Fusion Energy Technology R&D Priorities examines the current landscape of fusion technology. With a strong focus on technological advances, the book considers technical challenges and priorities to further the development of fusion research.
Beginning with an introduction to fusion technology research and development, the book then presents an overview of basic magnetic fusion concepts, experimental facilities, and fusion materials R&D. Subsequent chapters then take a deep dive into capabilities of potential neutron sources for materials testing, plasma facing components, and blanket and tritium systems. Vacuum vessels and shields, and superconducting magnets are also highlighted, before concluding with modelling techniques, computational tools, safety features, and environmental considerations.
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.
1. Chapter 1 : Introduction - p. Page x 2. Chapter 2 : Overview of basic magnetic fusion concepts - p. Page 4 3. Chapter 3 : Fusion materials R&D - p. Page 14 4. Chapter 3.1 : Status and future development of Japanese reduced activation ferritic/martensitic steel F82H - p. Page xix 5. Chapter 3.2 : Status of European reduced activation ferritic/martensitic steel EUROFER97 - p. Page 24 6. Chapter 3.3 : Status of U.S. reduced activation bainitic steel - p. Page 36 7. Chapter 3.4 : Tungsten alloys R&D program at KIT - p. Page 51 8. Chapter 3.5 : Tungsten heavy alloys - p. Page 57 9. Chapter 3.6 : Dispersion-strengthened tungsten alloy composites - p. Page 63 10. Chapter 3.7 : Tungsten alloy developments in Japan - p. Page 68 11. Chapter 3.8 : SiC/SiC composites - p. Page 74 12. Chapter 3.9 : Vanadium alloys - p. Page 83 13. Chapter 3.10 : Modelling and simulation of fusion materials - p. Page 90 14. Chapter 4 : Capabilities of potential neutron sources for fusion materials testing - p. Page 95 15. Chapter 4.1 : The U.S. approach to a fusion prototypic neutron source - p. Page c 16. Chapter 4.2 : DEMO Oriented Neutron Source (IFMIF-DONES)—Spain - p. Page 102 17. Chapter 4.3 : Fusion neutron source (A-FNS)—Japan - p. Page 112 18. Chapter 4.4 : High intensity neutron generator (HINEG-CAS)—China - p. Page 120 19. Chapter 4.5 : Axisymmetric mirror linear neutron source - p. Page 130 20. Chapter 5 : Plasma facing components - p. Page 138 21. Chapter 5.1 : Challenges of plasma material interactions - p. Page cxlii 22. Chapter 5.2 : Helium-cooled divertor option and limitations - p. Page 152 23. Chapter 5.3 : Water-cooled divertor option and limitations - p. Page 160 24. Chapter 5.4 : Liquid metal walls - p. Page 167 25. Chapter 6 : Plasma diagnostics, heating, and control - p. Page 176 26. Chapter 6.1 : Plasma diagnostics - p. Page 176 27. Chapter 6.2 : Plasma heating technology - p. Page 186 28. Chapter 6.3 : Current drive technology - p. Page 191 29. Chapter 7 : Breeding blanket and tritium system - p. Page 198 30. Chapter 7.1 : Blanket options - p. Page cc 31. Chapter 7.2 : Dual-coolant lead lithium blanket - p. Page 202 32. Chapter 7.3 : The water-cooled lithium–lead breeding blanket - p. Page 208 33. Chapter 7.4 : Flibe/Flinabe blanket - p. Page 214 34. Chapter 7.5 : Ceramic breeder blankets - p. Page 221 35. Chapter 7.6 : Breeding potential and tritium self-sufficiency - p. Page 231 36. Chapter 7.7 : Heat extraction, recovery, and power cycle - p. Page 238 37. Chapter 7.8 : Tritium modeling, extraction, migration, and accountability - p. Page 244 38. Chapter 8 : Vacuum vessel and shielding system - p. Page 249 39. Chapter 8.1 : ITER vacuum vessel - p. Page 249 40. Chapter 8.2 : Vacuum vessel R&D needs for power plants - p. Page 261 41. Chapter 8.3 : Shielding system and radiation protection - p. Page 267 42. Chapter 8.4 : ASME boiler & pressure vessel code Section III Division 4 construction rules for fusion energy - p. Page 273 43. Chapter 9 : Safety features - p. Page 278 44. Chapter 9.1 : US fusion safety activities - p. Page cclxxx 45. Chapter 9.2 : EU and French safety assessments - p. Page 284 46. Chapter 9.3 : Safety features—United Kingdom - p. Page 287 47. Chapter 9.4 : Safety features—Japan - p. Page 293 48. Chapter 9.5 : Safety assessment in China - p. Page 299 49. Chapter 9.6 : Safety assessments in the Republic of Korea - p. Page 306 50. Chapter 10 : Environmental and social issues - p. Page 311 51. Chapter 10.1 : Potential radwaste management approaches: Disposal, recycling, and clearance—United States - p. Page cccxv 52. Chapter 10.2 : Fusion radwaste management approaches in Europe - p. Page 322 53. Chapter 10.3 : Fusion radwaste management approaches in Japan - p. Page 327 54. Chapter 10.4 : Radwaste management approaches in China - p. Page 332 55. Chapter 10.5 : Recycling of fusion material and its predicted nuclide distribution - p. Page 337 56. Chapter 10.6 : Socially engaged approach to fusion technology development - p. Page 344 57. Index - p. Page 349
Fusion Energy Technology R&D Priorities examines the current landscape of fusion technology. With a strong focus on technological advances, the book considers technical challenges and priorities to further the development of fusion research.
Beginning with an introduction to fusion technology research and development, the book then presents an overview of basic magnetic fusion concepts, experimental facilities, and fusion materials R&D. Subsequent chapters then take a deep dive into capabilities of potential neutron sources for materials testing, plasma facing components, and blanket and tritium systems. Vacuum vessels and shields, and superconducting magnets are also highlighted, before concluding with modelling techniques, computational tools, safety features, and environmental considerations.
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.
1. Chapter 1 : Introduction - p. Page x 2. Chapter 2 : Overview of basic magnetic fusion concepts - p. Page 4 3. Chapter 3 : Fusion materials R&D - p. Page 14 4. Chapter 3.1 : Status and future development of Japanese reduced activation ferritic/martensitic steel F82H - p. Page xix 5. Chapter 3.2 : Status of European reduced activation ferritic/martensitic steel EUROFER97 - p. Page 24 6. Chapter 3.3 : Status of U.S. reduced activation bainitic steel - p. Page 36 7. Chapter 3.4 : Tungsten alloys R&D program at KIT - p. Page 51 8. Chapter 3.5 : Tungsten heavy alloys - p. Page 57 9. Chapter 3.6 : Dispersion-strengthened tungsten alloy composites - p. Page 63 10. Chapter 3.7 : Tungsten alloy developments in Japan - p. Page 68 11. Chapter 3.8 : SiC/SiC composites - p. Page 74 12. Chapter 3.9 : Vanadium alloys - p. Page 83 13. Chapter 3.10 : Modelling and simulation of fusion materials - p. Page 90 14. Chapter 4 : Capabilities of potential neutron sources for fusion materials testing - p. Page 95 15. Chapter 4.1 : The U.S. approach to a fusion prototypic neutron source - p. Page c 16. Chapter 4.2 : DEMO Oriented Neutron Source (IFMIF-DONES)—Spain - p. Page 102 17. Chapter 4.3 : Fusion neutron source (A-FNS)—Japan - p. Page 112 18. Chapter 4.4 : High intensity neutron generator (HINEG-CAS)—China - p. Page 120 19. Chapter 4.5 : Axisymmetric mirror linear neutron source - p. Page 130 20. Chapter 5 : Plasma facing components - p. Page 138 21. Chapter 5.1 : Challenges of plasma material interactions - p. Page cxlii 22. Chapter 5.2 : Helium-cooled divertor option and limitations - p. Page 152 23. Chapter 5.3 : Water-cooled divertor option and limitations - p. Page 160 24. Chapter 5.4 : Liquid metal walls - p. Page 167 25. Chapter 6 : Plasma diagnostics, heating, and control - p. Page 176 26. Chapter 6.1 : Plasma diagnostics - p. Page 176 27. Chapter 6.2 : Plasma heating technology - p. Page 186 28. Chapter 6.3 : Current drive technology - p. Page 191 29. Chapter 7 : Breeding blanket and tritium system - p. Page 198 30. Chapter 7.1 : Blanket options - p. Page cc 31. Chapter 7.2 : Dual-coolant lead lithium blanket - p. Page 202 32. Chapter 7.3 : The water-cooled lithium–lead breeding blanket - p. Page 208 33. Chapter 7.4 : Flibe/Flinabe blanket - p. Page 214 34. Chapter 7.5 : Ceramic breeder blankets - p. Page 221 35. Chapter 7.6 : Breeding potential and tritium self-sufficiency - p. Page 231 36. Chapter 7.7 : Heat extraction, recovery, and power cycle - p. Page 238 37. Chapter 7.8 : Tritium modeling, extraction, migration, and accountability - p. Page 244 38. Chapter 8 : Vacuum vessel and shielding system - p. Page 249 39. Chapter 8.1 : ITER vacuum vessel - p. Page 249 40. Chapter 8.2 : Vacuum vessel R&D needs for power plants - p. Page 261 41. Chapter 8.3 : Shielding system and radiation protection - p. Page 267 42. Chapter 8.4 : ASME boiler & pressure vessel code Section III Division 4 construction rules for fusion energy - p. Page 273 43. Chapter 9 : Safety features - p. Page 278 44. Chapter 9.1 : US fusion safety activities - p. Page cclxxx 45. Chapter 9.2 : EU and French safety assessments - p. Page 284 46. Chapter 9.3 : Safety features—United Kingdom - p. Page 287 47. Chapter 9.4 : Safety features—Japan - p. Page 293 48. Chapter 9.5 : Safety assessment in China - p. Page 299 49. Chapter 9.6 : Safety assessments in the Republic of Korea - p. Page 306 50. Chapter 10 : Environmental and social issues - p. Page 311 51. Chapter 10.1 : Potential radwaste management approaches: Disposal, recycling, and clearance—United States - p. Page cccxv 52. Chapter 10.2 : Fusion radwaste management approaches in Europe - p. Page 322 53. Chapter 10.3 : Fusion radwaste management approaches in Japan - p. Page 327 54. Chapter 10.4 : Radwaste management approaches in China - p. Page 332 55. Chapter 10.5 : Recycling of fusion material and its predicted nuclide distribution - p. Page 337 56. Chapter 10.6 : Socially engaged approach to fusion technology development - p. Page 344 57. Index - p. Page 349
