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Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide offers a deep understanding of MOX properties for nuclear fuels that will be useful for performance evaluation. It also reviews fuel property simulation technology and an irradiation behavior model required for performance evaluation. Based on research findings, the book investigates various physical property data in order to develop MOX fuel for sodium-cooled fast reactors. It discusses a database of MOX properties, including oxygen potential, melting temperature, the lattice parameter, sound speeds, thermal expansion, thermal diffusivity, oxygen self-diffusion, and chemical diffusion coefficients, that was used to derive a science-based model of MOX properties (Sci-M Pro) for fuel-performance code development. Features: - Concisely covers the essential aspects of MOX nuclear fuels. - Explores MOX nuclear fuels by systematically evaluating various physical property values using a behavior model. - Presents fuel property simulation technology. - Considers oxygen potential, the lattice parameter, sound speeds, and oxygen self-diffusion. - Discusses melting temperature, thermal expansion, thermal diffusivity, and chemical diffusion coefficients. The book will be useful for researchers and engineers working in the field of nuclear fuels and nuclear materials.
Dr. Masato Kato is currently senior princial researcher at the Sector of Fast Reactor Research and Development at the Japan Atomic Energy Agency (JAEA). He received his doctorate from Tohoku University in 2009. His work focuses specifically on the physical properties and nuclear fuel technology of plutonium oxide fuels. He is a member of the Atomic Energy Society of Japan (AESJ) and the President on its Nuclear Fuel subcommittee in 2021-2022. Dr. Masahiko Machida is currently the Deputy Director at Computational Science and E-systems at Japan Atomic Energy Agency. He received his doctorate from Tohoku University in 2000. His reseaerch area is theoretical and computational physics and chemistry on various materials including nuclear fuel compounds. He is a member of the Atomic Energy Society of Japan and Physical Society of Japan.
1. Introduction. 2. Experimental Techniques. 3. Properties. 4. Theoretical and Computational Works on Oxide Nuclear-Fuel Materials. 5. Fuel Technologies. 6. Summary. 7. Appendices.
