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

<table>Temperatures in lower plenum wall and debris after melt relocation 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

fig18

Figure 18

Figure 18: Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM 

Figure 18 | Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM 