TY - JOUR
T1 - Central-Difference method based on consistent Half-Node linear approximation for the neutron diffusion equation
AU - Qin, Junwei
AU - Li, Yunzhao
AU - Cao, Liangzhi
AU - Wu, Hongchun
N1 - Publisher Copyright:
© 2026 Elsevier Ltd. All rights are reserved, including those for text and data mining, AI training, and similar technologies.
PY - 2027/1
Y1 - 2027/1
N2 - The finite difference method (FDM) is widely used in the numerical solution of the neutron transport equation due to its simplicity and ease of parallelization. However, inconsistent theoretical approximations appear in the conventional central difference method, which limits its accuracy and efficiency. A half-node linear approximation is employed for the leakage term, while a full-mesh linear approximation is applied to the collision and source terms.To eliminate this inconsistency, a Central Finite Difference Method based on a Consistent Half-node Linear approximation, named as HNL-CFDM is proposed in the paper. By adopting a consistent half-node linear approximation across all terms of the diffusion equation, this method ensures that the discrete formulation remains highly aligned with the physical essence of the continuous equation, thereby effectively enhancing spatial accuracy. In addition, to address the issue of slow convergence in large sparse linear systems often encountered in high-fidelity full-core calculations with this new scheme, a hybrid acceleration strategy combining Coarse Mesh Rebalance (CMR) and the Gauss-Seidel Left-preconditioned Generalized Minimal Residual method (gsl-GMRES) are developed.The performance of the proposed method was validated using the KAIST benchmark problems. Numerical results demonstrate that, compared to the FDM, the HNL-CFDM scheme achieves a nearly twofold improvement in the accuracy at the minimal cost of only a 7% increase in computation time. Furthermore, regarding iterative acceleration, the hybrid scheme achieves an acceleration ratio of approximately 12 times compared to the traditional Gauss-Seidel (GS) iteration method.This study confirms that the proposed method greatly improves the accuracy of neutron diffusion calculations while maintaining computational efficiency, providing a more reliable numerical tool for reactor physics analysis.
AB - The finite difference method (FDM) is widely used in the numerical solution of the neutron transport equation due to its simplicity and ease of parallelization. However, inconsistent theoretical approximations appear in the conventional central difference method, which limits its accuracy and efficiency. A half-node linear approximation is employed for the leakage term, while a full-mesh linear approximation is applied to the collision and source terms.To eliminate this inconsistency, a Central Finite Difference Method based on a Consistent Half-node Linear approximation, named as HNL-CFDM is proposed in the paper. By adopting a consistent half-node linear approximation across all terms of the diffusion equation, this method ensures that the discrete formulation remains highly aligned with the physical essence of the continuous equation, thereby effectively enhancing spatial accuracy. In addition, to address the issue of slow convergence in large sparse linear systems often encountered in high-fidelity full-core calculations with this new scheme, a hybrid acceleration strategy combining Coarse Mesh Rebalance (CMR) and the Gauss-Seidel Left-preconditioned Generalized Minimal Residual method (gsl-GMRES) are developed.The performance of the proposed method was validated using the KAIST benchmark problems. Numerical results demonstrate that, compared to the FDM, the HNL-CFDM scheme achieves a nearly twofold improvement in the accuracy at the minimal cost of only a 7% increase in computation time. Furthermore, regarding iterative acceleration, the hybrid scheme achieves an acceleration ratio of approximately 12 times compared to the traditional Gauss-Seidel (GS) iteration method.This study confirms that the proposed method greatly improves the accuracy of neutron diffusion calculations while maintaining computational efficiency, providing a more reliable numerical tool for reactor physics analysis.
KW - Diffusion Equation
KW - Finite Difference
KW - Half-node Approximation
UR - https://www.scopus.com/pages/publications/105046714729
U2 - 10.1016/j.anucene.2026.112727
DO - 10.1016/j.anucene.2026.112727
M3 - 文章
AN - SCOPUS:105046714729
SN - 0306-4549
VL - 240
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
M1 - 112727
ER -