Boron Equivalent Measurement of Nuclear Graphite with Photoneutron Source

WANG Xiaohe; HU Jifeng; CHEN Jingen; CAI Xiangzhou; WANG Naxiu; WANG Hongwei; HAN Jianlong

doi:10.7538/yzk.2019.youxian.0781

Atomic Energy Science and Technology > 2020 > 54(11): 1991-1998. > DOI: 10.7538/yzk.2019.youxian.0781

WANG Xiaohe, HU Jifeng, CHEN Jingen, CAI Xiangzhou, WANG Naxiu, WANG Hongwei, HAN Jianlong. Boron Equivalent Measurement of Nuclear Graphite with Photoneutron Source[J]. Atomic Energy Science and Technology, 2020, 54(11): 1991-1998. DOI: 10.7538/yzk.2019.youxian.0781

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Boron Equivalent Measurement of Nuclear Graphite with Photoneutron Source

Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
CAS Innovative Academies in TMSR Energy System, Shanghai 201800, China
University of Chinese Academy of Sciences, Beijing 100049, China
Shanghai Advanced Research Institute, Chinese Academy of Sciences, Shanghai 201204, China

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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.
- photoneutron source,
- nuclear graphite,
- boron equivalent,
- MCNP simulation

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