Research on the Few Group Cross-section Production Method for Heat Pipe Micro Reactors Based on Monte Carlo Code

Xiao Peng; Luo Qi; Xia Bangyang; Yao Dong; Zhou Yajing; Fang Chao; Qin Tianjiao

doi:10.13832/j.jnpe.2023.06.0266

Volume 44 Issue 6

Dec. 2023

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Article Navigation > Nuclear Power Engineering > 2023 > 44(6): 266-274

Xiao Peng, Luo Qi, Xia Bangyang, Yao Dong, Zhou Yajing, Fang Chao, Qin Tianjiao. Research on the Few Group Cross-section Production Method for Heat Pipe Micro Reactors Based on Monte Carlo Code[J]. Nuclear Power Engineering, 2023, 44(6): 266-274. doi: 10.13832/j.jnpe.2023.06.0266

Citation:

Xiao Peng, Luo Qi, Xia Bangyang, Yao Dong, Zhou Yajing, Fang Chao, Qin Tianjiao. Research on the Few Group Cross-section Production Method for Heat Pipe Micro Reactors Based on Monte Carlo Code[J]. Nuclear Power Engineering, 2023, 44(6): 266-274. doi: 10.13832/j.jnpe.2023.06.0266

Citation:

Xiao Peng, Luo Qi, Xia Bangyang, Yao Dong, Zhou Yajing, Fang Chao, Qin Tianjiao. Research on the Few Group Cross-section Production Method for Heat Pipe Micro Reactors Based on Monte Carlo Code[J]. Nuclear Power Engineering, 2023, 44(6): 266-274. doi: 10.13832/j.jnpe.2023.06.0266

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Research on the Few Group Cross-section Production Method for Heat Pipe Micro Reactors Based on Monte Carlo Code

doi: 10.13832/j.jnpe.2023.06.0266

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

Received Date: 2023-08-21
Rev Recd Date: 2023-09-07
Publish Date: 2023-12-15

Abstract

Abstract

In order to improve the efficiency of the physical calculations of Heat Pipe Micro Reactors, based on the two-step method of cell homogenization-core transport calculation, this paper studies the few group cross-section production method for Heat Pipe Reactor core transport calculation by using the Monte Carlo (MC) code from the aspects of anisotropic scattering, fuel homogenization model, leakage correction and energy group structure. The numerical results show that using transport correction, leakage correction and other methods, and using a specialized "fuel-reflector" homogenization model for the peripheral fuel, the k_eff deviation obtained by the two-step core calculation is less than 100pcm (1pcm=10⁻⁵), the power distribution deviation is less than 3%, and the the control drum total worth deviation is less than 5%. Moreover, the core transport calculation cost is two orders of magnitude smaller than that of the Monte Carlo one-step full core calculation. Therefore, the two-step method of cell homogenization-core transport studied in this paper meets the accuracy requirements of engineering design and can greatly improve the efficiency of physical calculations of Heat Pipe Micro Reactors.
- Few group cross-section generation,
- Monte Carlo,
- Core transport,
- Heat Pipe Micro Reactors

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References(6)

References

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