Multicell Correction Method for Treatment of Heterogeneities in Full-Core Calculation of CANDU-Type Reactors

被引:4
|
作者
Shen, Wei [1 ]
Altiparmakov, Dimitar [2 ]
机构
[1] Candu Energy Inc, Mississauga, ON L5K 1B1, Canada
[2] Atom Energy Canada Ltd, Chalk River Labs, Chalk River, ON K0J 1J0, Canada
关键词
LATTICES;
D O I
10.13182/NSE12-42
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This paper presents a multicell correction method that has been developed and implemented in the code suite WIMS-AECL/RFSP to capture the effects of the lattice-cell neighborhood while maintaining the basic structure of the single-cell-based reactor-physics methodology traditionally used for Canada Deuterium Uranium (CANDU)-reactor calculations for decades. To validate the effectiveness in treating the core-reflector interface heterogeneity as well as the checkerboard-voiding scenario, the results of WIMS-AECL/RFSP calculations (with and without the multicell correction) are compared with the results of MCNP5 full-core calculations for CANDU-type reactors. The presented results show that the multicell correction method is effective, generic, and capable of capturing the heterogeneity effects of the neighborhood in CANDU-type reactors.
引用
收藏
页码:109 / 134
页数:26
相关论文
共 6 条
  • [1] The evaluation of RCS depressurization to prevent core melting in pressure tube reactors (CANDU-type)
    Mehedinteanu, Stefan
    ANNALS OF NUCLEAR ENERGY, 2009, 36 (04) : 537 - 545
  • [2] On the better performance of the coarse-mesh finite-difference method for CANDU-type reactors
    Shen, W.
    ANNALS OF NUCLEAR ENERGY, 2012, 46 : 169 - 178
  • [3] Data decomposition method for full-core Monte Carlo transport–burnup calculation
    Hong-Fei Liu
    Peng Ge
    Sheng-Peng Yu
    Jing Song
    Xiao-Lei Zheng
    Nuclear Science and Techniques, 2018, 29 (02) : 99 - 106
  • [4] Data decomposition method for full-core Monte Carlo transport–burnup calculation
    Hong-Fei Liu
    Peng Ge
    Sheng-Peng Yu
    Jing Song
    Xiao-Lei Zheng
    Nuclear Science and Techniques, 2018, 29
  • [5] Data decomposition method for full-core Monte Carlo transport-burnup calculation
    Liu, Hong-Fei
    Ge, Peng
    Yu, Sheng-Peng
    Song, Jing
    Zheng, Xiao-Lei
    NUCLEAR SCIENCE AND TECHNIQUES, 2018, 29 (02)
  • [6] A computationally efficient method for full-core conjugate heat transfer modeling of sodium fast reactors
    Hu, Rui
    Yu, Yiqi
    NUCLEAR ENGINEERING AND DESIGN, 2016, 308 : 182 - 193