Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide
Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide
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Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide provides a comprehensive understanding of MOX properties for nuclear fuels, exploring fuel property simulation technology and irradiation behavior models. It investigates physical property data to develop MOX fuel for sodium-cooled fast reactors and presents a science-based model (Sci-M Pro) for fuel-performance code development.
Format: Hardback
Length: 172 pages
Publication date: 18 October 2022
Publisher: Taylor & Francis Ltd
Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide delves into a comprehensive understanding of MOX properties, which are crucial for evaluating the performance of nuclear fuels. It provides a thorough review of fuel property simulation technology and an irradiation behavior model, both essential for performance assessment. Through extensive research, the book explores various physical property data to develop MOX fuel for sodium-cooled fast reactors. It discusses a comprehensive database of MOX properties, encompassing oxygen potential, melting temperature, lattice parameter, sound speeds, thermal expansion, thermal diffusivity, oxygen self-diffusion, and chemical diffusion coefficients. This database serves as the foundation for deriving a science-based model of MOX properties (Sci-M Pro) to facilitate fuel-performance code development.
The book offers a concise yet comprehensive coverage of MOX nuclear fuels, systematically evaluating various physical property values through a behavior model. It highlights fuel property simulation technology, emphasizing its significance in understanding the behavior of MOX fuels under irradiation conditions. Additionally, the book delves into oxygen potential, the lattice parameter, sound speeds, and oxygen self-diffusion, providing valuable insights into the properties of MOX materials. Furthermore, it discusses melting temperature, thermal expansion, thermal diffusivity, and chemical diffusion coefficients, contributing to a comprehensive understanding of MOX nuclear fuels.
With its extensive coverage, Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide is an invaluable resource for researchers and engineers engaged in the field of nuclear fuels and nuclear materials. It serves as a comprehensive guide for understanding MOX properties, fuel property simulation technology, and irradiation behavior models, enabling professionals to make informed decisions and advancements in this critical domain.
Weight: 500g
Dimension: 234 x 156 (mm)
ISBN-13: 9781032287133
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