中子慢化材料特性研究

Research on Characteristic of Neutron Moderating Material

  • 摘要: 文章采用蒙特卡罗模拟计算方法分析铝、氧化铝和氟化铝3种慢化材料在清华大学试验核反应堆束流孔道内的慢化特性。研究给出了利用慢化材料实现超热中子辐射场的一般规律,并优选出适用于在该堆建立超热中子辐射场的最佳慢化材料是Al与AlF3质量百分数比为2∶3的Al-AlF3混合物。

     

    Abstract: The research concerns in the moderating characteristics analysis of Al, Al2O3 and AlF3 placed in the neutron beam passage of Tsinghua University experimental reactor by Monte-Carlo method. The main moderating performances of above 3 kinds of materials used in constructing epithermal neutron radiation field are obtained, and the optimized moderating material, an Al-AlF3 mixture with a mass fraction ratio w(Al)/w(AlF3)of 2/3, is recommended for Tsinghua University experimental reactor.

     

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