Research of Material Irradiation Fine Neutron Flux Spectrum in HFETR
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摘要: 采用蒙特卡洛程序(MCNP)模拟计算高通量工程试验堆(HFETR)典型辐照孔道内样品精细中子注量率谱,包括轴向、径向中子注量率谱及172群中子能谱,分析其特点和变化规律,同时比较辐照孔道填充不同材料时的中子能谱。结果表明:不同孔道辐照相同材料及同一孔道辐照不同材料时,所得的能谱分布趋势和特点比较一致。在高能区,中子能谱近似为于裂变中子谱分布;在慢化能区,近似为费米谱分布;而在热能区,近似为麦克斯韦谱分布。
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关键词:
- 精细中子注量率谱 /
- 辐照孔道 /
- MCNP /
- 高通量工程试验堆(HFETR)
Abstract: The paper calculated and compared the fine neutron flux spectrum of the material at the typical irradiation channels of HFETR using MCNP code,including axial and radial distribution of neutron fluxes,and the 172-group neutron energy spectrum.It indicates that the distributions and characteristics of neutron energy spectrum in different channels filled with the same material,and in the same channel filled with different materials are almost identical,that is,the neutron energy spectrum with high energy is similar to fission neutron spectrum,the spectrums with middle energy and low energy are similar to Fermi spectrum distribution and Maxwell distribution separately.-
Key words:
- Fine neutron flux spectrum /
- Irradiation channel /
- MCNP /
- HFETR
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