计算物理 ›› 2003, Vol. 20 ›› Issue (1): 65-70.

• 论文 • 上一篇    下一篇

多群输运-燃耗耦合蒙特卡罗计算

邓力1, 谢仲生2, 李树1   

  1. 1. 北京应用物理与计算数学研究所计算物理实验室, 北京 100088;
    2. 西安交通大学核能科学工程系, 陕西 西安 710049
  • 收稿日期:2001-09-19 修回日期:2002-01-31 出版日期:2003-01-25 发布日期:2003-01-25
  • 作者简介:邓力(i 1960-),male,Sichuan,Associate prefessor,PhD,engaged in Monte Carlo method and its applications. P. O. Box 8009-16, 100088.
  • 基金资助:
    Supported by the Science Foundation of China Academy of Engineering Physics under the Grant No.20010660

Multigroup Monte Carlo Calculation Coupled of Transport and Burnup

DENG Li1, XIE Zhong-sheng2, LI Shu1   

  1. 1. Laboratory of Computational Physics, Institute of Applied Physics and Computational Mathematics, Beijing 100088, China;
    2. Nuclear Engineering Department, Xi'an Jiaotong University, Xi'an 710049, China
  • Received:2001-09-19 Revised:2002-01-31 Online:2003-01-25 Published:2003-01-25
  • Supported by:
    Supported by the Science Foundation of China Academy of Engineering Physics under the Grant No.20010660

摘要: 介绍三维多群中子输运-燃耗耦合P3近似蒙特卡罗程序MCMG BURN.该程序是在连续截面蒙特卡罗程序MCNP和反应堆栅元均匀化程序WIMS基础上发展而来的.使用多群截面库模拟临界实验堆和高通量工程实验堆,取得了与MCNP和实验一致的结果.MCMG BURN具有与MCNP相同的精度,但计算时间较MCNP要少得多.

关键词: 三维多群, P3近似, 蒙特卡罗, 中子输运, 燃耗

Abstract: A 3-D multigroup P3 approximation Monte Carlo code MCMG-BURN is developed by coupling the neutron transport and burnup.MCMG-BURN code is based on the continuous-energy cross-section Monte Carlo code MCNP and the lattice homogeneous code WIMS.It uses the multigroup cross-section libraries to simulate the critical test reactors and HFETR(High Flux Engineering Test Reactor).The agreement results with the MCNP results and experiments are achieved.The MCMG-BURN code is at almost the same precision with the MCNP code while requiring considerably less computing time.

Key words: 3-D multigroup, P3 approximation, Monte Carlo, neutron transport, burnup

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