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.
Original language | English |
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Title of host publication | Ens rrfm 2006 transactions |
Place of Publication | Bruxelles, Belgium |
Pages | 300-304 |
State | Published - 30 Apr 2006 |
Event | 2006 - RRFM - Research Reactor Fuel Management: 10th ENS Topical Meeting - European Nuclear Society, Sofia Duration: 30 Apr 2006 → 3 May 2006 |
Conference
Conference | 2006 - RRFM - Research Reactor Fuel Management |
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Country/Territory | Bulgaria |
City | Sofia |
Period | 2006-04-30 → 2006-05-03 |