MCNP程序计数分段卡存在的问题及解决办法

解家春; 赵守智; 孙征; 贾宝山

MCNP程序计数分段卡存在的问题及解决办法

1. 清华大学工程物理系系, 北京, 100084;
2. 中国原子能科学研究院反应堆工程研究设计所, 北京, 102314

详细信息

作者简介:
解家春(1979-),男,博士研究生。2003年毕业于清华大学核能科学与工程专业。现从事反应堆物理研究。赵守智(1966-),男,研究员,博士生导师。2002毕业于中国原子能科学研究院核能科学与工程专业,获博士学位。现从事反应堆工程设计研究。孙征(1978-),男,工程师。2001年毕业于哈尔滨工程大学核工程专业,获学士学位。现从事反应堆物理研究。

中图分类号: TL329
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出版历程
- 收稿日期: 2009-05-12
- 修回日期: 2009-12-06
- 刊出日期: 2010-08-01

Problem and Solution of Tally Segment Card in MCNP Code

1. Department of Engineering Physics, Tsinghua University, Beijing, 10084, China;
2. Department of Reactor Engineering Research and Design, China Institute of Atomic Energy, Beijing, 102413, China

摘要

摘要: 当应用蒙特卡罗程序(MCNP)的计数分段卡(FS卡)配合其他计数卡进行分段计数时,可能给出错误的计数结果。通过比较FS卡对同一几何体的3种模型的分段计数结果发现,填充形式模型的燃料棒区域的计数结果不正确。其原因在于燃料棒栅元由栅元集合卡(Universe卡)和填充卡(Fill卡)填充得到,而分段计数时MCNP程序认为被填充的栅元仍位于Universe卡定义的几何体处。据此提出了在Universe卡定义的几何体处对被填充栅元进行分段计数的解决方法。对例题的径向中子注量率分布的计算表明,该方法能够解决FS卡对填充形式描述的几何体进行分段计数时出现的错误。
- MCNP程序 /
- FS卡 /
- 分段计数 /
- 填充 /
- 径向中子注量率
Abstract: 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.
- MCNP code /
- FS card /
- Segment tally /
- Fill /
- Radial flux distribution