Generation of the Few-Group Cross Sections for Molten Salt Reactors Based on Non-Uniform Spectra Modification Method

Dai Ming; Zhang Ao; Cheng Maosong

doi:10.13832/j.jnpe.2024.05.0062

Volume 45 Issue 5

Oct. 2024

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Dai Ming, Zhang Ao, Cheng Maosong. Generation of the Few-Group Cross Sections for Molten Salt Reactors Based on Non-Uniform Spectra Modification Method[J]. Nuclear Power Engineering, 2024, 45(5): 62-70. doi: 10.13832/j.jnpe.2024.05.0062

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Dai Ming, Zhang Ao, Cheng Maosong. Generation of the Few-Group Cross Sections for Molten Salt Reactors Based on Non-Uniform Spectra Modification Method[J]. Nuclear Power Engineering, 2024, 45(5): 62-70. doi: 10.13832/j.jnpe.2024.05.0062

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Generation of the Few-Group Cross Sections for Molten Salt Reactors Based on Non-Uniform Spectra Modification Method

doi: 10.13832/j.jnpe.2024.05.0062

Dai Ming^1
,,
Zhang Ao¹,
Cheng Maosong^{1, 2
,
,}

1.
Shanghai Institute of Applied Physics, Chinese Academy of Science, Shanghai, 201800, China
2.
University of Chinese Academy of Sciences, Beijing, 101408, China

Received Date: 2023-10-27
Rev Recd Date: 2024-01-12
Publish Date: 2024-10-14

Abstract

Abstract

In view of the high leakage and strong heterogeneity of molten salt reactors, the whole-core transport calculation based on the method of characteristic (MOC) is suitable for the critical calculation of molten salt reactors. To balance computational efficiency and accuracy, the non-uniform spectra modification (nSM) method is proposed to generate the few-group cross sections for MOC whole-core calculations. This method is an embedded leakage modification method, which utilizes the leakage parameters obtained by the few-group MOC whole-core calculation for multi-group spectrum calculations, thereby online updating the few-group cross sections of the whole-core calculation. Compared with results from the continuous energy Monto Carlo code OpenMC for the MSRE two-dimensional whole-core benchmark problems, the k_eff errors calculated by nSM method are less than 0.25% and the maximum error of 2.6% in fission rate distributions occurs at the core can node with a relative fission rate of only 0.04, which are obviously better than those using the cross sections collapsed by the spectra calculated by assembly calculations. The results show that the approximate nSM method still has good accuracy, and could significantly improve the calculation efficiency. Therefore, nSM method could be a feasible method that provides few-group cross sections for the MOC whole-core calculation of molten salt reactors.
- Non-uniform spectra modification,
- Molten salt reactors,
- MOC,
- Whole-core transport calculation,
- Generation of few-group cross sections

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References(16)

References

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