《Table 1 Neutron yield per gamma from MCS》
本系列图表出处文件名:随高清版一同展现
《A study of PFBR auxiliary neutron source strength activation and its variability with respect to the neutron spectrum and ~(123)Sb capture cross section》
Then,the total photoneutron reaction rate is estimated using the average saturation gamma flux in beryllium and the beryllium photoneutron cross section from ENDF/B-VII.1.The neutron source strength calculated by this method is 9.26 9 1011n/s/SA(saturated),and the estimated neutron yield is 1.87 9 10-4n/c.The photoneutron yield is also verified by an independent application-specific Monte Carlo simulation(MCS)of gamma transport in the SSA by assuming a uniform gamma source strength in the antimony pins and subsequent transport through the pins and beryllium block.The photonuclear and photoatomic interaction cross sections are obtained from ENDF/B-VII.1.Table 1 gives the estimated neutron yield per gamma.The results show that the neutron yields per gamma for the SSA antimony–beryllium geometry obtained by the two methods are in very good agreement.
图表编号 | XD0065045500 严禁用于非法目的 |
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绘制时间 | 2019.08.01 |
作者 | G.Pandikumar、D.Sunil Kumar、M.M.Shanthi、Bagchi Subhrojit、A.John Arul、D.Venkata Subramanian、Rajeev Ranjan Prasad |
绘制单位 | Reactor Shielding and Data Division, Department of Atomic Energy,Nuclear Systems Design Group, Reactor Design Group, Indira Gandhi Centre for Atomic Research、Reactor Shielding and Data Division, Department of Atomic Energy,Nuclear Systems Design Group, Re |
更多格式 | 高清、无水印(增值服务) |
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