Boron Equivalent Measurement of Nuclear Graphite with Photoneutron Source

被引：0
|
作者：
Wang X. [1 ,2 ,3 ]
Hu J. [1 ,2 ]
Chen J. [1 ,2 ,3 ]
Cai X. [1 ,2 ,3 ]
Wang N. [1 ,2 ,3 ]
Wang H. [4 ]
Han J. [1 ,2 ]
机构：
[1] Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai
[2] CAS Innovative Academies in TMSR Energy System, Shanghai
[3] University of Chinese Academy of Sciences, Beijing
[4] Shanghai Advanced Research Institute, Chinese Academy of Sciences, Shanghai
来源：
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2020年 / 54卷 / 11期
关键词：
Boron equivalent; MCNP simulation; Nuclear graphite; Photoneutron source;
D O I：
10.7538/yzk.2019.youxian.0781
中图分类号：
学科分类号：
摘要：
Impurities in nuclear materials with high thermal neutron absorption cross section will change the reactivity. The absorption of thermal neutrons by these impurities is represented by boron equivalent, which is one of the important factors to measure the purity of nuclear materials. Boron equivalent can be determined directly via the measurement of macroscopic thermal neutron absorption cross section based on an isotopic neutron source, but with lower accuracy. The photoneutron source, which can generate neutrons with higher intensity, better direction and lower energy, can effectively improve the accuracy of boron equivalence measurement. Therefore, the boron equivalent measurement of nuclear graphite was carried out with the photoneutron source driven by 15 MeV electron LINAC. Monte Carlo simulation method was used to optimize the experimental scheme, and the experimental data were tested and modified. Finally, the quantitative analysis method was established for the measurement of graphite boron equivalent. This method can quickly and accurately measure the boron equivalent of nuclear materials, which is of great significance for the physical design and safety assessment of the reactor. © 2020, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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页码：1991 / 1998
页数：7
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