Advances in Nuclear Fuel Chemistry presents a high-level description of nuclear fuel chemistry based on the most recent research and advances. Dr. Markus H.A. Piro and his team of global, expert contributors cover all aspects of both the conventional uranium-based nuclear fuel cycle and non-conventional fuel cycles, including mining, refining, fabrication, and long-term storage, as well as emerging nuclear technologies, such as accident tolerant fuels and molten salt materials. Aimed at graduate students, researchers, academics and practicing engineers and regulators, this book will provide the reader with a single reference from which to learn the fundamentals of classical thermodynamics and radiochemistry.
1. 1.1 Introduction - p. 3 2. 1.2 Basic concepts of chemical kinetics - p. 4 3. 1.3 Fundamentals of chemical thermodynamics - p. 9 4. 1.4 Thermodynamics of condensed phases - p. 15 5. 1.5 Statistical thermodynamics applied to gases - p. 35 6. 1.6 Thermodynamics of nuclear fuel and fission products - p. 49 7. 1.7 Solution thermodynamics applied to the storage of spent fuel and geological disposal - p. 69 8. 1.8 Basics of redox equilibria - p. 72 9. 1.9 Conclusion - p. 84 10. Acknowledgment - p. 84 11. References - p. 85 12. Further reading - p. 85 13. 2. Experimental methods - p. 89 14. 3. Computational thermochemistry of nuclear fuel - p. 159 15. Part B: Fuel Designs - p. 180 16. 4. Oxide power reactor fuels - p. 185 17. 5. Other power reactor fuels - p. 215 18. 6. Molten salt reactor fuels - p. 249 19. 7. Research reactor fuels - p. 273 20. Part C: Stages of the Fuel Cycle and Other Applications - p. 305 21. 8. Mining and milling - p. 315 22. 9. Uranium conversion and enrichment - p. 331 23. 10. Advances in fuel fabrication - p. 371 24. 11. In-reactor behavior - p. 419 25. 12. Reprocessing and recycling - p. 469 26. 13. Spent nuclear fuel and disposal - p. 527 27. 14. Advances in fuel chemistry during a severe accident: Update after Fukushima Daiichi Nuclear Power Station (FDNPS) accident - p. 555 28. Index - p. 627
Advances in Nuclear Fuel Chemistry presents a high-level description of nuclear fuel chemistry based on the most recent research and advances. Dr. Markus H.A. Piro and his team of global, expert contributors cover all aspects of both the conventional uranium-based nuclear fuel cycle and non-conventional fuel cycles, including mining, refining, fabrication, and long-term storage, as well as emerging nuclear technologies, such as accident tolerant fuels and molten salt materials. Aimed at graduate students, researchers, academics and practicing engineers and regulators, this book will provide the reader with a single reference from which to learn the fundamentals of classical thermodynamics and radiochemistry.
1. 1.1 Introduction - p. 3 2. 1.2 Basic concepts of chemical kinetics - p. 4 3. 1.3 Fundamentals of chemical thermodynamics - p. 9 4. 1.4 Thermodynamics of condensed phases - p. 15 5. 1.5 Statistical thermodynamics applied to gases - p. 35 6. 1.6 Thermodynamics of nuclear fuel and fission products - p. 49 7. 1.7 Solution thermodynamics applied to the storage of spent fuel and geological disposal - p. 69 8. 1.8 Basics of redox equilibria - p. 72 9. 1.9 Conclusion - p. 84 10. Acknowledgment - p. 84 11. References - p. 85 12. Further reading - p. 85 13. 2. Experimental methods - p. 89 14. 3. Computational thermochemistry of nuclear fuel - p. 159 15. Part B: Fuel Designs - p. 180 16. 4. Oxide power reactor fuels - p. 185 17. 5. Other power reactor fuels - p. 215 18. 6. Molten salt reactor fuels - p. 249 19. 7. Research reactor fuels - p. 273 20. Part C: Stages of the Fuel Cycle and Other Applications - p. 305 21. 8. Mining and milling - p. 315 22. 9. Uranium conversion and enrichment - p. 331 23. 10. Advances in fuel fabrication - p. 371 24. 11. In-reactor behavior - p. 419 25. 12. Reprocessing and recycling - p. 469 26. 13. Spent nuclear fuel and disposal - p. 527 27. 14. Advances in fuel chemistry during a severe accident: Update after Fukushima Daiichi Nuclear Power Station (FDNPS) accident - p. 555 28. Index - p. 627
