A multi-scale finite element method for neutron diffusion eigenvalue problem

Gong Helin; Hu Xindi; Zhu Shengfeng

doi:10.1016/j.net.2024.103420

논문KCI 등재

A multi-scale finite element method for neutron diffusion eigenvalue problem

Gong Helin|Hu Xindi|Zhu Shengfeng

한국원자력학회 (Korean Nuclear Society)|2025.06|Nuclear Engineering and Technology|제57권 제6호|DOI 10.1016/j.net.2024.103420

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키워드

Finite element method Neutron diffusion equation Two-grid Eigenvalue problem

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초록

In this paper, we propose a multi-scale finite element method for solving the two-group neutron diffusion equation, which represents the distribution of neutrons in thermal reactors. More specifically, a coarse-fine two-grid is employed for finite element discretizations. The two-grid algorithm can keep asymptotical accuracy of the single fine-grid finite element method, while saving computational costs. Numerical results are presented to show the effectiveness and efficiency of the algorithm

Abstract

In this paper, we propose a multi-scale finite element method for solving the two-group neutron diffusion equation, which represents the distribution of neutrons in thermal reactors. More specifically, a coarse-fine two-grid is employed for finite element discretizations. The two-grid algorithm can keep asymptotical accuracy of the single fine-grid finite element method, while saving computational costs. Numerical results are presented to show the effectiveness and efficiency of the algorithm

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