Numerical Simulations of Upper Plenum Thermalhydraulics of Monju Reactor Vessel Using High Resolution Mesh Models
NURETH-14 - 2011 September 25-30

Presented at:
2011 September 25-30
Toronto, Canada
Session Title:
O10-1 IAEA Session on Benchmark Analyses of Sodium Natural Convection in the Upper Plenum of the Mon

Hiroaki Ohira (Japan Atomic Energy Agency)
Kei Honda (Japan Atomic Energy Agency)
Masutake Sotsu (Japan Atomic Energy Agency)


In order to evaluate the upper plenum thermal-hydraulics of the Monju reactor vessel, we have performed detail calculations under the 40% rated power operational condition using high resolution mesh models by a commercial FVM code, FrontFlow/Red. In this study, we applied a high resolution meshes around the flow holes (FHs) on the inner barrel.We mainly made clear that the thermal-hydraulics did not change largely since the flow rates through the FHs were small enough to the total coolant flow rate but were affected largely in case without FHs on the honeycomb structure.

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