Study on On-the-fly Cross-Section Treatment and Burnup Calculation of Space Nuclear Reactor Based on Monte Carlo Method

Li Rui; Liu Shichang; Che Rui; Lu Di; Wang Lianjie; Wang Zhenyu; Chen Yixue

doi:10.13832/j.jnpe.2022.S2.0111

Volume 43 Issue S2

Dec. 2022

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Article Navigation > Nuclear Power Engineering > 2022 > 43(S2): 111-117

Li Rui, Liu Shichang, Che Rui, Lu Di, Wang Lianjie, Wang Zhenyu, Chen Yixue. Study on On-the-fly Cross-Section Treatment and Burnup Calculation of Space Nuclear Reactor Based on Monte Carlo Method[J]. Nuclear Power Engineering, 2022, 43(S2): 111-117. doi: 10.13832/j.jnpe.2022.S2.0111

Citation:

Li Rui, Liu Shichang, Che Rui, Lu Di, Wang Lianjie, Wang Zhenyu, Chen Yixue. Study on On-the-fly Cross-Section Treatment and Burnup Calculation of Space Nuclear Reactor Based on Monte Carlo Method[J]. Nuclear Power Engineering, 2022, 43(S2): 111-117. doi: 10.13832/j.jnpe.2022.S2.0111

Citation:

Li Rui, Liu Shichang, Che Rui, Lu Di, Wang Lianjie, Wang Zhenyu, Chen Yixue. Study on On-the-fly Cross-Section Treatment and Burnup Calculation of Space Nuclear Reactor Based on Monte Carlo Method[J]. Nuclear Power Engineering, 2022, 43(S2): 111-117. doi: 10.13832/j.jnpe.2022.S2.0111

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Study on On-the-fly Cross-Section Treatment and Burnup Calculation of Space Nuclear Reactor Based on Monte Carlo Method

doi: 10.13832/j.jnpe.2022.S2.0111

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: 2022-07-22
Rev Recd Date: 2022-09-26
Publish Date: 2022-12-31

Abstract

Abstract

To solve the problem of on-the-fly cross-section treatment in the calculation of the Monte Carlo (MC) code, the target motion sampling method and the improved Gauss-Hermite method are used to calculate the effective multiplication factor ( k_eff) at different fuel temperatures for the resolvable resonance energy region. Two cross-section treatment methods are applied to the kilowatt-class heat pipe space nuclear reactor model and compared with the calculation results of keff using the accurate temperature cross-section library. The results show that for k eff at different temperatures, the absolute errors of the two methods are within ± 3 times the relative combined statistical error. The calculation time of the target motion sampling method and the improved Gauss-Hermite method increases by 45% and 9%, respectively. To solve the burnup calculation problem in space reactors, the internal coupling burnup calculation function of the Reactor Monte Carlo code (RMC) is applied to the megawatt-class heat pipe space nuclear reactor model and the prism-type high-temperature gas-cooled reactor model, and compared with typical MC code Serpent and MCNP. The results show that the maximum error of k_effis less than 0.2% and 0.3% at each burnup step. Two studies preliminarily verify the correctness of RMC's on-the-fly cross-section treatment and burnup calculation of space nuclear reactors.
- On-the-fly cross-section treatment,
- Burnup calculation,
- Space nuclear reactor,
- Monte Carlo

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References(19)

References

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