
Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide
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Product details:
- Edition number 1
- Publisher CRC Press
- Date of Publication 29 November 2024
- ISBN 9781032287171
- Binding Paperback
- No. of pages182 pages
- Size 234x156 mm
- Weight 263 g
- Language English
- Illustrations 59 Illustrations, black & white; 9 Halftones, black & white; 50 Line drawings, black & white; 16 Tables, black & white 776
Categories
Short description:
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.
MoreLong description:
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.
MoreTable of Contents:
1. Introduction. 2. Experimental Techniques. 3. Properties. 4. Theoretical and Computational Works on Oxide Nuclear-Fuel Materials. 5. Fuel Technologies. 6. Summary. 7. Appendices.
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