Thermal-hydraulic 0D/3D coupling in OpenFOAM: Validation and application in nuclear installations

被引:0
|
作者
Corzo, Santiago F. [1 ,2 ]
Godino, Dario M. [1 ]
Sarache Pina, Alirio J. [1 ]
Nigro, Norberto M. [1 ,2 ]
Ramajo, Damian E. [1 ,2 ]
机构
[1] UNL, CONICET, CIMEC Ctr Invest Metodos Computac, Santa Fe, Argentina
[2] UNL Univ Nacl Litoral, Santa Fe, Argentina
关键词
CFD; 3D; 0D coupling; Thermal; -hydraulics; CFD; FLUENT; CODES;
D O I
10.1016/j.net.2023.01.001
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
The nuclear safety assessment involving large transient simulations is forcing the community to develop methods for coupling thermal-hydraulics and neutronic codes and three-dimensional (3D) Computational Fluid Dynamics (CFD) codes. In this paper a set of dynamic boundary conditions are implemented in OpenFOAMCIRCLED LATIN CAPITAL LETTER R in order to apply zero-dimensional (0D) approaches coupling with 3D thermal-hydraulic simulation in a single framework. This boundary conditions are applied to model pipelines, tanks, pumps, and heat exchangers. On a first stage, four tests are perform in order to assess the implementations. The results are compared with experimental data, full 3D CFD, and system code simulations, finding a general good agreement. The semi-implicit implementation nature of these boundary conditions has shown robustness and accuracy for large time steps. Finally, an application case, consisting of a simplified open pool with a cooling external circuit is solved to remark the capability of the tool to simulate thermal hydraulic systems commonly found in nuclear installations.(c) 2023 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
引用
收藏
页码:1911 / 1923
页数:13
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