TY - JOUR
T1 - Simulating Fuel Assembly Bowing
T2 - A Neutron-Diffusion Method Based on Arbitrary Quadrilateral Node and Conformal Mapping Technique
AU - Wu, Hongchun
AU - Guo, Lin
AU - Wan, Chenghui
N1 - Publisher Copyright:
© 2024 American Nuclear Society.
PY - 2025
Y1 - 2025
N2 - Fuel assembly bowing, widely observed in a pressurized water reactor (PWR), often results in an asymmetrical power distribution. This paper proposes a neutron-diffusion method that integrates the arbitrary quadrilateral node with the conformal mapping technique to characterize the impact of fuel assembly bowing on power distribution. The proposed method involves a nonlinear iteration process to solve the neutron-diffusion equation. The global coarse-mesh finite difference equation is established on the arbitrary quadrilateral nodes, which are redivided in response to fuel assembly bowing. The local two-node nodal expansion method equation is established on the rectangular nodes, which are mapped from the original arbitrary quadrilateral nodes using the conformal mapping technique. The proposed method has improved our self-developed core code, named SPARK, for PWRs. To verify this novel method, two distinct types of fuel assembly bowing are modeled based on the mini core. The reference results for these models were obtained using the Monte Carlo code NECP-MCX. The numerical results suggest a robust agreement between the biases of keff and power distributions and their corresponding reference results.
AB - Fuel assembly bowing, widely observed in a pressurized water reactor (PWR), often results in an asymmetrical power distribution. This paper proposes a neutron-diffusion method that integrates the arbitrary quadrilateral node with the conformal mapping technique to characterize the impact of fuel assembly bowing on power distribution. The proposed method involves a nonlinear iteration process to solve the neutron-diffusion equation. The global coarse-mesh finite difference equation is established on the arbitrary quadrilateral nodes, which are redivided in response to fuel assembly bowing. The local two-node nodal expansion method equation is established on the rectangular nodes, which are mapped from the original arbitrary quadrilateral nodes using the conformal mapping technique. The proposed method has improved our self-developed core code, named SPARK, for PWRs. To verify this novel method, two distinct types of fuel assembly bowing are modeled based on the mini core. The reference results for these models were obtained using the Monte Carlo code NECP-MCX. The numerical results suggest a robust agreement between the biases of keff and power distributions and their corresponding reference results.
KW - Neutron-diffusion method
KW - arbitrary quadrilateral node
KW - conformal mapping technique
KW - fuel assembly bowing
UR - https://www.scopus.com/pages/publications/85192148836
U2 - 10.1080/00295639.2024.2334988
DO - 10.1080/00295639.2024.2334988
M3 - 文章
AN - SCOPUS:85192148836
SN - 0029-5639
VL - 199
SP - 115
EP - 130
JO - Nuclear Science and Engineering
JF - Nuclear Science and Engineering
IS - 1
ER -