A numerical analysis of the thermal stratification in the upper plenum of the MONJU fast breeder reactor was performed. Calculations were performed for a 1/6 simplified model of the MONJU reactor using the commercial code, CFX-13. To better resolve the geometrically complex upper core structure of the MONJU reactor, the porous media approach was adopted for the simulation. First, a steady state solution was obtained, and the transient solutions were then obtained for the turbine trip test conducted in December 1995. The time dependent inlet conditions for the mass flow rate and temperature were provided by JAEA. Good agreement with the experimental data was observed for the steady state solution. The numerical solution of the transient analysis shows the formation of thermal stratification within the upper plenum of the reactor vessel during the turbine trip test. The temporal variations of temperature were predicted accurately by the present method in the initial rapid coastdown period (∼300 seconds). However, the transient numerical solutions show a faster thermal mixing than that observed in the experiment after the initial coastdown period. A near homogenization of the temperature field in the upper plenum is predicted after about 900 seconds, which is a much shorter-term thermal stratification than the experimental data indicates.
Numerical Simulation of Thermal Stratification in the Upper Plenum of Fast Reactor
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Choi, S, & Lee, T. "Numerical Simulation of Thermal Stratification in the Upper Plenum of Fast Reactor." Proceedings of the ASME 2013 Pressure Vessels and Piping Conference. Volume 4: Fluid-Structure Interaction. Paris, France. July 14–18, 2013. V004T04A075. ASME. https://doi.org/10.1115/PVP2013-97833
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