Implementation of high-fidelity neutronics and thermal-hydraulic coupling calculations in HNET

Yan-Ling Zhu; Xing-Wu Chen; Chen Hao; Yi-Zhen Wang; Yun-Lin Xu

doi:10.1007/s41365-022-01120-z

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Implementation of high-fidelity neutronics and thermal-hydraulic coupling calculations in HNET

NUCLEAR ENERGY SCIENCE AND ENGINEERING | Updated：2022-12-16

- Implementation of high-fidelity neutronics and thermal-hydraulic coupling calculations in HNET
- Implementation of high-fidelity neutronics and thermal-hydraulic coupling calculations in HNET
- 核技术（英文版） 2022年33卷第11期文章编号：146
- Affiliations：
  
  1.Fundamental Science On Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin 150001, China
  2.Institute of Nuclear and New Energy Technology (INET), Tsinghua University, Beijing 100084, China
  3.Purdue University, West Lafayette, IN 47907, USA
- Author bio：
  
  * haochen.heu@163.com
- Funds：
  
  China Postdoctoral Science Foundation(2021M703045);National Natural Science Foundation of China(12075067);National Key R&D Program of China(2018YFE0180900)
- DOI：10.1007/s41365-022-01120-z
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Implementation of high-fidelity neutronics and thermal-hydraulic coupling calculations in HNET[J]. 核技术（英文版）, 2022,33(11):146

Yan-Ling Zhu, Xing-Wu Chen, Chen Hao, et al. Implementation of high-fidelity neutronics and thermal-hydraulic coupling calculations in HNET[J]. Nuclear Science and Techniques, 2022,33(11):146
Implementation of high-fidelity neutronics and thermal-hydraulic coupling calculations in HNET[J]. 核技术（英文版）, 2022,33(11):146 DOI： 10.1007/s41365-022-01120-z.

Yan-Ling Zhu, Xing-Wu Chen, Chen Hao, et al. Implementation of high-fidelity neutronics and thermal-hydraulic coupling calculations in HNET[J]. Nuclear Science and Techniques, 2022,33(11):146 DOI： 10.1007/s41365-022-01120-z.

摘要

Abstract

To perform nuclear reactor simulations in a more realistic manner, the coupling scheme between neutronics and thermal-hydraulics was implemented in the HNET program for both steady-state and transient conditions. For simplicity, efficiency, and robustness, the matrix-free Newton/Krylov (MFNK) method was applied to the steady-state coupling calculation. In addition, the optimal perturbation size was adopted to further improve the convergence behavior of the MFNK. For the transient coupling simulation, the operator splitting method with a staggered time mesh was utilized to balance the computational cost and accuracy. Finally, VERA Problem 6 with power and boron perturbation and the NEACRP transient benchmark were simulated for analysis. The numerical results show that the MFNK method can outperform Picard iteration in terms of both efficiency and robustness for a wide range of problems. Furthermore, the reasonable agreement between the simulation results and the reference results for the NEACRP transient benchmark verifies the capability of predicting the behavior of the nuclear reactor.

关键词

Keywords

Coupling calculationHigh-fidelity neutronicsThermal-hydraulicsMatrix-free Newton/Krylov methodTransient simulation

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