Research on Few Group Cross-Section Generation Method For Fast Reactor Based on Monte Carlo Code

Xiao Peng; Luo Qi; Xia Bangyang; Zhang Guangchun; Yao Dong; Zhou Yajing; Fang Chao; Li Tianya

doi:10.13832/j.jnpe.2023.S2.0017

Volume 44 Issue S2

Dec. 2023

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Xiao Peng, Luo Qi, Xia Bangyang, Zhang Guangchun, Yao Dong, Zhou Yajing, Fang Chao, Li Tianya. Research on Few Group Cross-Section Generation Method For Fast Reactor Based on Monte Carlo Code[J]. Nuclear Power Engineering, 2023, 44(S2): 17-22. doi: 10.13832/j.jnpe.2023.S2.0017

Citation:

Xiao Peng, Luo Qi, Xia Bangyang, Zhang Guangchun, Yao Dong, Zhou Yajing, Fang Chao, Li Tianya. Research on Few Group Cross-Section Generation Method For Fast Reactor Based on Monte Carlo Code[J]. Nuclear Power Engineering, 2023, 44(S2): 17-22. doi: 10.13832/j.jnpe.2023.S2.0017

Citation:

Xiao Peng, Luo Qi, Xia Bangyang, Zhang Guangchun, Yao Dong, Zhou Yajing, Fang Chao, Li Tianya. Research on Few Group Cross-Section Generation Method For Fast Reactor Based on Monte Carlo Code[J]. Nuclear Power Engineering, 2023, 44(S2): 17-22. doi: 10.13832/j.jnpe.2023.S2.0017

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Research on Few Group Cross-Section Generation Method For Fast Reactor Based on Monte Carlo Code

doi: 10.13832/j.jnpe.2023.S2.0017

1.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
2.
China National Nuclear Corporation, Beijing, 100045, China
3.
School of Energy Science and Engineering, Harbin Institute of Technology, Harbin, 150001, China

Received Date: 2023-07-11
Rev Recd Date: 2023-08-03
Publish Date: 2023-12-30

Abstract

Abstract

In order to improve the accuracy of neutronics analysis for fast reactors and solve the complex resonance problem faced by traditional deterministic method in making few group cross-sections of fast reactors, this paper, based on the two-step method of assembly homogenization-core transport calculation, studies the method of assembly homogenized few group cross-section by using the Monte Carlo code from the aspects of anisotropic scattering, energy group structure and leakage correction. The numerical results show that the resonance effect of medium-mass nuclides can be well treated in the fast reactor few group cross-section generation based on the Monte Carlo code; the effects of anisotropic scattering can be effectively considered with 1-order scattering cross-section or transport modified few group section. Core effective multiplication factor ( k_eff ) may decrease due to the decrease in the number of energy groups of few group cross-section; core k_eff may increase due to the leakage correction. When Monte Carlo code is used in few group cross-sections generation of fast reactor, the k_eff deviation of core transport is less than 100 pcm (1pcm=10⁻⁵), and the power distribution deviation is less than 2%.
- Few group cross-section generation,
- Monte Carlo,
- Core transport,
- Fast reactor

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References(6)

References

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