12482nam 22006375 450 991087467030332120240720125243.09783031643620(electronic bk.)978303164361310.1007/978-3-031-64362-0(MiAaPQ)EBC31539154(Au-PeEL)EBL31539154(CKB)33101347100041(DE-He213)978-3-031-64362-0(EXLCZ)993310134710004120240720d2024 u| 0engurcnu||||||||txtrdacontentcrdamediacrrdacarrierChallenges and Recent Advancements in Nuclear Energy Systems Proceedings of Saudi International Conference on Nuclear Power Engineering (SCOPE) /edited by Afaque Shams, Khaled Al-Athel, Iztok Tiselj, Andreas Pautz, Tomasz Kwiatkowski1st ed. 2024.Cham :Springer Nature Switzerland :Imprint: Springer,2024.1 online resource (849 pages)Lecture Notes in Mechanical Engineering,2195-4364Includes index.Print version: Shams, Afaque Challenges and Recent Advancements in Nuclear Energy Systems Cham : Springer,c2024 9783031643613 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.This book gathers the latest advances, innovations, and applications in the field of nuclear power engineering, as presented by researchers and engineers at the Saudi International Conference on Nuclear Power Engineering (SCOPE), which was organized by King Fahd University of Petroleum and Minerals (KFUPM), and held in Dhahran, Saudi Arabia on November 13–15, 2023. The contributions encompass topics such as nuclear thermal-hydraulics, reactor physics, nuclear materials, fuel cycle and waste management, safety and severe accidents, fusion and advanced reactors, nuclear applications and radiation processing. The contributions, which were selected through a rigorous international peer-review process, share exciting ideas that will spur novel research directions and foster new multidisciplinary collaborations.Lecture Notes in Mechanical Engineering,2195-4364Nuclear engineeringNuclear fusionRefuse and refuse disposalNuclear EnergyNuclear FusionWaste Management/Waste TechnologyNuclear engineering.Nuclear fusion.Refuse and refuse disposal.Nuclear Energy.Nuclear Fusion.Waste Management/Waste Technology.621.48Shams AfaqueMiAaPQMiAaPQMiAaPQ9910874670303321Challenges and Recent Advancements in Nuclear Energy Systems4183681UNINA