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

SANTIAGO F. CORZO; DARIO M. GODINO; JOHAN SARACHE PIÑA; NORBERTO M. NIGRO; DAMIAN E. RAMAJO

NUCLEAR ENGINEERING AND TECHNOLOGY

KOREAN NUCLEAR SOC

Lugar: Seúl ; Año: 2023

1738-5733

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 OpenFOAM$^{circledR}$ 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.