Measurement of the Heat Load Imposed on the Reactor Vessel Depending on the Crust Layer in a Severe Accident

In an In-Vessel Retention and External Reactor Vessel Cooling (IVR-ERVC) situation, the molten corium in the oxide pool may be solidified and form a crust layer along the oxide layer boundary. This changes thermal boundary and geometrical condition of the oxide pool which may affect natural convection heat transfer of the oxide pool [1]. However, only a few studies [2,3] were performed regarding the crust layer. We measured the mean Nu imposed to reactor vessel and local heat flux and comparative analyses were performed between the crust free and crust conditions with a few different thicknesses depending on the decay heat.

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