Modeling of Excess Reactivity Transients in the Sealer Lead-Cooled Reactor

Abstract

Modeling of the two hypothetical excess reactivity accidents was performed for the SEALER small lead-cooled reactor concept. The reactivity transient due to the leakage of steam from a steam generator to the core was analyzed using the SERPENT code. The ejection of the control rod assembly accident was modeled with the DONJON and DRAGON codes. The results of these two studies will be presented.