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
- Nuclear Science and Techniques Vol. 33, Issue 11, Article number: 146(2022)
- 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：
- DOI：10.1007/s41365-022-01120-z
  CLC：
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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 33(11):146(2022)
DOI：

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 33(11):146(2022) 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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