Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM

<table>Horizontal metallographic cross-sections from PBF-SFD-ST showing blockage formation after {U-Zr}-O<sub>2</sub> melting and relocation.</table>

Science and Technology of Nuclear Installations

Figure 3: Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM 