Thermal analysis of moxt fuel during vessel drain event

摘要

A thermal analysis was performed at the Idaho National Engineering and Environmental laboratory on mixed uranium and plutonium oxide (MOX) fuel to determine whether overheating would occur during in-vessel testing in the Advancd Test Reactor (ATR) with the vessel drained. The results of the analysis indicate that overheating of the fuel capsules or surrounding materials will not occur when the ART vessel is drained.