October 2010

Conference Paper

SCALE Monte Carlo Eigenvalue Methods and New Advancements

By:
Goluoglu, Sedat ; Leppanen, Jaakko; Petrie Jr, Lester M; Dunn, Michael E
Publication Date:
October 2010
Conference Name:
Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC 2010)
Conference Location:
Tokyo, Japan

Abstract

SCALE code system is developed and maintained by Oak Ridge National Laboratory to perform criticality safety, reactor analysis, radiation shielding, and spent fuel characterization for nuclear facilities and transportation/storage package designs. SCALE is a modular code system that includes several codes which use either Monte Carlo or discrete ordinates solution methodologies for solving relevant neutral particle transport equations. This paper describes some of the key capabilities of the Monte Carlo criticality safety codes within the SCALE code system.