Monte Carlo transport and burnup calculation

被引：0
|
作者：
Deng, L
Xie, ZS
Li, S
机构：
[1] Inst Appl Phys & Computat Math, Lab Computat Phys, Beijing 100088, Peoples R China
[2] Xian Jiaotong Univ, Dept Nucl Engn, Xian 710049, Peoples R China
来源：
ANNALS OF NUCLEAR ENERGY | 2003年 / 30卷 / 01期
关键词：
D O I：
暂无
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：
A 3-D multigroup P-3 neutron transport Monte Carlo code MCMG-BURN is developed for coupling neutron transport with burnup. MCMG-BURN code is based on Monte Carlo code MCNP with the continuous energy cross-section and the reactor lattice code WIMS. It uses the up-front multigroup macroscopic cross-section library based on burnup for Monte Carlo calculations, The almost consistent results with the experiments have been achieved. (C) 2002 Elsevier Science Ltd. All rights reserved.
引用
收藏
页码：127 / 132
页数：6
相关论文
共 50 条
  • [1] Data decomposition method for full-core Monte Carlo transport–burnup calculation
    Hong-Fei Liu
    Peng Ge
    Sheng-Peng Yu
    Jing Song
    Xiao-Lei Zheng
    [J]. Nuclear Science and Techniques, 2018, 29 (02) : 99 - 106
  • [2] Data decomposition method for full-core Monte Carlo transport–burnup calculation
    Hong-Fei Liu
    Peng Ge
    Sheng-Peng Yu
    Jing Song
    Xiao-Lei Zheng
    [J]. Nuclear Science and Techniques, 2018, 29
  • [3] Data decomposition method for full-core Monte Carlo transport-burnup calculation
    Liu, Hong-Fei
    Ge, Peng
    Yu, Sheng-Peng
    Song, Jing
    Zheng, Xiao-Lei
    [J]. NUCLEAR SCIENCE AND TECHNIQUES, 2018, 29 (02)
  • [4] RESEARCH ON COUPLING SCHEME OF MONTE CARLO BURNUP CALCULATION IN RMC
    Li, Wanlin
    Wang, Kan
    Yu, Ganglin
    Li, Yaodong
    [J]. PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 3, 2018,
  • [5] Comparative analysis of coupling schemes of Monte Carlo burnup calculation in RMC
    Li, Wanlin
    Yu, Ganglin
    Wang, Kan
    [J]. ANNALS OF NUCLEAR ENERGY, 2020, 137
  • [6] Improvement of Monte Carlo lattice burnup calculation performance with the correlated sampling method
    Moriwaki, M
    Aoyama, M
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2002, 39 (06) : 587 - 596
  • [7] MONTE CARLO CALCULATION OF TRANSPORT OF FAST ELECTRONS
    PERKINS, JF
    [J]. PHYSICAL REVIEW, 1962, 126 (05): : 1781 - &
  • [8] An optimum approach to Monte Carlo burnup
    Haeck, W.
    Verboomen, B.
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 2007, 156 (02) : 180 - 196
  • [9] Scattering direction biasing for Monte Carlo transport calculation
    Murata, I
    Yamamoto, H
    Miyamaru, H
    Goldenbaum, F
    Filges, D
    [J]. NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2006, 562 (02): : 845 - 848
  • [10] Analysis of Effectiveness on Monte Carlo Importance Biased Transport Calculation
    Xu, Haiyan
    Huang, Zhengfeng
    Cai, Shaohui
    [J]. COMMUNICATIONS IN COMPUTATIONAL PHYSICS, 2010, 8 (04) : 866 - 876
12345