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...

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Detalles Bibliográficos
Clasificación:Libro Electrónico
Otros Autores: Pioro, I. L. (Igorʹ Leonardovich) (Editor )
Formato: Electrónico eBook
Idioma:Inglés
Publicado: Duxford, UK : Woodhead Publishing is an imprint of Elsevier, 2016.
Colección:Woodhead Publishing in energy ; no. 103.
Temas:
Nuclear reactors > Handbooks, manuals, etc.
Réacteurs nucléaires > Guides, manuels, etc.
TECHNOLOGY & ENGINEERING > Mechanical.
Nuclear reactors.
manuals (instructional materials)
handbooks.
Handbooks and manuals.
Guides et manuels.
Acceso en línea:Texto completo
Tabla de Contenidos:
  • 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.
  • 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

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