Handbook of Generation IV Nuclear Reactors presents information on the current fleet of Nuclear Power Plants (NPPs) with water-cooled reactors (Generation III and III+) (96% of 430 power reactors in the world) that have relatively low thermal efficiencies (within the range of 32 36%) compared to those of modern advanced thermal power plants (combined cycle gas-fired power plants – up to 62% and supercritical pressure coal-fired power plants – up to 55%).
Moreover, thermal efficiency of the current fleet of NPPs with water-cooled reactors cannot be increased significantly without completely different innovative designs, which are Generation IV reactors. Nuclear power is vital for generating electrical energy without carbon emissions.
Complete with the latest research, development, and design, and written by an international team of experts, this handbook is completely dedicated to Generation IV reactors.
1. 1. Introduction: A survey of the status of electricity generation in the world - p. 1 2. Part One. Generation IV nuclear-reactor concepts - p. 34 3. Preface to Part One - p. 35 4. 2. Introduction: Generation IV International Forum - p. 37 5. 3. Very high-temperature reactor - p. 55 6. 4. Gas-cooled fast reactors - p. 91 7. 5. Sodium-cooled fast reactor - p. 97 8. 6. Lead-cooled fast reactor - p. 119 9. 7. Molten salt fast reactors - p. 157 10. 8. Super-critical water-cooled reactors - p. 189 11. Part Two. Current status of Generation IV activities in selected countries - p. 220 12. Preface to Part Two - p. 221 13. 9. Generation IV: USA - p. 223 14. 10. Euratom research and training program in Generation-IV systems: Breakthrough technologies to improve sustainability, safety and reliability, socioeconomics, and proliferation resistance - p. 241 15. 11. Generation IV concepts: Japan - p. 283 16. 12. Generation IV concepts: USSR and Russia - p. 309 17. 13. Generation IV concepts in Korea - p. 335 18. 14. Generation IV concepts: China - p. 373 19. 15. Generation IV concepts: India - p. 413 20. Part Three. Related topics to Generation IV nuclear reactor concepts - p. 452 21. Preface to Part Three - p. 453 22. 16. The safety of advanced reactors - p. 455 23. 16.1. Basic safety principles - p. 455 24. 16.2. Safety and reliability goals - p. 455 25. 16.3. Safety objectives and the classification of advanced reactor types - p. 465 26. 16.4. Generic safety objectives and safety barriers - p. 471 27. 16.5. Risk informing safety requirements by learning from prior events - p. 474 28. 16.6. Major technical safety issues - p. 476 29. 16.7. Multiple modules and plant risk - p. 479 30. 16.8. The role of safety research and development for advanced reactors - p. 481 31. 16.9. Natural-circulation loop and parallel channel thermal-hydraulics - p. 481 32. 16.10. Literature review - p. 486 33. 16.11. Modeling natural-circulation loops - p. 498 34. 16.12. Conclusions - p. 520 35. Nomenclature - p. 521 36. Greek symbols - p. 522 37. Nondimensional numbers - p. 522 38. Subscripts - p. 522 39. Acronyms and abbreviations - p. 523 40. 17. Nonproliferation for advanced reactors: Political and social aspects - p. 541 41. 18. Thermal aspects of conventional and alternative fuels - p. 583 42. 19. Hydrogen cogeneration with Generation IV nuclear power plants - p. 637 43. 20. Advanced small modular reactors - p. 661 44. Appendix A1. Additional materials (schematics, layouts, T–s diagrams, basic parameters, and photos) on thermal and nuclear power plants - p. 701 45. Appendix A2. Comparison of thermophysical properties of reactor coolants - p. 743 46. Appendix A3. Thermophysical properties of fluids at subcritical and critical/supercritical conditions - p. 771 47. Appendix A4. Heat transfer and pressure drop in forced convection to fluids at supercritical pressures - p. 795 48. Appendix A5. World experience in nuclear steam reheat - p. 825 49. Appendix A6. Comparison of thermophysical properties of selected gases at atmospheric pressure - p. 855 50. Appendix A7. Supplementary tables - p. 859 51. Appendix A8. Unit conversion - p. 871 52. Index - p. 879
Handbook of Generation IV Nuclear Reactors presents information on the current fleet of Nuclear Power Plants (NPPs) with water-cooled reactors (Generation III and III+) (96% of 430 power reactors in the world) that have relatively low thermal efficiencies (within the range of 32 36%) compared to those of modern advanced thermal power plants (combined cycle gas-fired power plants – up to 62% and supercritical pressure coal-fired power plants – up to 55%).
Moreover, thermal efficiency of the current fleet of NPPs with water-cooled reactors cannot be increased significantly without completely different innovative designs, which are Generation IV reactors. Nuclear power is vital for generating electrical energy without carbon emissions.
Complete with the latest research, development, and design, and written by an international team of experts, this handbook is completely dedicated to Generation IV reactors.
1. 1. Introduction: A survey of the status of electricity generation in the world - p. 1 2. Part One. Generation IV nuclear-reactor concepts - p. 34 3. Preface to Part One - p. 35 4. 2. Introduction: Generation IV International Forum - p. 37 5. 3. Very high-temperature reactor - p. 55 6. 4. Gas-cooled fast reactors - p. 91 7. 5. Sodium-cooled fast reactor - p. 97 8. 6. Lead-cooled fast reactor - p. 119 9. 7. Molten salt fast reactors - p. 157 10. 8. Super-critical water-cooled reactors - p. 189 11. Part Two. Current status of Generation IV activities in selected countries - p. 220 12. Preface to Part Two - p. 221 13. 9. Generation IV: USA - p. 223 14. 10. Euratom research and training program in Generation-IV systems: Breakthrough technologies to improve sustainability, safety and reliability, socioeconomics, and proliferation resistance - p. 241 15. 11. Generation IV concepts: Japan - p. 283 16. 12. Generation IV concepts: USSR and Russia - p. 309 17. 13. Generation IV concepts in Korea - p. 335 18. 14. Generation IV concepts: China - p. 373 19. 15. Generation IV concepts: India - p. 413 20. Part Three. Related topics to Generation IV nuclear reactor concepts - p. 452 21. Preface to Part Three - p. 453 22. 16. The safety of advanced reactors - p. 455 23. 16.1. Basic safety principles - p. 455 24. 16.2. Safety and reliability goals - p. 455 25. 16.3. Safety objectives and the classification of advanced reactor types - p. 465 26. 16.4. Generic safety objectives and safety barriers - p. 471 27. 16.5. Risk informing safety requirements by learning from prior events - p. 474 28. 16.6. Major technical safety issues - p. 476 29. 16.7. Multiple modules and plant risk - p. 479 30. 16.8. The role of safety research and development for advanced reactors - p. 481 31. 16.9. Natural-circulation loop and parallel channel thermal-hydraulics - p. 481 32. 16.10. Literature review - p. 486 33. 16.11. Modeling natural-circulation loops - p. 498 34. 16.12. Conclusions - p. 520 35. Nomenclature - p. 521 36. Greek symbols - p. 522 37. Nondimensional numbers - p. 522 38. Subscripts - p. 522 39. Acronyms and abbreviations - p. 523 40. 17. Nonproliferation for advanced reactors: Political and social aspects - p. 541 41. 18. Thermal aspects of conventional and alternative fuels - p. 583 42. 19. Hydrogen cogeneration with Generation IV nuclear power plants - p. 637 43. 20. Advanced small modular reactors - p. 661 44. Appendix A1. Additional materials (schematics, layouts, T–s diagrams, basic parameters, and photos) on thermal and nuclear power plants - p. 701 45. Appendix A2. Comparison of thermophysical properties of reactor coolants - p. 743 46. Appendix A3. Thermophysical properties of fluids at subcritical and critical/supercritical conditions - p. 771 47. Appendix A4. Heat transfer and pressure drop in forced convection to fluids at supercritical pressures - p. 795 48. Appendix A5. World experience in nuclear steam reheat - p. 825 49. Appendix A6. Comparison of thermophysical properties of selected gases at atmospheric pressure - p. 855 50. Appendix A7. Supplementary tables - p. 859 51. Appendix A8. Unit conversion - p. 871 52. Index - p. 879
