Geometry Optimization of Monte Carlo Model of Fast Reactor Core

被引:0
|
作者
Wang Z. [1 ]
Huo X. [1 ]
Zhang J. [1 ]
Hu Y. [1 ]
机构
[1] Division of Reactor Engineering Technology Research, China Institute of Atomic Energy, Beijing
关键词
China Experimental Fast Reactor; Eigenvalue-difference method; Geometry simplification; Homogenization; Monte Carlo;
D O I
10.7538/yzk.2020.youxian.0158
中图分类号
学科分类号
摘要
In Monte Carlo calculation, the geometrical precision of model is equilibrium between calculation efficiency and accuracy of result. The precise modeling of reactor core largely decreases calculation efficiency, while homogenization by experience brings large deviation to the result. In this paper, the influence of geometry simplification of core structures of China Experimental Fast Reactor on keff was assessed based on eigenvalue-difference method, and an optimized core model was established. The results indicate that the optimized core model largely improves calculation efficiency with the result remaining almost the same. The detailed geometrical treatment and calculation results provide reference for Monte Carlo model in reactor core design and experiment analysis, and present academic worth to Monte Carlo code development and theoretical research. © 2021, Editorial Board of Atomic Energy Science and Technology. All right reserved.
引用
收藏
页码:258 / 264
页数:6
相关论文
共 11 条
  • [1] (1980)
  • [2] (2006)
  • [3] YU Shengpeng, CHENG Mengyun, LONG Peng-cheng, Et al., Improved void filling algorithm for automatic Monte Carlo modeling, Atomic Energy Science and Technology, 49, pp. 35-39, (2015)
  • [4] MCNP: A general Monte Carlo N-particle transport code, Version 5, (2003)
  • [5] Coordinated research activities
  • [6] HUO Xingkai, Technical specifications for neutronics benchmark of CEFR start-up tests, IAEA CRP-I31032Version 7, (2019)
  • [7] (2008)
  • [8] (2010)
  • [9] (2012)
  • [10] Dan GABRIEL C., Hand book of nuclear engineering, (2010)