Research Article

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

Figure 11

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).