Research on Predictor-Corrector Method Based on Prediction of Reaction Rates

Wen Xingjian; Tian Chao; Tang Songqian; Zhai Zian; Miao Jianxin; Cao Liangzhi; Liu Zhouyu

doi:10.13832/j.jnpe.2022.S2.0213

Volume 43 Issue S2

Dec. 2022

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Article Navigation > Nuclear Power Engineering > 2022 > 43(S2): 213-219

Wen Xingjian, Tian Chao, Tang Songqian, Zhai Zian, Miao Jianxin, Cao Liangzhi, Liu Zhouyu. Research on Predictor-Corrector Method Based on Prediction of Reaction Rates[J]. Nuclear Power Engineering, 2022, 43(S2): 213-219. doi: 10.13832/j.jnpe.2022.S2.0213

Citation:

Wen Xingjian, Tian Chao, Tang Songqian, Zhai Zian, Miao Jianxin, Cao Liangzhi, Liu Zhouyu. Research on Predictor-Corrector Method Based on Prediction of Reaction Rates[J]. Nuclear Power Engineering, 2022, 43(S2): 213-219. doi: 10.13832/j.jnpe.2022.S2.0213

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Research on Predictor-Corrector Method Based on Prediction of Reaction Rates

doi: 10.13832/j.jnpe.2022.S2.0213

1.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
2.
Xi’an Jiaotong University, Xi’an, 710049, China

Received Date: 2022-07-20
Rev Recd Date: 2022-09-27
Publish Date: 2022-12-31

Abstract

Abstract

Traditional predictor-corrector method revises the burnup calculation results by means of the nuclide inventory of the average predictor step and the corrector step, two neutronics calculations are required at each burn-up step. In order to reduce the time of transport-burnup coupling calculation, the traditional predictor-corrector method is analyzed in this work and the predictor-corrector method based on the prediction of the reaction rates is proposed in this work. This method makes use of the characteristics of the smooth variation of the multi-group neutron spectrum difference between the predictor step and the correction step with burnup in the traditional predictor-corrector method, Lagrangian interpolation method is used to describe the variation characteristics of regional and burnup time related neutron spectrum deviation with burnup time, and analytical interpolation formula is obtained. Under the condition that the calculation times of the predictor steps remain unchanged, the reaction rate of some corrector steps is predicted directly so as to avoid the neutronics calculation of such corrector steps. This study takes the traditional predictor-corrector method as reference, and verifies the proposed predictor-corrector method based on reaction rate prediction through VERA and JAEA burnup benchmark tasks. The numerical results show that the predictor-corrector method based on reaction rate prediction can reduce the neutronics calculation time by about 20% on the basis of ensuring the rod power distribution and the accuracy of the main nuclide components. Therefore, the predictor-corrector method based on reaction rate prediction established in this study can be used for efficient transport-burnup coupling calculation.
- Transport-burnup coupling calculation,
- Predictor-corrector method,
- Burnup benchmark task

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References(8)

References

[1]	SCHLAPPER G A. Methods of steady-state reactor physics in nuclear design[J]. Nuclear Technology, 1984, 65(2): 358-358. doi: 10.13182/NT84-A33423
[2]	GERRITY III T P. MCODE-3: Time-dependent depletion isotopics with MCNP-5 and SCALE-6.1[D]. Cambridge, Massachusetts: Massachusetts Institute of Technology, 2012.
[3]	ISOTALO A E, AARNIO P A. Higher order methods for burnup calculations with Bateman solutions[J]. Annals of Nuclear Energy, 2011, 38(9): 1987-1995. doi: 10.1016/j.anucene.2011.04.022
[4]	王芷妍. 基于改进半预估修正的蒙特卡罗输运—燃耗耦合策略研究[D]. 合肥: 中国科学技术大学, 2018.
[5]	GODFREY A. VERA core physics benchmark progression problem specifications, revision 4, CASL technical report: CASL-U-2012-0131-004[R]. Oak Ridge, Tennessee: Oak Ridge National Laboratory, 2014.
[6]	KIM K S. Specification for the VERA depletion benchmark suite: CASL-X-2015-1014-000[R]. Oak Ridge, Tennessee: Oak Ridge National Laboratory, 2015.
[7]	CHEN J, LIU Z Y, ZHAO C, et al. A new high-fidelity neutronics code NECP-X[J]. Annals of Nuclear Energy, 2018, 116: 417-428. doi: 10.1016/j.anucene.2018.02.049
[8]	YAMAMOTO A, IKEHARA T, ITO T, et al. Benchmark problem suite for reactor physics study of LWR next generation fuels[J]. Journal of Nuclear Science and Technology, 2002, 39(8): 900-912. doi: 10.1080/18811248.2002.9715275