Modeling of Temperature and Burnup Distributions in the Uranium-Gadolinium Fuel Element of VVER

被引:0
|
作者
Yu. N. Devyatko
V. V. Novikov
O. V. Khomyakov
机构
[1] National Research Nuclear University MEPhI (Moscow Engineering Physics Institute),
[2] JSC Bochvar High-Tech Scientific and Research Institute of Inorganic Materials (JSC VNIINM),undefined
来源
Physics of Atomic Nuclei | 2018年 / 81卷
关键词
uranium-gadolinium fuel; burnable neutron absorber; burnup; thermal conductivity; temperature distribution;
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学科分类号
摘要
In this paper, we have developed a model for calculating of the fission rate and burnup in an uranium- gadolinium fuel (UGF) pellet. The heterogeneous fission rate distribution at beginning of life of the uranium-gadolinium fuel is shown to lead to the formation of a radial gradient of the porosity in the UGF pellet and to the heterogeneous radiation-induced densification of the fuel. We have also developed physical models of thermophysical properties of He, ZrO2, and zirconium cladding. Spatial and time temperature distributions in UGFE are calculated.
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页码:1257 / 1275
页数:18
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