INVESTIGADORES
CORZO Santiago Francisco
congresos y reuniones científicas
Título:
PRESSURISED HEAVY WATER REACTOR (PHWR) COOLANT CHANNEL SIMULATION OF THE ATUCHA II NUCLEAR POWER PLANT
Autor/es:
SANTIAGO CORZO; RAMAJO DAMIAN; NORBERTO NIGRO; SANTIAGO MÁRQUEZ DAMIÁN
Lugar:
Rosario
Reunión:
Congreso; Encuentro Nacional de Investigadores de Elementos Finitos; 2011
Institución organizadora:
Asociación Argentina de Mecánica Computacional
Resumen:
The coolant channel components and fuel assembly of the Atucha II PHWR nuclear power plant were simulated. 3D CFD simulation was used for estimating the pressure drop and the flow fieldaround detailed models of one of the spacers and the channel outlet throttle port. Results allow for adeep understanding of the channel flow and the frictional and form pressure losses inside the channel.Results were compared with experimental data for a simplified spacer and correlations for the pressuredrop from literature were also implemented obtaining good agreement.