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

<table>Horizontal metallographic cross-sections for CORA-18 showing destruction of control blade and channel box at temperatures between 1500–1700 K.</table>

Science and Technology of Nuclear Installations

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Figure 2

Figure 2: Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM 