Containment Response during Degraded Core Accidents Initiated by Transients and Small Break LOCA in the Zion/Indian Point Reactor Plants

摘要

An assessment has been made of hypothetical degraded core accidents initiated by transients and small break LOCA in the Zion (Units 1 and 2) and Indian Point (Units 2 and 3) reactor plants. In particular, the containment building pressure and temperature histories resulting from steam pressurization and hydrogen burning were determined for a range of potential accident sequences. These histories were determined by use of the MARCH (Meltdown Accident Response Characteristics) Code. Because of uncertainties in MARCH and also because of the uncertainties associated with the fundamental characteristics of hydrogen combustion in large volumes (i.e., reactor containments, especially during accident conditions), the containment building loading contribution from H2 combustion is correspondingly uncertain.