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

被引:3
|
作者
Zhu, Yan-Ling [1 ]
Chen, Xing-Wu [1 ]
Hao, Chen [1 ]
Wang, Yi-Zhen [2 ]
Xu, Yun-Lin [3 ]
机构
[1] Harbin Engn Univ, Fundamental Sci Nucl Safety & Simulat Technol Lab, Harbin 150001, Peoples R China
[2] Tsinghua Univ, Inst Nucl & New Energy Technol INET, Beijing 100084, Peoples R China
[3] Purdue Univ, W Lafayette, IN 47907 USA
基金
国家重点研发计划; 中国国家自然科学基金; 中国博士后科学基金;
关键词
Coupling calculation; High-fidelity neutronics; Thermal-hydraulics; Matrix-free Newton; Krylov method; Transient simulation; SIMULATION;
D O I
10.1007/s41365-022-01120-z
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
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.
引用
收藏
页数:13
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