Study on non-uniform circumferential temperature distribution of annular fuel in the tight lattice configuration of a lead-bismuth cooled fast reactor

被引:0
|
作者
Zhang, Xiaolong [1 ]
Zeng, Fulin [1 ]
Zhao, Pengcheng [1 ]
机构
[1] Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Hunan, Peoples R China
关键词
Annular fuel; Circumferential temperature distribution; Numerical fitting; Lead-bismuth reactor; Computational fluid dynamics; FLOW;
D O I
10.1016/j.pnucene.2024.105383
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
To guarantee the safe operation of nuclear reactors and protect fuel elements from being damaged under longterm thermal stress, analyzing the circumferential temperature distribution of the outer cladding of nuclear fuel rods in reactors with tight lattice structures is crucial. In this work, a mathematical and physical model was established through theoretical analysis to calculate the circumferential temperature distribution of the outer cladding of an annular fuel rod. The proposed model provides an analytical expression for the circumferential temperature distribution, and the key factors influencing this distribution are determined. The results of the mathematical-physical model and numerical simulation are then combined through numerical fitting. Consequently, a numerical fitting equation is obtained under the steady-state condition of the lead-bismuth reactor using annular fuel and compared with the numerical simulation data acquired via computational fluid dynamics. The results demonstrate that the proposed numerical fitting equation has high accuracy and can serve as a valuable computational tool for analyzing the circumferential temperature of fuel claddings during the operation of lead-bismuth reactors with annular fuels.
引用
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页数:10
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