中子吸收材料累积中子注量研究

Research of Neutron Fluence of Neutron Absorber Material

  • 摘要: 中子注量可作为加速辐照实验的辐照指标。为了通过加速辐照的方式检验中子吸收材料的中子吸收性能,计算了中子吸收材料贮存不同时间下的中子注量。通过对乏燃料组件初始富集度、燃耗深度以及乏池温度、可溶硼浓度的研究,得到中子吸收材料在乏池贮存时中子注量的包络值,同时计算得到不同贮存时间材料10B的消耗量。结果表明,材料的中子吸收性能在贮存10~60 a的情况下并无明显变化。本文结果可为检验材料的中子吸收性能提供支持。

     

    Abstract: Neutron fluence can be used as an indicator of accelerated irradiation experiments. In order to examine the neutron absorption properties of neutron absorber material by accelerated irradiation, the neutron fluence at different storage time of neutron absorber material was calculated. By studying the initial enrichment and burnup of spent fuel assemblies, spent fuel pool temperature and soluble boron concentration, the envelopment of neutron fluence during the storage in the spent fuel pool was obtained. At the same time, the 10B consumption at different storage time was calculated. The results show that the neutron absorption properties of the material in the storage of 10-60 a don’t change significantly. The results of this paper can support to examine the neutron absorption properties of material.

     

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