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Handbook of generation IV nuclear reactors /
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 tho...
| Clasificación: | Libro Electrónico |
|---|---|
| Otros Autores: | |
| Formato: | Electrónico eBook |
| Idioma: | Inglés |
| Publicado: |
Duxford, UK :
Woodhead Publishing is an imprint of Elsevier,
2016.
|
| Colección: | Woodhead Publishing in energy ;
no. 103. |
| Temas: | |
| Acceso en línea: | Texto completo |
MARC
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| 245 | 0 | 0 | |a Handbook of generation IV nuclear reactors / |c edited by Igor L. Pioro. |
| 264 | 1 | |a Duxford, UK : |b Woodhead Publishing is an imprint of Elsevier, |c 2016. | |
| 300 | |a 1 online resource | ||
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| 490 | 1 | |a Woodhead Publishing series in energy ; |v number 103 | |
| 520 | |a 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. | ||
| 500 | |a Includes index. | ||
| 588 | 0 | |a Online resource; title from PDF title page (ScienceDirect, viewed June 22, 2016). | |
| 505 | 0 | |8 1.1\x |a 1. Introduction: a survey of the status of electricity generation in the world -- 1.1. Statistics on electricity generation in the world / I.L. Pioro / R.B. Duffey / P.L. Kirillov / R. Panchal -- 1.2. Thermal power plants / I.L. Pioro / R.B. Duffey / P.L. Kirillov / R. Panchal -- 1.3. Modern nuclear power plants / I.L. Pioro / R.B. Duffey / P.L. Kirillov / R. Panchal -- 1.4. Conclusions / I.L. Pioro / R.B. Duffey / P.L. Kirillov / R. Panchal -- Abbreviations / I.L. Pioro / R.B. Duffey / P.L. Kirillov / R. Panchal -- Acknowledgments / I.L. Pioro / R.B. Duffey / P.L. Kirillov / R. Panchal -- References / I.L. Pioro / R.B. Duffey / P.L. Kirillov / R. Panchal -- Preface to Part One / I.L. Pioro / R.B. Duffey / P.L. Kirillov / R. Panchal -- 2. Introduction: Generation IV International Forum / I.L. Pioro / R.B. Duffey / P.L. Kirillov / R. Panchal -- 2.1. Origins of the Generation IV International Forum / I.L. Pioro -- 2.2. Generation IV goals / I.L. Pioro -- 2.3. Selection of Generation IV systems / I.L. Pioro -- 2.4. Six Generation IV nuclear energy systems / I.L. Pioro -- 2.5. Summary / I.L. Pioro -- Acknowledgments / I.L. Pioro -- References / I.L. Pioro -- 3. Very high-temperature reactor / I.L. Pioro -- 3.1. Development history and current status / X.L. Yan -- 3.2. Technology overview / X.L. Yan -- 3.3. Detailed technical description / X.L. Yan -- 3.4. Applications and economics / X.L. Yan -- 3.5. Summary / X.L. Yan -- Acronyms / X.L. Yan -- References / X.L. Yan -- 4. Gas-cooled fast reactors / X.L. Yan -- 4.1. Rationale and generational research and development bridge / P. Tsvetkov -- 4.2. Gas-cooled fast reactor technology / P. Tsvetkov -- 4.3. Conclusions / P. Tsvetkov -- References / P. Tsvetkov -- 5. Sodium-cooled fast reactor / P. Tsvetkov -- 5.1. Introduction / H. Ohshima / S. Kubo -- 5.2. Development history / H. Ohshima / S. Kubo -- 5.3. System characteristics / H. Ohshima / S. Kubo -- 5.4. Safety issues / H. Ohshima / S. Kubo -- 5.5. Future trends and key challenges / H. Ohshima / S. Kubo -- References / H. Ohshima / S. Kubo -- 6. Lead-cooled fast reactor / H. Ohshima / S. Kubo -- 6.1. Overview and motivation for lead-cooled fast reactor systems / C.F. Smith / L. Cinotti -- 6.2. Basic design choices / C.F. Smith / L. Cinotti -- 6.3. Safety principles / C.F. Smith / L. Cinotti -- 6.4. Fuel technology and fuel cycles for the lead-cooled fast reactor / C.F. Smith / L. Cinotti -- 6.5. Summary of advantages and key challenges of the lead-cooled fast reactor / C.F. Smith / L. Cinotti -- 6.6. Overview of Generation IV lead-cooled fast reactor designs / C.F. Smith / L. Cinotti -- 6.7. Future trends / C.F. Smith / L. Cinotti -- Sources of further information / C.F. Smith / L. Cinotti -- Nomenclature / C.F. Smith / L. Cinotti -- References / C.F. Smith / L. Cinotti -- 7. Molten salt fast reactors / C.F. Smith / L. Cinotti -- 7.1. Introduction / M. Allibert / M. Aufiero / M. Brovchenko / S. Delpech / V. Ghetta / D. Heuer / A. Laureau / E. Merle-Lucotte -- 7.2. The molten salt fast reactor concept / M. Allibert / M. Aufiero / M. Brovchenko / S. Delpech / V. Ghetta / D. Heuer / A. Laureau / E. Merle-Lucotte -- 7.3. Fuel salt chemistry and material issues / M. Allibert / M. Aufiero / M. Brovchenko / S. Delpech / V. Ghetta / D. Heuer / A. Laureau / E. Merle-Lucotte -- 7.4. Molten salt fast reactor fuel cycle scenarios / M. Allibert / M. Aufiero / M. Brovchenko / S. Delpech / V. Ghetta / D. Heuer / A. Laureau / E. Merle-Lucotte -- 7.5. Safety issues / M. Allibert / M. Aufiero / M. Brovchenko / S. Delpech / V. Ghetta / D. Heuer / A. Laureau / E. Merle-Lucotte -- 7.6. Concept viability: issues and demonstration steps / M. Allibert / M. Aufiero / M. Brovchenko / S. Delpech / V. Ghetta / D. Heuer / A. Laureau / E. Merle-Lucotte -- 7.7. Conclusion and perspectives / M. Allibert / M. Aufiero / M. Brovchenko / S. Delpech / V. Ghetta / D. Heuer / A. Laureau / E. Merle-Lucotte -- Nomenclature / M. Allibert / M. Aufiero / M. Brovchenko / S. Delpech / V. Ghetta / D. Heuer / A. Laureau / E. Merle-Lucotte -- Acknowledgments / M. Allibert / M. Aufiero / M. Brovchenko / S. Delpech / V. Ghetta / D. Heuer / A. Laureau / E. Merle-Lucotte -- References / M. Allibert / M. Aufiero / M. Brovchenko / S. Delpech / V. Ghetta / D. Heuer / A. Laureau / E. Merle-Lucotte -- Bibliography web sources / M. Allibert / M. Aufiero / M. Brovchenko / S. Delpech / V. Ghetta / D. Heuer / A. Laureau / E. Merle-Lucotte -- 8. Super-critical water-cooled reactors / M. Allibert / M. Aufiero / M. Brovchenko / S. Delpech / V. Ghetta / D. Heuer / A. Laureau / E. Merle-Lucotte -- 8.1. Introduction / T. Schulenberg / L. Leung -- 8.2. Types of supercritical water-cooled reactor concepts and main system parameters / T. Schulenberg / L. Leung -- 8.3. Example of a pressure vessel concept / T. Schulenberg / L. Leung -- 8.4. Example of a pressure tube concept / T. Schulenberg / L. Leung -- 8.5. Fuel cycle technology / T. Schulenberg / L. Leung -- 8.6. Fuel assembly concept / T. Schulenberg / L. Leung -- 8.7. Safety system concept / T. Schulenberg / L. Leung -- 8.8. Dynamics and control / T. Schulenberg / L. Leung -- 8.9. Start-up / T. Schulenberg / L. Leung -- 8.10. Stability / T. Schulenberg / L. Leung -- 8.11. Advantages and disadvantages of supercritical water-cooled reactor concepts / T. Schulenberg / L. Leung -- 8.12. Key challenges / T. Schulenberg / L. Leung -- 8.13. Future trends / T. Schulenberg / L. Leung -- Acronyms / T. Schulenberg / L. Leung -- Nomenclature / T. Schulenberg / L. Leung -- References / T. Schulenberg / L. Leung -- Preface to Part Two / T. Schulenberg / L. Leung -- 9. Generation IV: USA / T. Schulenberg / L. Leung -- 9.1. Generation IV program evolution in the United States / P. Tsvetkov -- 9.2. Energy market in the United States and the potential role of Generation IV systems: electricity, process heat, and waste management / P. Tsvetkov -- 9.3. Electrical grid integration of Generation IV nuclear energy systems in the United States / P. Tsvetkov -- 9.4. Industry and utilities interests in Generation IV nuclear energy systems in the United States / P. Tsvetkov -- 9.5. Deployment perspectives for Generation IV systems in the United States and deployment schedule / P. Tsvetkov -- 9.6. Conclusions / P. Tsvetkov -- Abbreviations / P. Tsvetkov -- References / P. Tsvetkov -- 10. Euratom research and training program in Generation-IV systems: breakthrough technologies to improve sustainability, safety and reliability, socioeconomics, and proliferation resistance / P. Tsvetkov -- 10.1. Background: Euratom (nuclear fission research and training) within the Energy Union (European Union energy mix policy) / G. Van Goethem -- 10.2. Generation-I, -II, -III, and -IV of nuclear fission reactors: research, development, and continuous improvement for more than five decades / G. Van Goethem -- 10.3."Goals for Generation-IV nuclear energy systems" and "technology roadmap" for the six GIF systems (2002 and 2013) / G. Van Goethem -- 10.4."European sustainable nuclear industrial initiative" and Euratom research and training program in fast neutron reactor systems / G. Van Goethem -- 10.5. Sustainability (efficient resource utilization and minimization of radioactive waste) / G. Van Goethem -- 10.6. Safety and reliability (maximum safety performance through design, technology, regulation, and culture) / G. Van Goethem -- 10.7. Socioeconomics (economic advantage over other energy sources and better governance structure in energy decision-making process) / G. Van Goethem -- 10.8. Proliferation resistance and physical protection (protection against all kinds of terrorism) / G. Van Goethem -- 10.9. Conclusion: a new way of "developing/teaching science," closer to the end-user needs of the 21-st century (society and industry) / G. Van Goethem -- Nomenclature / G. Van Goethem -- Appendix: Tentative training scheme for preconceptual Generation-IV design engineers (knowledge, skills, attitudes) / G. Van Goethem -- A1. Introduction / G. Van Goethem -- A2. Trainees prerequisites / G. Van Goethem -- A3. Knowledge, skills, and attitudes required for a Generation-IV engineer / G. Van Goethem -- A4. Learning outcomes related to knowledge, skills, and attitudes for a Generation-IV engineer / G. Van Goethem -- 11. Generation IV concepts: Japan / G. Van Goethem -- 11.1. Introduction / H. Kamide / H. Ohshima / T. Sakai / M. Morishita -- 11.2. JSFR design and its key innovative technologies / H. | |
| 505 | 0 | |a Kamide / H. Ohshima / T. Sakai / M. Morishita -- 11.3. Update of the Japan sodium-cooled fast reactor design with lessons learned from the Fukushima-Daiichi accident / H. Kamide / H. Ohshima / T. Sakai / M. Morishita -- 11.4. Concluding remarks / H. Kamide / H. Ohshima / T. Sakai / M. Morishita -- References / H. Kamide / H. Ohshima / T. Sakai / M. Morishita -- 12. Generation IV concepts: USSR and Russia / H. Kamide / H. Ohshima / T. Sakai / M. Morishita -- 12.1. Introduction / D.V. Paramonov / E.D. Paramonova -- 12.2. History of the Soviet fast reactor program / D.V. Paramonov / E.D. Paramonova -- 12.3. Sodium fast reactors / D.V. Paramonov / E.D. Paramonova -- 12.4. Heavy liquid metal reactors / D.V. Paramonov / E.D. Paramonova -- 12.5. Supercritical water reactor / D.V. Paramonov / E.D. Paramonova -- 12.6. Conclusion / D.V. Paramonov / E.D. Paramonova -- Nomenclature / D.V. Paramonov / E.D. Paramonova -- References / D.V. Paramonov / E.D. Paramonova -- 13. Generation IV concepts in Korea / D.V. Paramonov / E.D. Paramonova -- 13.1. Current status of nuclear power in Korea / D. Hahn -- 13.2. Plans for advanced nuclear reactors in Korea / D. Hahn -- 13.3. Current research and development on Generation IV reactor in Korea / D. Hahn -- Acronyms / D. Hahn -- References / D. Hahn -- Appendix: Paper list related to PEACER (including P-demo and Pyroprocess), PASCAR, URANUS, and other SNU-NUTRECK activities / D. Hahn -- 14. Generation IV concepts: China / D. Hahn -- 14.1. Current statu | |
| 590 | |8 1.2\x |a s of nuclear power in China / D. Zhang | ||
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