CIMEC   24726
CENTRO DE INVESTIGACION DE METODOS COMPUTACIONALES
Unidad Ejecutora - UE
congresos y reuniones científicas
Título:
Thermal-Hydraulic simulation of loss of forced circulation in the TRIGA MARK I IPR-R1 reactor
Autor/es:
SANTIAGO CORZO; CLAUBIA PEREIRA; PATRÍCIA AMÉLIA L. REIS; NIGRO, NORBERTO; DARIO GODINO; ANTONELLA COSTA ; DAMIAN RAMAJO
Lugar:
Santos
Reunión:
Congreso; International Nuclear Atlantic Conference 2019; 2019
Institución organizadora:
Brazilian Nuclear Energy Association
Resumen:
The loss of forced circulation (LFC) in the nuclear training reactor TRIGA Mark I-IPR-R1 was simulated by Computational Fluid Dynamics (CFD). The objective was to assess the capability of the reactor for cooling by natural convection at operational heat power. The geometry of the pool and core was carefully represented, and the fuel power distribution was properly defined in the model. The fluid was solved by using an incompressible buoyant approach with the buoyantBoussinesqPimpleFoam solver of OpenFOAM R. First, the forced convection flow under normal operation was established, and later the shutdown of the external cooling system was achieved. The flow pattern in the pool, and especially around the core, was analyzed in depth to find low-velocity zones and hot temperature spots over the fuel rods. The model allowed to determine the rate of increase of temperature, finding agreement with experimental data and simulations performed with RELAP.