Advance Search
Volume 31 Issue 4
Aug.  2010
Turn off MathJax
Article Contents
JIE Jia-chun, ZHAO Shou-zhi, SUN Zheng, JIA Bao-shan. Problem and Solution of Tally Segment Card in MCNP Code[J]. Nuclear Power Engineering, 2010, 31(4): 16-20.
Citation: JIE Jia-chun, ZHAO Shou-zhi, SUN Zheng, JIA Bao-shan. Problem and Solution of Tally Segment Card in MCNP Code[J]. Nuclear Power Engineering, 2010, 31(4): 16-20.

Problem and Solution of Tally Segment Card in MCNP Code

  • Received Date: 2009-05-12
  • Rev Recd Date: 2009-12-06
  • Publish Date: 2010-08-01
  • Wrong results may be given when FS card(tally segment card) was used for tally with other tally cards in Monte Carlo code MCNP.According to the comparison of segment tally results which were obtained by FS card of three different models of the same geometry,the tally results of fuel regions were found to be wrong in fill pattern.The reason is that the fuel cells were described by Universe card and FILL card,and the filled cells were always considered at Universe card definition place.A proposed solution was that the segment tally for filled cells was done at Universe card definition place.Radial flux distribution of one example was calculated in this way.The results show that the fault of segment tally with FS card in fill pattern could be solved by this method.

     

  • loading
  • 加载中

Catalog

    通讯作者: 陈斌, bchen63@163.com
    • 1. 

      沈阳化工大学材料科学与工程学院 沈阳 110142

    1. 本站搜索
    2. 百度学术搜索
    3. 万方数据库搜索
    4. CNKI搜索

    Article Metrics

    Article views (7) PDF downloads(0) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return