Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide

铀钚混合氧化物材料科学与燃料技术

化学工程基础学科

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1314.00
发货周期:国外库房发货,通常付款后3-5周到货!
出  版 社
出版时间
2022年09月29日
装      帧
精装
ISBN
9781032287133
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页      码
182
开      本
234 x 156 mm (6.14 x 9.21
语      种
英文
版      次
1
综合评分
5 分
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图书简介
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.
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