Artículo
Thermal-hydraulic 0D/3D coupling in OpenFOAM: Validation and application in nuclear installations
Corzo, Santiago Francisco
; Godino, Dario Martin
; Sarache Piña, Alirio Johan; Nigro, Norberto Marcelo
; Ramajo, Damian Enrique
Fecha de publicación:
01/2023
Editorial:
Korean Nuclear Soc
Revista:
Nuclear Engineering And Technology
ISSN:
1738-5733
Idioma:
Inglés
Tipo de recurso:
Artículo publicado
Clasificación temática:
Resumen
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Ⓡ 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.
Palabras clave:
3D/0D COUPLING
,
CFD
,
THERMAL-HYDRAULICS
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Articulos(CIMEC)
Articulos de CENTRO DE INVESTIGACION DE METODOS COMPUTACIONALES
Articulos de CENTRO DE INVESTIGACION DE METODOS COMPUTACIONALES
Citación
Corzo, Santiago Francisco; Godino, Dario Martin; Sarache Piña, Alirio Johan; Nigro, Norberto Marcelo; Ramajo, Damian Enrique; Thermal-hydraulic 0D/3D coupling in OpenFOAM: Validation and application in nuclear installations; Korean Nuclear Soc; Nuclear Engineering And Technology; 55; 5; 1-2023; 1911-1923
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