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

<table>Maximum bundle temperature, water level, effective molten pool radius, and lower plenum debris height for a scenario with depressurization and termination of emergency water injection at 4.2 hours after reactor scram (CRD flows maintained).</table>

Science and Technology of Nuclear Installations

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Figure 11

Figure 11: Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM 

Figure 11 | Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM 