Article ID Journal Published Year Pages File Type
4925393 Nuclear Engineering and Design 2017 12 Pages PDF
Abstract
The model for U-Zr-O molten pool oxidation under non-equilibrium conditions is further extended to consideration of the vessel steel corrosion by the oxidized corium melt. The heat and mass exchange processes between various interaction layers, including U-Zr-O melt, (Zr,U)O2−x crust, FeO corrosion layer and vessel steel wall, are considered taking into account a steep temperature gradient in the layered system. The new model is numerically realized and applied to consideration of typical temperature scenarios of METCOR tests on corrosion of vessel steel during its interaction with oxidized molten corium.
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