Fridman, E and Shwageraus, E (2010) HTGR fuel element depletion benchmark: Stage three results. In: UNSPECIFIED pp. 1180-1191..Full text not available from this repository.
Recently, a new numerical benchmark exercise for High Temperature Gas Cooled Reactor (HTGR) fuel depletion was defined. The purpose of this benchmark is to provide a comparison basis for different codes and methods applied to the burnup analysis of HTGRs. The benchmark specifications include three different models: (1) an infinite lattice of tristructural isotropic (TRISO) fuel particles, (2) an infinite lattice of fuel pebbles, and (3) a prismatic fuel including fuel and coolant channels. In this paper, we present the results of the third stage of the benchmark obtained with MCNP based depletion code BGCore and deterministic lattice code HELIOS 1.9. The depletion calculations were performed for three-dimensional model of prismatic fuel with explicitly described TRISO particles as well as for two-dimensional model, in which double heterogeneity of the TRISO particles was eliminated using reactivity equivalent physical transformation (RPT). Generally, good agreement in the results of the calculations obtained using different methods and codes was observed.
|Item Type:||Conference or Workshop Item (UNSPECIFIED)|
|Divisions:||Div A > Energy|
|Depositing User:||Unnamed user with email firstname.lastname@example.org|
|Date Deposited:||02 Sep 2016 17:22|
|Last Modified:||08 Dec 2016 06:28|