Fusion Energy Technology R&D Priorities
- 1st Edition - November 17, 2024
- Latest edition
- Editor: Laila El-Guebaly
- Language: English
Fusion Technology R&D Priorities examines the current landscape of fusion technology. With a strong focus on technological advances, this book considers technical challenge… Read more
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Description
Description
Fusion Technology R&D Priorities examines the current landscape of fusion technology. With a strong focus on technological advances, this book considers technical challenges and priorities to further the development of fusion research.
Beginning with an introduction to fusion technology research and development, this book then presents an overview of basic magnetic fusion concepts and worldwide pathways to fusion energy. Subsequent chapters then take a deep dive into fusion materials R&D, capabilities of potential neutron sources for materials testing, plasma facing components, and plasma diagnostics, heating, and control. Breeding blanket and tritium system, vacuum vessels, and the shielding system are also highlighted, before concluding with safety features and environmental and social issues.
Presenting the most advanced developments in nuclear fusion R&D, this is an essential read for researchers and engineers interested in nuclear energy and fusion technology.
Key features
Key features
- Presents the latest advances and developments in fusion science and technology
- Outlines the R&D priorities and critical issues that are foundational to the further development of fusion energy technologies
- Identifies technical fusion challenges and considers future perspectives
- Reviews the present-day status of essential R&D programs that support fusion for energy
Readership
Readership
Advanced researchers and engineers interested in nuclear energy and fusion technology.
Table of contents
Table of contents
1. Introduction
2. Overview of Basic Magnetic Fusion Concepts
3. Fusion Materials R&D
Overview
Reduced-Activation Ferritic/Martensitic Steels: F82H Steel
Reduced-Activation Ferritic/Martensitic Steels: EUROFER97 Steel
Reduced-Activation Ferritic/Martensitic Steels: Bainitic Steel
Potential Tungsten Alloys: Tungsten alloys R&D program at KIT
Potential Tungsten Alloys: Tungsten Heavy Alloys
Potential Tungsten Alloys: Dispersion-Strengthened Tungsten Alloy Composites
Potential Tungsten Alloys: Tungsten alloy developments in Japan
SiC/SiC Composites
Vanadium Alloys
Modeling and Simulation
4. Capabilities of Potential Neutron Sources for Fusion Materials Testing
Overview
Potential Fusion neutron sources: The US Approach to a Fusion Prototypic Neutron Source
Potential Fusion neutron sources: DEMO Oriented Neutron Source (IFMIF-DONES) - EU
Potential Fusion neutron sources: Fusion Neutron Source (A-FNS) - Japan
Potential Fusion neutron sources: High Intensity Neutron Generator (HINEG-CAS) – China
Potential Fusion neutron sources: Axisymmetric Mirror Linear Neutron Source
5. Plasma Facing Components
Overview
Challenges of Plasma Material Interactions
Divertor System: Helium-cooled Divertor Option and Limitations
Divertor System: Water-Cooled Divertor Option and Limitations
Liquid Metal Wall
6. Plasma Diagnostics, Heating and Control
Overview
Plasma Diagnostics
Plasma Heating Technology
Current Drive Technology
7. Breeding Blanket and Tritium System
Overview
Blanket options:
Liquid Breeder Blankets: Dual-Coolant Lead Lithium Blanket
Liquid Breeder Blankets: Water-Cooled Lead Lithium Blanket
Liquid Breeder Blankets: Flibe/Flinabe Blanket
Ceramic Breeder Blankets
Breeding Potential and Tritium Self-Sufficiency
Heat Extraction, Recovery and Power Cycle
Tritium Modeling, Extraction, Migration and Accountability
8. Vacuum Vessel and Shielding System
Overview
Vacuum Vessel: ITER Vacuum Vessel
Vacuum Vessel: Power Plant Vacuum Vessel
Shielding System and Radiation Protection
ASME Construction Rules for Fusion
9. Safety Features
Overview
Safety Requirements, Approaches, Accident Scenarios, Code/Standards, and R&D: United States
Safety Requirements, Approaches, Accident Scenarios, Code/Standards, and R&D: Europe and France
Safety Requirements, Approaches, Accident Scenarios, Code/Standards, and R&D: United Kingdom
Safety Requirements, Approaches, Accident Scenarios, Code/Standards, and R&D: Japan
Safety Requirements, Approaches, Accident Scenarios, Code/Standards, and R&D: China
Safety Requirements, Approaches, Accident Scenarios, Code/Standards, and R&D: Korea
10. Environmental and Social Issues
Overview
Potential Radwaste Management Approaches: Disposal, Recycling, and Clearance: United States
Potential Radwaste Management Approaches: Disposal, Recycling, and Clearance: Europe
Potential Radwaste Management Approaches: Disposal, Recycling, and Clearance: Japan
Potential Radwaste Management Approaches: Disposal, Recycling, and Clearance: China
Recycling of Fusion Material and its Predicted Nuclide Distribution
Socially Engaged Approach to Fusion Technology Development
2. Overview of Basic Magnetic Fusion Concepts
3. Fusion Materials R&D
Overview
Reduced-Activation Ferritic/Martensitic Steels: F82H Steel
Reduced-Activation Ferritic/Martensitic Steels: EUROFER97 Steel
Reduced-Activation Ferritic/Martensitic Steels: Bainitic Steel
Potential Tungsten Alloys: Tungsten alloys R&D program at KIT
Potential Tungsten Alloys: Tungsten Heavy Alloys
Potential Tungsten Alloys: Dispersion-Strengthened Tungsten Alloy Composites
Potential Tungsten Alloys: Tungsten alloy developments in Japan
SiC/SiC Composites
Vanadium Alloys
Modeling and Simulation
4. Capabilities of Potential Neutron Sources for Fusion Materials Testing
Overview
Potential Fusion neutron sources: The US Approach to a Fusion Prototypic Neutron Source
Potential Fusion neutron sources: DEMO Oriented Neutron Source (IFMIF-DONES) - EU
Potential Fusion neutron sources: Fusion Neutron Source (A-FNS) - Japan
Potential Fusion neutron sources: High Intensity Neutron Generator (HINEG-CAS) – China
Potential Fusion neutron sources: Axisymmetric Mirror Linear Neutron Source
5. Plasma Facing Components
Overview
Challenges of Plasma Material Interactions
Divertor System: Helium-cooled Divertor Option and Limitations
Divertor System: Water-Cooled Divertor Option and Limitations
Liquid Metal Wall
6. Plasma Diagnostics, Heating and Control
Overview
Plasma Diagnostics
Plasma Heating Technology
Current Drive Technology
7. Breeding Blanket and Tritium System
Overview
Blanket options:
Liquid Breeder Blankets: Dual-Coolant Lead Lithium Blanket
Liquid Breeder Blankets: Water-Cooled Lead Lithium Blanket
Liquid Breeder Blankets: Flibe/Flinabe Blanket
Ceramic Breeder Blankets
Breeding Potential and Tritium Self-Sufficiency
Heat Extraction, Recovery and Power Cycle
Tritium Modeling, Extraction, Migration and Accountability
8. Vacuum Vessel and Shielding System
Overview
Vacuum Vessel: ITER Vacuum Vessel
Vacuum Vessel: Power Plant Vacuum Vessel
Shielding System and Radiation Protection
ASME Construction Rules for Fusion
9. Safety Features
Overview
Safety Requirements, Approaches, Accident Scenarios, Code/Standards, and R&D: United States
Safety Requirements, Approaches, Accident Scenarios, Code/Standards, and R&D: Europe and France
Safety Requirements, Approaches, Accident Scenarios, Code/Standards, and R&D: United Kingdom
Safety Requirements, Approaches, Accident Scenarios, Code/Standards, and R&D: Japan
Safety Requirements, Approaches, Accident Scenarios, Code/Standards, and R&D: China
Safety Requirements, Approaches, Accident Scenarios, Code/Standards, and R&D: Korea
10. Environmental and Social Issues
Overview
Potential Radwaste Management Approaches: Disposal, Recycling, and Clearance: United States
Potential Radwaste Management Approaches: Disposal, Recycling, and Clearance: Europe
Potential Radwaste Management Approaches: Disposal, Recycling, and Clearance: Japan
Potential Radwaste Management Approaches: Disposal, Recycling, and Clearance: China
Recycling of Fusion Material and its Predicted Nuclide Distribution
Socially Engaged Approach to Fusion Technology Development
Product details
Product details
- Edition: 1
- Latest edition
- Published: November 20, 2024
- Language: English
About the editor
About the editor
LE
Laila El-Guebaly
Before retiring from the University of Wisconsin-Madison (UW) as a Distinguished Research Professor, Dr El-Guebaly was the:
Nuclear Group Leader at the UW Fusion Technology Institute
Nuclear Task Leader for the multi-institutional ARIES and FNSF fusion projects
U.S. Contact Person for the IEA Task on Fusion Radioactive Waste Studies.
Her primary interest is in the area of neutronics, activation, radiation shielding, and radwaste management for both D-T and D-3He fueled plants for terrestrial and space applications. She has extensive experience in experimental and power plant designs and was involved in the conceptual designs of numerous national and international fusion concepts: magnetic (tokamaks, spherical tori, stellarators, FRC, and tandem mirrors) and inertial (laser, heavy ion, and Z-pinch). She participated in over 25 multi-institutional fusion design studies and was also involved in several small-scale projects focusing on space, advanced D-3He fuel, component testing, radioactive waste management, proliferation-resistance, and non-electric applications. She published extensively in fusion contexts, authoring ~300 technical reports and scientific publications in U.S. and international refereed journals and contributing nine chapters on fusion-related topics to books on nuclear energy. She now currently offers consulting in several areas of fusion technologies, including the environmental aspect of fusion.
Affiliations and expertise
Distinguished Research Professor Emerita, University of Wisconsin-Madison, USAView book on ScienceDirect
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