Research on the Neutron-photon Transport and Heat Calculation Method Based on MOSASAUR Code

Hu Kui; Ma Xubo; Wang Lianjie; Zhang Bin; Zhao Chen; Zhang Teng; Chen Yixue

doi:10.13832/j.jnpe.2024.03.0037

Volume 45 Issue 3

Jun. 2024

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Article Navigation > Nuclear Power Engineering > 2024 > 45(3): 37-44

Hu Kui, Ma Xubo, Wang Lianjie, Zhang Bin, Zhao Chen, Zhang Teng, Chen Yixue. Research on the Neutron-photon Transport and Heat Calculation Method Based on MOSASAUR Code[J]. Nuclear Power Engineering, 2024, 45(3): 37-44. doi: 10.13832/j.jnpe.2024.03.0037

Citation:

Hu Kui, Ma Xubo, Wang Lianjie, Zhang Bin, Zhao Chen, Zhang Teng, Chen Yixue. Research on the Neutron-photon Transport and Heat Calculation Method Based on MOSASAUR Code[J]. Nuclear Power Engineering, 2024, 45(3): 37-44. doi: 10.13832/j.jnpe.2024.03.0037

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Research on the Neutron-photon Transport and Heat Calculation Method Based on MOSASAUR Code

doi: 10.13832/j.jnpe.2024.03.0037

1.
School of Nuclear Science and Engineering, North China Electric Power University, Beijing, 102206, China
2.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2023-06-12
Rev Recd Date: 2023-07-16
Publish Date: 2024-06-13

Abstract

Abstract

To accurately calculate the heat released by all fissile and non-fissile materials in the fast reactor core, with a meticulous consideration of energy deposition by neutrons, photons, and electrons within the core, so as to enhance the precision of heat generation calculations, this paper, based on the deterministic two-step method, explores and implements a neutron-photon coupled transport calculation method. By solving the fission-source neutron transport equation and the fixed-source photon transport equation, the neutron and photon flux are obtained. Prompt neutron and prompt photon heat generation rates are calculated using the KERMA factor method. The delayed photon production matrix is computed using the scaling factor method. A self-coupling method in the MOSASAUR code is employed to achieve neutron-photon transport and heat generation calculations within the fast reactor core. The power distribution of the lead-bismuth fast reactor RBEC-M benchmark is compared with the results from Monte Carlo code. The relative deviations of total power are within ±4% for fuel assemblies, within ±10% for non-fuel assemblies, and within ±10% for all assemblies' photon power. Therefore, the neutron-photon transport and heat calculation method studied in this article has a high level of accuracy for the fast reactor cores.
- Neutron-photon transport,
- KERMA factor,
- Fast reactor,
- Delayed gamma,
- High-order photon transport

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References(13)

References

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