Analysis of different burnup calculation models on nuclide components of spent fuel assembly in commercial pressurized water reactor

Chen Xirong; Xie Jinsen; Yu Tao; Ni Zining; Deng Nianbiao; Shao Zeng; Xie Haoran

doi:10.11884/HPLPB202335.230010

Volume 35 Issue 5

Apr. 2023

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Chen Xirong, Xie Jinsen, Yu Tao, et al. Analysis of different burnup calculation models on nuclide components of spent fuel assembly in commercial pressurized water reactor[J]. High Power Laser and Particle Beams, 2023, 35: 056002. doi: 10.11884/HPLPB202335.230010

Citation:

Chen Xirong, Xie Jinsen, Yu Tao, et al. Analysis of different burnup calculation models on nuclide components of spent fuel assembly in commercial pressurized water reactor[J]. High Power Laser and Particle Beams, 2023, 35: 056002. doi: 10.11884/HPLPB202335.230010

Citation:

Chen Xirong, Xie Jinsen, Yu Tao, et al. Analysis of different burnup calculation models on nuclide components of spent fuel assembly in commercial pressurized water reactor[J]. High Power Laser and Particle Beams, 2023, 35: 056002. doi: 10.11884/HPLPB202335.230010

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Analysis of different burnup calculation models on nuclide components of spent fuel assembly in commercial pressurized water reactor

doi: 10.11884/HPLPB202335.230010

Chen Xirong^{1, 2
,},
Xie Jinsen^{1, 2},
Yu Tao^{1, 2
,
,},
Ni Zining^{1, 2},
Deng Nianbiao^{2, 3},
Shao Zeng⁴,
Xie Haoran^{1, 2}

1.
School of Nuclear Science and Technology, University of South China, Hengyang 421001, China
2.
Virtual Simulation Experiment Teaching Center on Nuclear Energy and Technology, University of South China, Hengyang 421001, China
3.
School of Resource Environment and Safety Engineering, University of South China, Hengyang 421001, China
4.
China Nuclear Power Engineering Co., Ltd, Beijing 100840, China

Received Date: 2023-01-13
Rev Recd Date: 2023-02-18

Available Online: 2022-11-24

Publish Date: 2023-04-07

Abstract

Abstract

Burnup credit has an important impact on improving the efficiency of spent fuel storage. In the burnup credit, the burnup calculation model can affect the nuclide composition deviation, and the more accurate the nuclide composition, the lower the critical safety margin for spent fuel storage. To improve the accuracy of the burnup calculation, a multi-assembly burnup calculation model loaded with different fuel enrichment is proposed in this paper. Six samples of TMI-1 reactor NJ07OG assemblies were calculated, compared and analyzed by using different burnup calculation models. The results show that the average relative deviations of ²³⁵U, ²³⁸U and ²³⁹Pu obtained from the multi-assembly burnup model with different fuel enrichment are closer to zero and the relative deviations are more evenly distributed among the six samples than that of other models.
- burnup calculation model,
- SFCOMPO-2.0,
- nuclide deviation,
- burnup credit

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References(19)

References

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