Abstract
An analysis of design basis accidents has been completed and an analysis of the consequences of postulated beyond design basis accidents is now being performed on the IR-8 reactor. A computational analysis of the consequences of a beyond design basis accident with rupture of the delivery and intake piping in the first cooling loop of the reactor is being done. Preliminary assessments were initially made using the one-dimensional code BEREZA. In order to confirm the results and determine the time to onset of core drying, a three-dimensional thermohydraulic model of IR-8 was developed and constructed, and a computational analysis of this accident was performed using the systems code ATHLET.
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