Generation IV nuclear reactors :design, operation and prospects for future energy production /
"Version: 20241001"--Title page verso.Includes bibliographical references.1. Our energy needs and the case for nuclear fission -- 1.1. Introduction -- 1.2. Our past and present energy use -- 1.3. Environmental consequences of our energy use -- 1.4. Approaches to climate change mitigation -- 1.5. Energy options for the future2. Some introductory nuclear physics -- 2.1. Introduction -- 2.2. Nuclear structure -- 2.3. Particles and interactions -- 2.4. Nuclear binding energy -- 2.5. Nuclear decay processes -- 2.6. Excited nuclear states -- 2.7. Nuclear reactions3. Principles of nuclear fission reactors -- 3.1. Introduction -- 3.2. Fission processes -- 3.3. The fission of uranium -- 3.4. Neutron interactions in uranium -- 3.5. Basic thermal neutron reactor design -- 3.6. Reactor materials -- 3.7. Delayed neutrons and reactor stability -- 3.8. Principles of fast neutron reactors4. The early history of nuclear fission energy -- 4.1. Introduction -- 4.2. The development of nuclear physics -- 4.3. Early studies of nuclear fission -- 4.4. The Manhattan project -- 4.5. Clementine -- 4.6. Early nuclear power development5. Current fission reactor designs and the use of nuclear energy -- 5.1. Introduction -- 5.2. Nuclear reactor generations -- 5.3. Boiling water reactors -- 5.4. Pressurized water reactors -- 5.5. Gas-cooled graphite-moderated reactors -- 5.6. Water-cooled graphite-moderated reactors -- 5.7. Heavy water reactors -- 5.8. Liquid metal-cooled fast breeder reactors -- 5.9. Growth of nuclear power -- 5.10. Nuclear energy resources -- 5.11. Fuel reprocessing6. Risks associated with nuclear energy -- 6.1. Introduction -- 6.2. Nuclear reactor safety concerns -- 6.3. The Windscale fire -- 6.4. The Three Mile Island accident -- 6.5. The Chernobyl accident -- 6.6. The Fukushima accident -- 6.7. Nuclear security concerns -- 6.8. Nuclear waste disposal -- 6.9. Nuclear safety analysis7. Very high-temperature reactors (VHTRs) -- 7.1. Introduction -- 7.2. Fuel elements for very high-temperature reactors -- 7.3. Prismatic core high-temperature reactors -- 7.4. Pebble bed reactors -- 7.5. Progress towards the development of a high-temperature reactor -- 7.6. Cogeneration with a high-temperature reactor8. Molten salt reactors (MSRs) -- 8.1. Introduction -- 8.2. Molten salt reactor fuel requirements -- 8.3. Molten salt thermal reactors -- 8.4. Molten salt fast reactors -- 8.5. The history of molten salt reactor development -- 8.6. Advanced molten salt reactor designs9. Supercritical water-cooled reactors (SCWRs) -- 9.1. Introduction -- 9.2. Properties of supercritical water -- 9.3. General design of supercritical water-cooled reactors -- 9.4. Previous reactor development related to supercritical water-cooled reactors -- 9.5. Canadian supercritical water-cooled reactor -- 9.6. CSR1000 (China) -- 9.7. High-performance light-water reactor (European Union) -- 9.8. Super FR (Japan)10. Gas-cooled fast reactors (GFRs) -- 10.1. Introduction -- 10.2. History and general design of gas-cooled fast reactors -- 10.3. Generation IV gas-cooled fast reactor development -- 10.4. ALLEGRO -- 10.5. EM211. Sodium-cooled fast reactors (SFRs) -- 11.1. Introduction -- 11.2. General design of sodium-cooled fast reactors -- 11.3. History of sodium-cooled fast reactors -- 11.4. India's nuclear energy plan -- 11.5. CFR-600 (China) -- 11.6. BN-1200 (Russia) -- 11.7. PGSFR (South Korea)12. Lead-cooled fast reactors (LFRs) -- 12.1. Introduction -- 12.2. Advantages and disadvantages of lead as a coolant -- 12.3. Comparison of lead-bismuth eutectic with lead -- 12.4. History of early lead-cooled fast reactors -- 12.5. BREST-300 and BREST-1200 (Russia) -- 12.6. ALFRED and ELFR (European Union) -- 12.7. SNCLFR-100 (China)13. The future of nuclear energy -- 13.1. Introduction -- 13.2. Very high-temperature reactors (VHTRs) -- 13.3. Molten salt reactors (MSRs) -- 13.4. Supercritical water-cooled reactors (SCWRs) -- 13.5. Gas-cooled fast reactors (GFRs) -- 13.6. Sodium-cooled fast reactors (SFRs) -- 13.7. Lead-cooled fast reactors (LFRs) -- 13.8. The future of nuclear energy.Full-text restricted to subscribers or individual document purchasers.Generation IV nuclear reactors are designed to be safe, economical and to produce minimal radioactive waste material. The present book reviews the various categories of Generation IV reactors and their applications, providing an overview of the physics of nuclear power reactors and describing the technology behind each of the six Generation IV designs. It describes past progress in each of these technologies and summarizes current research and development activities. It gives an evaluation of the advantages and disadvantages of each design and summarizes the ways in which each satisfies the criteria specified by the Generation IV International Forum. This book provides an overview of the environmental aspects of nuclear power, an introduction to the physics of fission reactors and a summary of the drawbacks of current reactor designs.Advanced science and engineering students and professionals with a background in university level modern physics and an interest in nuclear power and sustainable energy.Also available in print.Mode of access: World Wide Web.System requirements: Adobe Acrobat Reader, EPUB reader, or Kindle reader.Richard A. Dunlap is a Research Professor at Dalhousie University in Canada. He joined Dalhousie University after receiving his PhD in Physics from Clark University in 1981 and became a full professor in 1990. He was the director of the Dalhousie University Institute for Research in Materials from 2009 to 2015. His research interests include nuclear spectroscopies, magnetic materials, quasicrystals, critical phenomena and advanced batteries materials.Title from PDF title page (viewed on November 4, 2024).
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