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Boiling Water Reactors, Volume Four in the JSME Series on Thermal and Nuclear Power Generation compiles the latest research in this very comprehensive reference that begins with an analysis of the history of BWR development and then moves through BWR plant design and innovations. The reader is guided through considerations for all BWR plant features and systems, including reactor internals, safety systems and plant instrumentation and control. Thermal-hydraulic aspects within a BWR core are analyzed alongside fuel analysis before comparisons of the latest BWR plant life management and maintenance technologies to promote safety and radiation protection practices are covered.

The book's authors combine their in-depth knowledge and depth of experience in the field to analyze innovations and Next Generation BWRs, considering prospects for a variety of different BWRs, such as High-Conversion-BWRs, TRU-Burner Reactors and Economic Simplified BWRs.

  • Written by experts from the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers
  • Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits
  • Considers societal impacts and sustainability concerns and goals throughout the discussion
  • Explores BWR plant design, thermal-hydraulic aspects, the reactor core and plant life management and maintenance in one complete resource

1. Title of Book - p. i 2. Cover image - p. i 3. Title page - p. ii 4. Table of Contents - p. iii 5. Copyright - p. iii 6. Contributors - p. xvii 7. About the Authors - p. xix 8. Preface of JSME series in Thermal and Nuclear Power Generation - p. xxv 9. Preface - p. xxvii 10. Editing working group for volume 4: Boiling water reactors - p. xxix 11. Abbreviations - p. xxxiii 12. 1. History of BWR development - p. 6 13. 2. Features of BWR plant - p. 59 14. 3. Nuclear reactor dynamics and thermal hydraulics of reactor core and fuel assembly - p. 167 15. Abstract - p. 167 16. 3.1. Reactor internals and coolant flow paths in a reactor pressure vessel - p. 168 17. 3.2. Advances of reactor core and fuel assembly - p. 178 18. 3.2.1. High burnup fuel design - p. 178 19. 3.2.2. MOX fuel design - p. 191 20. 3.2.3. Thermal-hydraulic design - p. 199 21. 3.2.4. Enhancement of critical power - p. 212 22. 3.2.5. Countermeasures and cause of fuel rod failure - p. 218 23. 3.2.6. Proving test on the thermal-hydraulic performance of BWR fuel assembly - p. 245 24. 3.3. Advances in reactor core and fuel assembly analysis - p. 250 25. 3.3.1. Nuclear analysis in BWRs - p. 250 26. 3.3.2. Thermal-hydraulics system analysis codes and subchannel analysis codes - p. 269 27. 3.4. Advances in containment vessel design - p. 297 28. 3.5. Advances in safety analysis code and safety systems - p. 315 29. 4. Fukushima Daiichi nuclear power plant accident and analysis evaluation - p. 348 30. 5. BWR innovations - p. 407 31. Abstract - p. 407 32. 5.1. Trans-uranic (TRU) burner reactor and reduced-moderation water reactor - p. 408 33. 5.1.1. TRU burner reactor - p. 408 34. 5.1.2. Reduced-moderation light water reactor - p. 423 35. 5.2. Design innovation of BWR and high-pressure BWR - p. 434 36. 5.3. Power uprate in BWR - p. 456 37. 5.4. Post-BT standard for BWR power plant - p. 473 38. 5.5. Core catcher - p. 478 39. 5.6. Steam injector - p. 492 40. 5.7. Built in upper internal control rod drives (CRDs) for ABWR-III - p. 533 41. Index - p. 569

Descripcion
Descripción

Boiling Water Reactors, Volume Four in the JSME Series on Thermal and Nuclear Power Generation compiles the latest research in this very comprehensive reference that begins with an analysis of the history of BWR development and then moves through BWR plant design and innovations. The reader is guided through considerations for all BWR plant features and systems, including reactor internals, safety systems and plant instrumentation and control. Thermal-hydraulic aspects within a BWR core are analyzed alongside fuel analysis before comparisons of the latest BWR plant life management and maintenance technologies to promote safety and radiation protection practices are covered.

The book's authors combine their in-depth knowledge and depth of experience in the field to analyze innovations and Next Generation BWRs, considering prospects for a variety of different BWRs, such as High-Conversion-BWRs, TRU-Burner Reactors and Economic Simplified BWRs.

  • Written by experts from the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers
  • Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits
  • Considers societal impacts and sustainability concerns and goals throughout the discussion
  • Explores BWR plant design, thermal-hydraulic aspects, the reactor core and plant life management and maintenance in one complete resource

1. Title of Book - p. i 2. Cover image - p. i 3. Title page - p. ii 4. Table of Contents - p. iii 5. Copyright - p. iii 6. Contributors - p. xvii 7. About the Authors - p. xix 8. Preface of JSME series in Thermal and Nuclear Power Generation - p. xxv 9. Preface - p. xxvii 10. Editing working group for volume 4: Boiling water reactors - p. xxix 11. Abbreviations - p. xxxiii 12. 1. History of BWR development - p. 6 13. 2. Features of BWR plant - p. 59 14. 3. Nuclear reactor dynamics and thermal hydraulics of reactor core and fuel assembly - p. 167 15. Abstract - p. 167 16. 3.1. Reactor internals and coolant flow paths in a reactor pressure vessel - p. 168 17. 3.2. Advances of reactor core and fuel assembly - p. 178 18. 3.2.1. High burnup fuel design - p. 178 19. 3.2.2. MOX fuel design - p. 191 20. 3.2.3. Thermal-hydraulic design - p. 199 21. 3.2.4. Enhancement of critical power - p. 212 22. 3.2.5. Countermeasures and cause of fuel rod failure - p. 218 23. 3.2.6. Proving test on the thermal-hydraulic performance of BWR fuel assembly - p. 245 24. 3.3. Advances in reactor core and fuel assembly analysis - p. 250 25. 3.3.1. Nuclear analysis in BWRs - p. 250 26. 3.3.2. Thermal-hydraulics system analysis codes and subchannel analysis codes - p. 269 27. 3.4. Advances in containment vessel design - p. 297 28. 3.5. Advances in safety analysis code and safety systems - p. 315 29. 4. Fukushima Daiichi nuclear power plant accident and analysis evaluation - p. 348 30. 5. BWR innovations - p. 407 31. Abstract - p. 407 32. 5.1. Trans-uranic (TRU) burner reactor and reduced-moderation water reactor - p. 408 33. 5.1.1. TRU burner reactor - p. 408 34. 5.1.2. Reduced-moderation light water reactor - p. 423 35. 5.2. Design innovation of BWR and high-pressure BWR - p. 434 36. 5.3. Power uprate in BWR - p. 456 37. 5.4. Post-BT standard for BWR power plant - p. 473 38. 5.5. Core catcher - p. 478 39. 5.6. Steam injector - p. 492 40. 5.7. Built in upper internal control rod drives (CRDs) for ABWR-III - p. 533 41. Index - p. 569

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Ficha Técnica