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

<table>Maximum bundle temperature and water level for high-pressure scenarios for scenarios where all of the emergency water injection was terminated at a time varying from 0 hours to 70 hours after scram.</table>

Science and Technology of Nuclear Installations

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Figure 26

Figure 26: Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM 

Figure 26 | Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM 