Kaiyue Zeng
North Carolina State University

Abstract

The presentation will focus on uncertainty quantification of the metallic-fueled ABR-1000 SFR, which is a numerical SFR designed by Argonne National Laboratory. Uncertainties from three main categories, i.e., nuclear data, thermal-physical properties, and operational conditions, has been studied and propagated to evaluate their impacts on reactor transient safety performance. Two kinds of unprotected transient scenarios, the Unprotected Loss of Supply Station Power (ULOSSP), and Unprotected Transient Over Power (UTOP), were selected as representative transient scenarios for this study.