Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research.
1. Chapter 1 Introduction - p. 1 2. References - p. 84 3. Further reading - p. 84 4. Sub Chapter 1.2 Current status and future trends in the world nuclear-power industry - p. 85 5. Chapter 2 Generation IV International Forum (GIF) - p. 111 6. Chapter 3 Very High Temperature Reactor - p. 133 7. Chapter 4 Gas-cooled Fast Reactors (GFRs) - p. 167 8. Chapter 5 Sodium-cooled Fast Reactors (SFRs) - p. 173 9. Chapter 6 Lead-cooled Fast Reactors (LFRs) - p. 195 10. Chapter 7 Homogeneous Molten Salt Reactors (MSRs): The Molten Salt Fast Reactor (MSFR) concept - p. 231 11. Chapter 8 SuperCritical Water-cooled Reactors (SCWRs) - p. 259 12. Chapter 9 Generation IV: United States - p. 287 13. Chapter 10 Generation IV: European Union - p. 303 14. 10.1: Introduction: “EU Energy Union” (2015) and “EU Green Deal” (2020)—Going climate neutral by 2050—Euratom contribution - p. 304 15. 10.2: EURATOM: Research & training; safety of nuclear installations; health and safety (radiation protection); safeguards; radwaste management - p. 310 16. 10.3: Generation-IV: Breakthrough developments in sustainability, safety and performance through multilateral collaboration (GIF, IAEA-INPRO) - p. 320 17. 10.4: Eight high-level goals for generation-IV nuclear energy systems and associated world-wide GIF R&D collaborative effort - p. 328 18. 10.5: Euratom research and training actions in innovative reactor systems and EU “Sustainable Nuclear Energy Technology Platform” - p. 338 19. 10.6: Experimental research reactors in the EU and small modular reactors - p. 344 20. 10.7: Conclusion: The Euratom research and training program—Maintaining EU leadership in nuclear fission developments - p. 350 21. Chapter 11 ESFR SMART: A European Sodium Fast Reactor concept including the European feedback experience and the new safety commitments following Fukushima accident - p. 355 22. Chapter 12 Generation-IV Sodium-cooled Fast Reactor (SFR) concepts in Japan - p. 395 23. Chapter 13 Generation-IV concepts in Korea - p. 419 24. Chapter 14 Generation-IV concepts: China - p. 449 25. Chapter 15 Generation-IV concepts: India - p. 485 26. Chapter 16 The safety and risk assessment of Advanced Reactors (ARs) - p. 519 27. 16.1: Basic safety principles - p. 522 28. 16.2: Safety and reliability goals - p. 522 29. 16.3: Safety objectives and the classification of advanced reactor types - p. 529 30. 16.4: Generic safety objectives and safety barriers - p. 533 31. 16.5: Risk informing safety requirements by learning from prior events - p. 536 32. 16.6: Major technical safety issues - p. 537 33. 16.7: Multiple modules and plant risk - p. 541 34. 16.8: The role of Safety R&D for ARs - p. 541 35. 16.9: Risk informing advanced reactor safety: Quantifying the probability and uncertainty of core damage due to loss of power and cooling - p. 542 36. 16.10: Natural circulation loop and parallel channel thermal-hydraulics - p. 553 37. 16.11: Conclusions - p. 565 38. References - p. 567 39. Further reading - p. 577 40. Chapter 17 Non-proliferation for Advanced Reactors (ARs): Political and Social aspects - p. 579 41. Chapter 18 Thermal aspects of conventional and alternative nuclear fuels - p. 613 42. Chapter 19 Hydrogen production pathways for Generation-IV reactors - p. 665 43. Chapter 20 Small Modular Reactors (SMRs) - p. 681 44. Sub Chapter 20.2 Current status of SMRs and S&MRs development in the world - p. 713 45. Chapter 21 Alternative power cycles for Generation-IV reactors - p. 759 46. Sub Chapter 21.2 Closed Brayton-cycle configurations for Gas-cooled Fast Reactors (GFRs) and Very-High-Temperature Reactors (VHTRs) - p. 777 47. 21.2.1: Introduction - p. 780 48. 21.2.2: Gas turbine as a power-conversion machine - p. 780 49. 21.2.3: Operational experience of helium gas turbines - p. 781 50. 21.2.4: Recent helium gas turbine tests - p. 782 51. 21.2.5: Nuclear power plant closed cycles - p. 783 52. 21.2.6: Helium as a coolant - p. 784 53. 21.2.7: Generation-IV closed-cycle configurations for GFRs and VHTRs - p. 787 54. 21.2.8: Component definition for design point performance - p. 788 55. 21.2.9: Cycle performance design considerations - p. 795 56. 21.2.10: Working fluid for NPP cycle performance, and operation - p. 802 57. 21.2.11: Nuclear power plant controls and operations - p. 814 58. 21.2.12: Risk assessment - p. 819 59. 21.2.13: Technology risk - p. 820 60. 21.2.14: Material technology for high temperature and pressure - p. 820 61. 21.2.15: Working fluid gas management - p. 821 62. 21.2.16: Technology maturity level for components based on selected working fluid - p. 822 63. 21.2.17: Working fluid TRL for turbomachinery components - p. 822 64. 21.2.18: Working fluid TRL for heat exchangers - p. 824 65. 21.2.19: Financial risk - p. 824 66. 21.2.20: Cost of working fluid - p. 824 67. 21.2.21: Sensitivity to pressure ratio and mass flow rate - p. 824 68. 21.2.22: Legislation - p. 827 69. 21.2.23: Other design considerations - p. 827 70. 21.2.24: Future trends - p. 829 71. 21.2.25: Conclusion - p. 830 72. References - p. 832 73. Further reading - p. 834 74. Chapter 22 Regulatory and licensing challenges with Generation-IV nuclear energy systems - p. 837 75. Chapter 23 ITER, the way to fusion energy - p. 867 76. 23.1: Nuclear fusion - p. 870 77. 23.2: The history of the ITER project - p. 873 78. 23.3: A gigantic fusion machine - p. 878 79. 23.4: A pharaonic worksite - p. 887 80. 23.5: Organizing a huge logistics - p. 889 81. 23.6: Delays and budget increases - p. 896 82. 23.7: The management challenge - p. 901 83. 23.8: Nuclear licensing - p. 903 84. 23.9: Safety and waste management - p. 904 85. 23.10: Natural hazards - p. 906 86. 23.11: The impact of ITER on the economy - p. 908 87. 23.12: Will fusion become commercial? - p. 911 88. 23.13: DEMO and the projects after ITER - p. 914 89. 23.14: Alternative technologies - p. 917 90. 23.15: The fusion era - p. 922 91. References - p. 925 92. Further reading - p. 927 93. Appendix A1 Additional materials (layouts, T-s diagrams, basic parameters, photos, etc.) on thermal and nuclear power plants - p. 929 94. References - p. 1058 95. Appendix A2 Comparison of thermophysical properties of reactor coolants - p. 1061 96. Index - p. 1083
Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research.
1. Chapter 1 Introduction - p. 1 2. References - p. 84 3. Further reading - p. 84 4. Sub Chapter 1.2 Current status and future trends in the world nuclear-power industry - p. 85 5. Chapter 2 Generation IV International Forum (GIF) - p. 111 6. Chapter 3 Very High Temperature Reactor - p. 133 7. Chapter 4 Gas-cooled Fast Reactors (GFRs) - p. 167 8. Chapter 5 Sodium-cooled Fast Reactors (SFRs) - p. 173 9. Chapter 6 Lead-cooled Fast Reactors (LFRs) - p. 195 10. Chapter 7 Homogeneous Molten Salt Reactors (MSRs): The Molten Salt Fast Reactor (MSFR) concept - p. 231 11. Chapter 8 SuperCritical Water-cooled Reactors (SCWRs) - p. 259 12. Chapter 9 Generation IV: United States - p. 287 13. Chapter 10 Generation IV: European Union - p. 303 14. 10.1: Introduction: “EU Energy Union” (2015) and “EU Green Deal” (2020)—Going climate neutral by 2050—Euratom contribution - p. 304 15. 10.2: EURATOM: Research & training; safety of nuclear installations; health and safety (radiation protection); safeguards; radwaste management - p. 310 16. 10.3: Generation-IV: Breakthrough developments in sustainability, safety and performance through multilateral collaboration (GIF, IAEA-INPRO) - p. 320 17. 10.4: Eight high-level goals for generation-IV nuclear energy systems and associated world-wide GIF R&D collaborative effort - p. 328 18. 10.5: Euratom research and training actions in innovative reactor systems and EU “Sustainable Nuclear Energy Technology Platform” - p. 338 19. 10.6: Experimental research reactors in the EU and small modular reactors - p. 344 20. 10.7: Conclusion: The Euratom research and training program—Maintaining EU leadership in nuclear fission developments - p. 350 21. Chapter 11 ESFR SMART: A European Sodium Fast Reactor concept including the European feedback experience and the new safety commitments following Fukushima accident - p. 355 22. Chapter 12 Generation-IV Sodium-cooled Fast Reactor (SFR) concepts in Japan - p. 395 23. Chapter 13 Generation-IV concepts in Korea - p. 419 24. Chapter 14 Generation-IV concepts: China - p. 449 25. Chapter 15 Generation-IV concepts: India - p. 485 26. Chapter 16 The safety and risk assessment of Advanced Reactors (ARs) - p. 519 27. 16.1: Basic safety principles - p. 522 28. 16.2: Safety and reliability goals - p. 522 29. 16.3: Safety objectives and the classification of advanced reactor types - p. 529 30. 16.4: Generic safety objectives and safety barriers - p. 533 31. 16.5: Risk informing safety requirements by learning from prior events - p. 536 32. 16.6: Major technical safety issues - p. 537 33. 16.7: Multiple modules and plant risk - p. 541 34. 16.8: The role of Safety R&D for ARs - p. 541 35. 16.9: Risk informing advanced reactor safety: Quantifying the probability and uncertainty of core damage due to loss of power and cooling - p. 542 36. 16.10: Natural circulation loop and parallel channel thermal-hydraulics - p. 553 37. 16.11: Conclusions - p. 565 38. References - p. 567 39. Further reading - p. 577 40. Chapter 17 Non-proliferation for Advanced Reactors (ARs): Political and Social aspects - p. 579 41. Chapter 18 Thermal aspects of conventional and alternative nuclear fuels - p. 613 42. Chapter 19 Hydrogen production pathways for Generation-IV reactors - p. 665 43. Chapter 20 Small Modular Reactors (SMRs) - p. 681 44. Sub Chapter 20.2 Current status of SMRs and S&MRs development in the world - p. 713 45. Chapter 21 Alternative power cycles for Generation-IV reactors - p. 759 46. Sub Chapter 21.2 Closed Brayton-cycle configurations for Gas-cooled Fast Reactors (GFRs) and Very-High-Temperature Reactors (VHTRs) - p. 777 47. 21.2.1: Introduction - p. 780 48. 21.2.2: Gas turbine as a power-conversion machine - p. 780 49. 21.2.3: Operational experience of helium gas turbines - p. 781 50. 21.2.4: Recent helium gas turbine tests - p. 782 51. 21.2.5: Nuclear power plant closed cycles - p. 783 52. 21.2.6: Helium as a coolant - p. 784 53. 21.2.7: Generation-IV closed-cycle configurations for GFRs and VHTRs - p. 787 54. 21.2.8: Component definition for design point performance - p. 788 55. 21.2.9: Cycle performance design considerations - p. 795 56. 21.2.10: Working fluid for NPP cycle performance, and operation - p. 802 57. 21.2.11: Nuclear power plant controls and operations - p. 814 58. 21.2.12: Risk assessment - p. 819 59. 21.2.13: Technology risk - p. 820 60. 21.2.14: Material technology for high temperature and pressure - p. 820 61. 21.2.15: Working fluid gas management - p. 821 62. 21.2.16: Technology maturity level for components based on selected working fluid - p. 822 63. 21.2.17: Working fluid TRL for turbomachinery components - p. 822 64. 21.2.18: Working fluid TRL for heat exchangers - p. 824 65. 21.2.19: Financial risk - p. 824 66. 21.2.20: Cost of working fluid - p. 824 67. 21.2.21: Sensitivity to pressure ratio and mass flow rate - p. 824 68. 21.2.22: Legislation - p. 827 69. 21.2.23: Other design considerations - p. 827 70. 21.2.24: Future trends - p. 829 71. 21.2.25: Conclusion - p. 830 72. References - p. 832 73. Further reading - p. 834 74. Chapter 22 Regulatory and licensing challenges with Generation-IV nuclear energy systems - p. 837 75. Chapter 23 ITER, the way to fusion energy - p. 867 76. 23.1: Nuclear fusion - p. 870 77. 23.2: The history of the ITER project - p. 873 78. 23.3: A gigantic fusion machine - p. 878 79. 23.4: A pharaonic worksite - p. 887 80. 23.5: Organizing a huge logistics - p. 889 81. 23.6: Delays and budget increases - p. 896 82. 23.7: The management challenge - p. 901 83. 23.8: Nuclear licensing - p. 903 84. 23.9: Safety and waste management - p. 904 85. 23.10: Natural hazards - p. 906 86. 23.11: The impact of ITER on the economy - p. 908 87. 23.12: Will fusion become commercial? - p. 911 88. 23.13: DEMO and the projects after ITER - p. 914 89. 23.14: Alternative technologies - p. 917 90. 23.15: The fusion era - p. 922 91. References - p. 925 92. Further reading - p. 927 93. Appendix A1 Additional materials (layouts, T-s diagrams, basic parameters, photos, etc.) on thermal and nuclear power plants - p. 929 94. References - p. 1058 95. Appendix A2 Comparison of thermophysical properties of reactor coolants - p. 1061 96. Index - p. 1083
