3-D Fuel Burn Up Modeling with MCNP&ORIGEN-S

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Abstract

The purpose of this paper is to highlight the importance of the applied detailed 3-D fuel modeling in the highly heterogeneous, high flux MTR reactor BR2 for the accurate assessment of the reactor safety characteristics during the reactor operation. The combined MCNP&ORIGEN-S full-scale 3-D heterogeneous geometry model with detailed 3-D isotopic fuel profile in the whole core is used for the neutronics calculations. The effects of three burn up profiles on the reactivity variations are investigated: axial burn up profile in a fuel plate, radial in a fuel assembly and azimuth depletion profile in each axial segment of the annular fuel plates. The uncertainties in the maximum values of the heat flux due to different orientations of the fuel element in the core are estimated.

Details

Original languageEnglish
Title of host publicationENS RRFM 2006: 10th International Meeting Research Reactor Fuel Management
Place of PublicationBrussels, Belgium
Pages253-257
Publication statusPublished - 18 Apr 2006
EventRRFM 2006 - 10th ENS Topical Meeting on Research Reactor Fuel Management - European Nuclear Society, Sofia, Bulgaria
Duration: 30 Apr 20063 May 2006

Publication series

NameResearch Reactor Fuel Management

Conference

ConferenceRRFM 2006 - 10th ENS Topical Meeting on Research Reactor Fuel Management
CountryBulgaria
CitySofia
Period2006-04-302006-05-03

Keywords

  • fuel modeling, mcnp, origen

ID: 226295