Investigation of BWR depletion calculations with SAS2H

The SAS2H sequence of the SCALE system has historically been used to characterize isotopics, radiation sources, and decay heat for spent nuclear fuel. However, there has been little work performed to investigate the viability of the SAS2H modeling limitations in application to the geometric complexities of boiling water reactor (BWR) fuel. Thus, Oak Ridge National Laboratory (ORNL) has initiated a study to investigate the use of SAS2H for calculating spent BWR fuel isotopics for criticality analyses and to assess the adequacy of SAS2H for this task. This paper discusses comparisons between one-dimensional (1-D) SAS2H and detailed two-dimensional (2-D) HELIOS assembly calculations. The work described in this paper is a small part of this larger project to assess BWR modeling for spent-fuel characterization.