Simulation of Irradiation History in Combined Annular Multi-Tube Fuel Element of BR2

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Abstract

The impact of strong non-uniformity of neutron fluxes in the Belgian High Flux Materials Testing Reactor BR2 on the spatial distributions of the fuel burn-up and heat fluxes in complex annular fuel elements and on the irradiation conditions in various experiments performed in BR2 is discussed in the paper. The purpose was to develop a calculation approach for predicting 3-D fuel burn-up in multi-tube annular fuel elements. In the method presented here the spatial 3-D distribution of the fuel burn-up in plates of the multi-tube fuel element is calculated using the 3-D distributions of the power peaking factor calculated in the registration mesh using the MCNP code linked with the burn-up module ORIGEN-S in the SCALE code. The presented approach permits to predict effectively the dependence of the fuel burn-up distribution in the fuel plates versus their position inside the core and versus their azimuth orientation.

Details

Original languageEnglish
Title of host publicationEns rrfm 2006 transactions
Place of PublicationBruxelles, Belgium
Pages300-304
Publication statusPublished - 30 Apr 2006
EventRRFM 2006 - 10th ENS Topical Meeting on Research Reactor Fuel Management - European Nuclear Society, Sofia, Bulgaria
Duration: 30 Apr 20063 May 2006

Conference

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

Keywords

  • BR2 Material Testing Reactor, simulation, 3-D fuel burn-up, fuel lement

ID: 190438