强激光与粒子束2012,Vol.24Issue(12):2951-2954,4.DOI:10.3788/HPLPB20122412.2951
基于FLUKA计算压力容器快中子注量的可行性研究
Validity of FLUKA applied to calculation of fast neutron fluence in reactor pressure vessel
苏耿华 1韩嵩1
作者信息
- 1. 中科华核电技术研究院有限公司,广东深圳518026
- 折叠
摘要
Abstract
Based on the consideration of intellectual property, in order to find an alternative code of MCNP, the validity of FLUKA applied to the calculation of neutron fluence in reactor pressure vessel was studied by means of comparison of calculation results of the both codes. The secondary particle stack was manipulated by modifying and calling the user subroutines, and then the key problem of turning off the transportation of fission neutrons was solved. The results of FLUKA and MCNP code agree well with each other, with the relative deviation less than 5%. It is concluded that using FLUKA code in place of MCNP code is technically feasible.关键词
FLUKA程序/蒙特卡罗程序/反应堆压力容器/中子注量Key words
FLUKA code/ Monte Carlo code/ reactor pressure vessel/ neutron fluence分类
能源科技引用本文复制引用
苏耿华,韩嵩..基于FLUKA计算压力容器快中子注量的可行性研究[J].强激光与粒子束,2012,24(12):2951-2954,4.