摘要
从中子输运方程出发,推导中子流与中子标通量密度满足的普遍规律。通过定义一个与角通量密度相关的均匀化参数替换扩散系数,使得扩散求得的中子流密度和输运计算的结果保持一致,避免了传统扩散方法中扩散系数近似引入的误差,最终使得扩散方程求解得到与输运方程一致的结果。数值计算结果表明,与传统扩散方法相比,本文提出的等效扩散方法计算的有效增殖系数偏差从原有>2000pcm(1pcm=10^(-5))降低到50pcm以内,中子标通量密度的均方根偏差从原有的5%左右降低到0.5%左右,验证了本文方法的正确性。本文提出的方法能够为两步法中均匀化参数的设置以及基于扩散的加速方法提供新的思路和视角。
Starting from the neutron transport equation,this study derives the generalized relationship between neutron current and scalar flux distribution.By defining a homogenization parameter related to the angular flux density to replace the diffusion coefficient,the neutron current density obtained from the diffusion calculation remains consistent with the results of transport calculations.This avoids the errors introduced by the diffusion coefficient approximation in traditional diffusion methods,ultimately enabling the diffusion equation to yield results consistent with the transport equation.Numerical results show that compared to the traditional diffusion method,the effective multiplication factor deviation calculated by the equivalent diffusion method proposed in this paper is reduced from>2000pcm to<50pcm(1pcm=10^(-5)),and the root mean square deviation of neutron scalar flux density is reduced from~5%to~0.5%,validating the correctness of the proposed method.The method presented in this paper provides new insights and perspectives for the setting of homogenization parameters in two-step methods and diffusion-based acceleration algorithms.
作者
方超
彭星杰
赵文博
李庆
陈长
Fang Chao;Peng Xingjie;Zhao Wenbo;Li Qing;Chen Zhang(Nuclear Power Institute of China,Chengdu,610213,China;State Key Laboratory of Advanced Nuclear Energy Technology,Chengdu,610213,China)
出处
《核动力工程》
北大核心
2025年第S2期8-13,共6页
Nuclear Power Engineering
基金
国家重点研发计划(2021YFC2802600)
中国核动力研究设计院原创基金(KJCX-2023-YC1-01)。
关键词
中子输运方程
等效扩散方法
均匀化参数
Neutron transport equation
Equivalent diffusion method
Homogenization parameters
