Research on Burnup Calculation Method Based on Splicing Fission Matrix

Gao Ruishuang; Liu Xiaojing; He Donghao; Pan Qingquan

doi:10.13832/j.jnpe.2024.02.0019

Volume 45 Issue 2

Apr. 2024

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Article Navigation > Nuclear Power Engineering > 2024 > 45(2): 19-23

Gao Ruishuang, Liu Xiaojing, He Donghao, Pan Qingquan. Research on Burnup Calculation Method Based on Splicing Fission Matrix[J]. Nuclear Power Engineering, 2024, 45(2): 19-23. doi: 10.13832/j.jnpe.2024.02.0019

Citation:

Gao Ruishuang, Liu Xiaojing, He Donghao, Pan Qingquan. Research on Burnup Calculation Method Based on Splicing Fission Matrix[J]. Nuclear Power Engineering, 2024, 45(2): 19-23. doi: 10.13832/j.jnpe.2024.02.0019

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Research on Burnup Calculation Method Based on Splicing Fission Matrix

doi: 10.13832/j.jnpe.2024.02.0019

Shanghai Jiao Tong University, Shanghai, 201100, China

Received Date: 2023-05-29
Rev Recd Date: 2023-11-29
Publish Date: 2024-04-12

Abstract

Abstract

In order to realize efficient transport-burnup coupling calculation, a new calculation method based on splicing fission matrix theory is proposed in this paper. The combined fission matrix method enables to obtain the system fission matrix from a pre-calculated database, and then the database matrices are combined according to the actual conditions of the calculation model and the properties of the terminal area. The fission matrix database is obtained by Monte Carlo fixed source calculation, and the core calculation does not need Monte Carlo simulation, so the time-consuming critical calculation can be avoided. In this paper, the effective multiplication factor and fission source distribution of a typical two-assembly model with a burnup up to 600EFPD are obtained. The burnup-enrichment composite correction ratio can reduce the root-mean-square error of the fission source to less than 0.7%, thereby confirming the feasibility of this algorithm.
- Splicing fission matrix,
- Monte Carlo,
- Burnup calculation

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References(4)

References

[1]	WENNER M T, HAGHIGHAT A. A combined diagnostic approach for Monte Carlo source convergence identification[C]//Proceedings of the 2009 International Conference on Advances in Mathematics, Computational Methods, and Reactor Physics. New York: Saratoga Springs, 2009.
[2]	KAPLAN E L. Monte Carlo methods for equilibrium solutions in neutron multiplication: NSA-13-012787[M]. Livermore: University of California Lawrence Radiation Laboratory, 1958: 114-121.
[3]	CARNEY S, BROWN F, KIEDROWSKI B, et al. Theory and applications of the fission matrix method for continuous-energy Monte Carlo[J]. Annals of Nuclear Energy, 2014, 73: 423-431. doi: 10.1016/j.anucene.2014.07.020
[4]	WALTERS W J, ROSKOFF N J, HAGHIGHAT A. The RAPID fission matrix approach to reactor core criticality calculations[J]. Nuclear Science and Engineering, 2018, 192(1): 21-39. doi: 10.1080/00295639.2018.1497395

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