
Numerical Prediction of Flow and Heat Transfer in a Molten Corium Pool
1 Introduction
2 Literature Review
2.1 BALI Experiments
3 Numerical Methodology
3.1 Computational Domain
3.2 Boundary Conditions
3.3 Flow Parameters
3.4 Numerical Model
4 Results and Discussion
5 Conclusions
References
Numerical Prediction of Natural Circulation Heat Transfer for Supercritical Carbon Dioxide
1 Introduction
2 Recent Supercritical CO2 Numerical Analyses
3 Reference Experimental Data
4 Methodology
5 Results
6 Conclusion
References
Prediction of Thermodynamic Properties and Phase Behaviour of CANDU Nuclear Reactor Fluid Coolant Using the SAFT-VR Mie Equation of State
1 Introduction
2 Methodology
2.1 Statistical Associating Fluid Theory
2.2 SAFT-VR Mie Equation of State
3 Results and Discussion
3.1 Pure Component Models
3.2 Binary Mixtures Models Performance
4 Conclusions
References
Derivation of a Condensation Heat Transfer Model for Light Water Reactor Applications Using Machine Learning Techniques
1 Introduction
2 Materials and Methods
2.1 The ANN Model Development
3 Results
4 Conclusion
References
Reactor Physics
A Study on Soluble Boron Control During Load-Follow Operation Using Sliding Mode Observer in APR1400
1 Introduction
2 Reactor Description
3 Sliding Mode Observer Model
4 Results and Simulations
5 Conclusions and Future Work
References
VERA Solution of Zero Power Physics Tests (ZPPT) Using DeCART2D - MASTER
1 Introduction
2 Physical Reactor ZPPT Problem Description
2.1 Single-Assembly Description
2.2 Full-Core Description
3 Methodology
4 Results
5 Conclusions
References
Neutron Voltaics: Diamond-Based Direct Energy Conversion in Nuclear Reactors
1 Introduction
2 Methods and Results
2.1 Energy from the Fission Process
2.2 Reactor Geometric Considerations of DEC
2.3 Isotopic Compatibility of DEC with the Nuclear Reactor
2.4 Diamond p-n Junction Compatibility with Nuclear Reactor
3 Conclusion
References
Neutronic Analysis of Annular & MOX Fuel Designs for SMART Core Using DeCART2D/MASTER Codes
1 Introduction
1.1 SMART Core Design and Assembly Models
2 Methodology
2.1 Computational Tools
2.2 Investigated Fuels
2.3 Fuel Rod Geometry Design
3 Results and Discussion
3.1 Neutron Multiplication Factor
3.2 Power Peaking Factor
3.3 Maximum Fuel Temperature
3.4 Fuel Burnup
3.5 Gas Production (Xenon-135 and Samarium-149)
4 Conclusions
References
A Neutronic Study on Safety Characteristics of Fast Spectrum Stable Salt Reactor (SSR)
1 Introduction
2 Study Design
2.1 SSR Core Structural Design
2.2 Salt and Material Considerations
2.3 Operating Conditions and Power
3 Methods and Results
3.1 Core Depletion Analysis
3.2 SSR Safety Characteristics
3.3 Description of Transient Analyses for SSR
3.4 Results
4 Conclusions
References
An Exposition of the Discrete Ordinates Method for Complex Irregular Geometries Utilizing a Structured Mesh
1 Introduction
2 Complex, Irregular Geometries
3 Numerical Examples
3.1 Absorbing, Emitting and Isotropically Scattering Medium in a Quadrilateral Enclosure
3.2 Isotropically Scattering Medium in a Quadrilateral Enclosure Under Radiative Equilibrium
4 Conclusions
References
Neutronic Analysis of the AP1000 Pressurized Water Reactor
1 Introduction
2 AP1000 Reactor Core Model
2.1 The OpenMC Monte Carlo Code
2.2 Model Development
3 Simulations
4 Simulation Results
4.1 Neutron Spectrum
4.2 Effective Multiplication Factor
4.3 Uranium Isotopes
4.4 Plutonium Isotopes
4.5 Xenon and Samarium Isotopes
5 Conclusions
References
Neutronic Analysis of the Westinghouse Demonstration Lead Fast Reactor
1 Introduction
2 Lead-Cooled Fast Reactors
2.1 Technology Overview
2.2 Fast Neutron Spectrum
2.3 Lead Coolant Properties
3 Uranium Nitride Fuel
4 Simulation
4.1 OpenMC Monte Carlo Code
4.2 Westinghouse DLFR Core Model
4.3 Simulation Settings
5 Simulation Results
5.1 Effective Neutron Multiplication Factor
5.2 Neutron Flux
5.3 Conversion Ratio
5.4 Actinides Mass Change
6 Conclusions
References
Safety and Severe Accidents
THAI Database for Validation of LWR Containment Safety Analyses Codes
1 Introduction
2 THAI Experimental Programme
3 THAI Experimental Database
3.1 Thermal-Hydraulic Tests
3.2 Water Pool Hydrodynamics (WH)
3.3 Hydrogen Recombiner (HR)
3.4 Hydrogen Deflagration (HD)
3.5 Fission Products Behaviour - Gaseous Iodine
3.6 Fission Products Behaviour - Aerosols
4 Conclusions and Perspectives
References
Safeguarding Biodiversity and Future Generations: An Application of RESRAD Codes for Nuclear Emergency Planning and Response
1 Introduction
2 Application of the RESRAD Codes in Safeguarding Biodiversity and Future Generation
2.1 Determination of Core Inventory and Source Term
2.2 Application of RESRAD in Safeguarding Biodiversity and Future Generation
2.3 Pathway Analysis for Deriving Soil Concentration Guides
2.4 Probabilistic Analysis
2.5 Recommended Minimum Site Specific Parameters for Use
3 Conclusion
References
Structural Health Monitoring of Nuclear Site Facilities Using Optimal Sensor Placement for Damage Detection and Prediction of Failure
1 Introduction
2 Literature Review on Model Order Reduction Techniques and Optimal Sensor Placement
3 Theoretical Background
3.1 D-Optimal Method
3.2 System Equivalent Reduction Expansion Process (SEREP)
4 Problem Formulation with Examples
4.1 Example 1: Clamped-Clamped Beam Under Harmonic Force
4.2 Example 2: Cantilever Beam Under Impact
4.3 Example 3: All Edges Clamped, Rectangular Plate Under Harmonic Force
5 Conclusion
References
Validation of a MELCOR Model of Reactor Cavity Cooling System Through Support of CFD Simulation
1 Introduction
2 Materials and Methods
2.1 MELCOR Model
2.2 CFD Model
3 Results and Discussion
4 Conclusions
References
Towards CFD Predictions of Radioactive Pollutants Dispersion Under Arabian Peninsula Environmental Conditions
1 Introduction
2 Literature Review
2.1 Modeling Scale
2.2 Why CFD
2.3 Prior Gas Dispersion Modelling Studies
3 CFD Validation Test Case A
3.1 Domain Setting and Boundary Conditions
3.2 Test Case A Results and Discussion
4 CFD Validation Test Case B
4.1 Domain Setting and Boundary Conditions
4.2 Mesh Sensitivity
4.3 Test Case B Results and Discussion
5 Conclusion
References
The Assessment of Environmental Radioactivity in Haqal Village in Saudi Arabia and Its Impact on Public Health
1 Introduction
2 Literature Review
3 Problem Statement
4 Study Methodology
4.1 Sample Collection and Preparation
4.2 Background Radiation Assessment
4.3 Radioactivity Analysis
5 Results
5.1 Water Samples
5.2 Soil and Rocks Samples
5.3 Background Evaluation
6 Conclusions
References
Research Reactors
The Site Selection of a Nuclear Reactor Near the Oil and Gas Exploration Region
1 Introduction
2 Seismic Data Acquistion
2.1 Geological Structure
2.2 Wave Equation
3 Short-Time Fourier Transform
4 Conclusion
References
Characteristics and Capabilities of the Saudi Low Power Research Reactor (LPRR)
1 Introduction
2 Reactor Core Design
3 The Saudi LPRR Capabilities and Applications
3.1 Reactor Physics Experiments
3.2 Health Physics and Radiation Protection Dosimetry
3.3 Irradiation Facilities, Services and Labs
3.4 Neutron Beam Facilities
4 Conclusion
References
Multipurpose Research Reactor for Countries with Ambitions
1 Introduction - What is a Research Reactor?
2 Applications of Research Reactor and its Justification
3 Ancillary Infrastructure and Staffing
4 Applications of the Research Reactor
4.1 Production of Medical and Industrial Radioisotopes
4.2 Irradiation Services
4.3 Analytical Techniques
4.4 Neutron Beam Techniques
4.5 Education and Training
5 Recommendations Based upon Experience with MARIA Reactor Operation
6 Conclusions
References
Past, Present and Future of Research Reactor(s) in Slovenia
1 Past and Present - TRIGA Reactor
2 New Research Reactor?
3 Conclusions
References
Fusion and Advanced Reactors
Evaluation of Hydrogen Production Feasibility Utilizing System Integrated Modular Advanced Reactor (SMART) in Saudi Arabia
1 Introduction
1.1 SMART Reactor Design
2 Methodology
3 Results and Discussion
3.1 Conventional Electrolysis (CE)
3.2 Discount Rate Sensitivity Analysis
3.3 Interest Rate Sensitivity Analysis
4 Conclusions
References
Effect of Irradiation's Angle of Incidence on the Sputtering Energy Threshold of Beryllium Metal of the ITER First Wall
1 Introduction
2 Simulation Methods and Parameters
3 Results and Discussion
3.1 Beryllium Irradiated by He+ ions
3.2 Beryllium Irradiated by T+ ions
3.3 Beryllium Irradiated by D+ ions
4 Conclusions
References
Preliminary Design of NDP-400: Economical Heat Generation for Efficient Desalination
1 Introduction
2 Core Design
2.1 Nuclear Design
2.2 Thermal-Hydraulic Design
3 Nuclear Steam Supply System Design
3.1 Reactor Coolant System Design
3.2 Mechanical Design
4 Safety Analysis
4.1 ESF
4.2 Total Loss of Reactor Coolant Flow Accident
5 Conclusions
References
Microreactor Applications with Proposed Designs for Saudi Arabia
1 Introduction
2 The Line
2.1 Application
2.2 Design
3 Microreactor Station
3.1 Application
3.2 Design
4 Gas Refinery Station
4.1 Application
4.2 Design
5 Mining Industry
5.1 Application
5.2 Design
6 Remote Areas
6.1 Application
6.2 Design
7 Summary
References
How Reactor Scale Affects Nuclear Power Plants Siting in Saudi Arabia
1 Introduction
2 Geospatial Filtering
2.1 Natural Hazards
2.2 Population Density Considerations
2.3 Water Access
2.4 Existing Infrastructure
3 Results and Discussions
4 Conclusions
References
The Prospect of Nuclear Power Integrated Desalination Plants in Saudi Arabia
1 Literature Review
2 Introduction
3 Economics
3.1 Conventional Desalination Plant
3.2 Nuclear Desalination Plant
3.3 Conventional vs Nuclear
4 Environmental Impact
4.1 Paris Agreement
4.2 Current Environmental Impact
4.3 Future Environmental Impact
5 Lifetime
6 Safety
7 Recommendations
8 Conclusion
References
Feasibility Study of Using Nuclear Energy to Produce Hydrogen Fuel in Saudi Arabia
1 Introduction
2 Saudi Arabia's Energy Landscape
2.1 Overview of Saudi Arabia's Energy Consumption
2.2 Current Energy Sources Used in Saudi Arabia
2.3 Challenges in Saudi Arabia's Energy Sector and the Need for a Shift
3 Nuclear Energy for Hydrogen Production
3.1 Technical Details of Using Nuclear Energy for Hydrogen Production
3.2 Advantages of Using Nuclear Energy for Hydrogen Production
4 Feasibility of Implementing Nuclear Energy for Hydrogen Production in Saudi Arabia
4.1 Overview of the Country's Planned Nuclear Infrastructure
4.2 Assessment of the Technical and Economic Feasibility
5 Recommendations for Saudi Arabia
6 Conclusions
References
Author Index

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