INVESTIGADORES
NIGRO Norberto Marcelo
artículos
Título:
CFD model of a moderator tank for a pressure vessel PHWR nuclear power plant
Autor/es:
CORZO SANTIAGO; RAMAJO, DAMIAN; NIGRO NORBERTO
Revista:
APPLIED THERMAL ENGINEERING
Editorial:
PERGAMON-ELSEVIER SCIENCE LTD
Referencias:
Lugar: Amsterdam; Año: 2016 vol. 107 p. 975 - 986
ISSN:
1359-4311
Resumen:
The CFD thermal hydraulic simulation of a Pressurized Heavy Water REactor (PHWR) moderator tank was performed. Heatingwas achieved by considering two heat sources, conduction/convection through the coolant channels and neutron thermalization.For the first method, a suitable 2D model for coupling the 3D with a 1D code to solve the in-channel coolant was implemented. Forthermalization, a volumetric heat source was estimated. Due to the relevance of natural and forced convection in the heat transfer,the Boussinesq approach was assessed for high Rayleigh number flow before it was used to model the moderator tank. The resultsclarified the complex flow behaviour and the temperature field. It was noted that the thermal power transferred from the coolantwas not directly related to the fission power distribution but to the coolant temperature profile (nearly the same for all channels)and the non-homogeneous moderator temperature. The former profile was as expected for high-Rayleigh natural convection flows.
