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

Xindi Hu; Helin Gong; Shengfeng Zhu

doi:10.1016/j.net.2024.103420

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

Xindi Hu
, Helin Gong
, Shengfeng Zhu^*

^*Corresponding author for this work

School of Mathematical Sciences

Research output: Contribution to journal › Article › peer-review

1 Scopus citations

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.

Original language	English
Article number	103420
Journal	Nuclear Engineering and Technology
Volume	57
Issue number	6
DOIs	https://doi.org/10.1016/j.net.2024.103420
State	Published - Jun 2025

Keywords

Eigenvalue problem
Finite element method
Neutron diffusion equation
Two-grid

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10.1016/j.net.2024.103420

Cite this

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title = "A multi-scale finite element method for neutron diffusion eigenvalue problem",

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.",

keywords = "Eigenvalue problem, Finite element method, Neutron diffusion equation, Two-grid",

author = "Xindi Hu and Helin Gong and Shengfeng Zhu",

note = "Publisher Copyright: {\textcopyright} 2025 Korean Nuclear Society",

year = "2025",

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T1 - A multi-scale finite element method for neutron diffusion eigenvalue problem

AU - Hu, Xindi

AU - Gong, Helin

AU - Zhu, Shengfeng

PY - 2025/6

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N2 - 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.

AB - 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.

KW - Eigenvalue problem

KW - Finite element method

KW - Neutron diffusion equation

KW - Two-grid

UR - https://www.scopus.com/pages/publications/85214670165

U2 - 10.1016/j.net.2024.103420

DO - 10.1016/j.net.2024.103420

M3 - 文章

AN - SCOPUS:85214670165

SN - 1738-5733

VL - 57

JO - Nuclear Engineering and Technology

JF - Nuclear Engineering and Technology

IS - 6

M1 - 103420

ER -

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

Abstract

Keywords

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