Reactivity Initiated Accident for the Canadian SCWR

Abstract

A full core model of the Canadian Supercritical Water-cooled Reactor was built in PARCS and RELAP/SCDAPSIM/MOD4. By using external scripts to exchange data, a coupled steady-state was calculated before carrying out a reactivity initiated accident. A control blade was ejected from the core to simulate the transient at beginning of cycle. The power, cladding temperature and fuel centerline temperature were evaluated throughout the transient for three different scenarios. The safety limits are largely respected when the reactor scram works. However, if the reactor scram isn't activated, it would result in partial fuel melting around the ejected control rod.