计算物理 ›› 2002, Vol. 19 ›› Issue (1): 67-72.

• 论文 • 上一篇    下一篇

向量裂变谱与矩阵裂变谱对临界计算的影响

邓力1, 刘瑞兰2, 谢仲生2   

  1. 1. 北京应用物理与计算数学研究所, 北京 100088;
    2. 西安交通大学能动学院核能工程系, 陕西 西安 710049
  • 收稿日期:2000-02-25 修回日期:2001-01-31 出版日期:2002-01-25 发布日期:2002-01-25
  • 作者简介:邓力(1960-),男,四川绵竹,博士,从事粒了输运MC方法研究,北京市8009信箱100088.
  • 基金资助:
    中国工程物理研究院(20010660)

THE EFFECT OF VECTOR FISSION SPECTRUM AND MATRIX FISSION SPECTRUM ON THE CRITICAL CALCULATION

DENG Li1, LIU Rui-lan2, XIE Zhong-sheng2   

  1. 1. Institute of Applied Physics and Computational Mathematics, Beijing 100088, P R China;
    2. Xi'an Jiaotong University, Department of Nuclear Energy and Engineering, Xi'an 710049, P R China
  • Received:2000-02-25 Revised:2001-01-31 Online:2002-01-25 Published:2002-01-25

摘要: 用蒙特卡罗方法及可适应多种截面的三维多群P3中子输运蒙特卡罗程序MCMG,计算比较了不同裂变材料使用向量裂变谱与矩阵裂变谱的计算结果,通过与MCNP程序结果的比较,确信两种裂变谱对计算结果的影响是存在的,但对计算结果不会带来本质影响.同时还比较了不同中子截面库计算结果.

关键词: 矩阵裂变谱, 向量裂变谱, 临界计算, 蒙特卡罗

Abstract: When the fission reaction happens in neutron transport calculation,the energy of the fission neutron can be usually determined by the fission spectrum.Since the coefficient of the spectrum type depends on the incident neutron energy,the multigroup neutron fission spectrum should strictly be a matrix form.In general transport calculation,the 235U vector fission spectrum is usually chosen as the standard fission spectrum.In order to make clear what kind of effect will be produced after this treatment,the Monte Carlo method and the multigroup P3 Monte Carlo neutron transport code MCMG are used to analyze the difference between two types of fission spectrums.By comparison the results with MCNP code,it is certain that the difference exists,but it does not have any effect on the correction of the calculated results.At the same time,the calculation results of the different neutron cross section libraries have been compared.

Key words: matrix fission spectrum, vector fission spectrum, critical calculation, Monte Carlo

中图分类号: