Pressurized Heavy Water Reactors: Atucha-II, the eighth volume in the JSME Series on Thermal and Nuclear Power Generation, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents a close analysis of the Atucha reactor, covering reactor physics, aging management of major components, and the role of codes in PHWR and Nuclear Regulation and Licensing. Including contemporary capabilities and challenges of nuclear technology, the book offers solutions and advice on common problems faced, guiding the reader through safe and approved processes that will help them reach suitable solutions.
Professionals involved in lifecycle assessments and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, design and licensing.
1. 2.1: Introduction - p. 51 2. 2.2: Outline of Autoridad Regulatoria Nuclear licensing process - p. 58 3. 2.3: Outline of international practices relevant for the proposed approach - p. 62 4. 2.4: Proposed best estimate plus uncertainty approach for final safety analysis report accident analyses - p. 77 5. 2.5: Three-dimensional neutron kinetics thermal hydraulics coupled code - p. 113 6. 2.6: A sample case for application of the best estimate plus uncertainty approach (best estimate plus uncertainty procedure for DEGB LB-LOCA analysis) - p. 128 7. 2.7: Step 3—selected calculation results - p. 169 8. 2.8: Step 4—uncertainty analysis - p. 181 9. 2.9: Step 5—safety margin determination - p. 182 10. 2.10: Conclusions - p. 186 11. Acknowledgements - p. 187 12. Appendix 1: Survey on regulatory basis for the reactivity initiated accidents acceptance criteria - p. 187 13. 3 Atucha II: insights from the accident analysis - p. 205 14. 3.1: Introduction - p. 205 15. 3.2: The list of transients analyzed in chapter 15 of Atucha II FSAR - p. 211 16. 3.3: Computational tools, system configuration and selected modeling assumptions - p. 227 17. 3.4: System performance - p. 260 18. 3.5: The role of specific components, subsystems, and containment - p. 337 19. 3.6: Thermal-hydraulic phenomena - p. 376 20. 3.7: The coupled phenomena and scenarios - p. 392 21. 3.8: The instrumentation and control role - p. 442 22. 3.9: Comparison of scenarios - p. 451 23. 3.10: Miscellaneous insights including radiological impacts - p. 461 24. 3.11: Conclusion - p. 513 25. Acknowledgments - p. 521 26. Appendix A1: Additional Information About LBLOCA Analysis - p. 521 27. Index - p. 549
Pressurized Heavy Water Reactors: Atucha-II, the eighth volume in the JSME Series on Thermal and Nuclear Power Generation, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents a close analysis of the Atucha reactor, covering reactor physics, aging management of major components, and the role of codes in PHWR and Nuclear Regulation and Licensing. Including contemporary capabilities and challenges of nuclear technology, the book offers solutions and advice on common problems faced, guiding the reader through safe and approved processes that will help them reach suitable solutions.
Professionals involved in lifecycle assessments and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, design and licensing.
1. 2.1: Introduction - p. 51 2. 2.2: Outline of Autoridad Regulatoria Nuclear licensing process - p. 58 3. 2.3: Outline of international practices relevant for the proposed approach - p. 62 4. 2.4: Proposed best estimate plus uncertainty approach for final safety analysis report accident analyses - p. 77 5. 2.5: Three-dimensional neutron kinetics thermal hydraulics coupled code - p. 113 6. 2.6: A sample case for application of the best estimate plus uncertainty approach (best estimate plus uncertainty procedure for DEGB LB-LOCA analysis) - p. 128 7. 2.7: Step 3—selected calculation results - p. 169 8. 2.8: Step 4—uncertainty analysis - p. 181 9. 2.9: Step 5—safety margin determination - p. 182 10. 2.10: Conclusions - p. 186 11. Acknowledgements - p. 187 12. Appendix 1: Survey on regulatory basis for the reactivity initiated accidents acceptance criteria - p. 187 13. 3 Atucha II: insights from the accident analysis - p. 205 14. 3.1: Introduction - p. 205 15. 3.2: The list of transients analyzed in chapter 15 of Atucha II FSAR - p. 211 16. 3.3: Computational tools, system configuration and selected modeling assumptions - p. 227 17. 3.4: System performance - p. 260 18. 3.5: The role of specific components, subsystems, and containment - p. 337 19. 3.6: Thermal-hydraulic phenomena - p. 376 20. 3.7: The coupled phenomena and scenarios - p. 392 21. 3.8: The instrumentation and control role - p. 442 22. 3.9: Comparison of scenarios - p. 451 23. 3.10: Miscellaneous insights including radiological impacts - p. 461 24. 3.11: Conclusion - p. 513 25. Acknowledgments - p. 521 26. Appendix A1: Additional Information About LBLOCA Analysis - p. 521 27. Index - p. 549
