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

<table>Laguna Verde: reactor pressure vessel and control rod drive (CRD) cooling system detailed nodalization.</table>

Science and Technology of Nuclear Installations

Figure 6: Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM 