Research on Method of Generating Monte Carlo Multigroup Library for Fast Reactor

Zhu Shuaitao; Ma Xubo; Xu Qian; Cao Bo; Chen Yixue

Volume 41 Issue 5

Sep. 2020

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Article Navigation > Nuclear Power Engineering > 2020 > 41(5): 35-39

Zhu Shuaitao, Ma Xubo, Xu Qian, Cao Bo, Chen Yixue. Research on Method of Generating Monte Carlo Multigroup Library for Fast Reactor[J]. Nuclear Power Engineering, 2020, 41(5): 35-39.

Citation:

Zhu Shuaitao, Ma Xubo, Xu Qian, Cao Bo, Chen Yixue. Research on Method of Generating Monte Carlo Multigroup Library for Fast Reactor[J]. Nuclear Power Engineering, 2020, 41(5): 35-39.

Zhu Shuaitao, Ma Xubo, Xu Qian, Cao Bo, Chen Yixue. Research on Method of Generating Monte Carlo Multigroup Library for Fast Reactor[J]. Nuclear Power Engineering, 2020, 41(5): 35-39.

Citation:

Zhu Shuaitao, Ma Xubo, Xu Qian, Cao Bo, Chen Yixue. Research on Method of Generating Monte Carlo Multigroup Library for Fast Reactor[J]. Nuclear Power Engineering, 2020, 41(5): 35-39.

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Research on Method of Generating Monte Carlo Multigroup Library for Fast Reactor

Publish Date: 2020-09-27

Abstract

Abstract

Based on the discrete angle method, a Monte Carlo multi-group cross section generation program MGXSMC was developed. This program can read the cross section data from an input file or read the cross section from a library in a specified format to generate the multi-group cross section for MCNP or RMC. The corresponding index file list can be automatically generated. The two-dimensional two-group IAEA pressurized water reactor (PWR) benchmark and lead-based fast reactor (RBEC-M) benchmark were used to verify the cross section library generated by the MGXSMC program. The calculation results show that the difference between the calculated result of the P5 order approximate multigroup section and the continuous point cross section is 24 pcm (1pcm = 10-5), and the difference of the keff result calculated by the P0 order approximate multigroup section and the continuous point section is large. This shows that the method and the program developed for the Monte Carlo Group Section Library are correct. At the same time, the neutron anisotropic scattering has a large impact on the calculation results of the lead-based fast reactor. Therefore, when the Monte Carlo Group Section library is produced, the neutron scattering angle data should be added.
- Monte Carlo multigroup library,
- Scattering cross section,
- Criticality calculation,
- MGXSMC

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