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Ta for this. I'm trying to understand how the loss of containment / protection differs between reactor 1 and reactor 2.  There was an explosion at reactor 1 too, wasn't there? So did that explosion not breach the drywell, whereas reactor 2's drywell is breached? Do the differences in pressure readings tell us anything about the intactness of the innermost reactor vessels?
by LondonAnalytics (Andrew Smith) on Thu Mar 31st, 2011 at 02:57:53 AM EST
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