HTGR fuel element depletion benchmark: Stage three results

Emil Fridman, Eugene Shwageraus

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

3 Scopus citations

Abstract

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.

Original languageEnglish
Title of host publicationInternational Conference on the Physics of Reactors 2010, PHYSOR 2010
PublisherAmerican Nuclear Society
Pages1180-1191
Number of pages12
ISBN (Print)9781617820014
StatePublished - 1 Jan 2010
EventInternational Conference on the Physics of Reactors 2010, PHYSOR 2010 - Pittsburgh, PA, United States
Duration: 9 May 201014 May 2010

Publication series

NameInternational Conference on the Physics of Reactors 2010, PHYSOR 2010
Volume2

Conference

ConferenceInternational Conference on the Physics of Reactors 2010, PHYSOR 2010
Country/TerritoryUnited States
CityPittsburgh, PA
Period9/05/1014/05/10

Keywords

  • BGCore
  • HELIOS 1.9
  • HTGR

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