Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide (Hardcover)

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.

General

Imprint:	Taylor & Francis
Country of origin:	United Kingdom
Release date:	September 2022
First published:	2023
Editors:	Masato Kato • Masahiko Machida
Dimensions:	234 x 156mm (L x W)
Format:	Hardcover
Pages:	172
ISBN-13:	978-1-03-228713-3
Categories:	Books > Professional & Technical > Energy technology & engineering > Nuclear power & engineering Books > Professional & Technical > Environmental engineering & technology > General
LSN:	1-03-228713-6
Barcode:	9781032287133

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