Title of article
Extension of the TRANSURANUS burn-up model
Author/Authors
Schubert، نويسنده , , A. and Van Uffelen، نويسنده , , P. and van de Laar، نويسنده , , J. and Walker، نويسنده , , C.T. and Haeck، نويسنده , , W.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2008
Pages
10
From page
1
To page
10
Abstract
The validation range of the model in the TRANSURANUS fuel performance code for calculating the radial power density and burn-up in UO2 fuel has been extended from 64 MWd/kgHM up to 102 MWd/kgHM, thereby improving also its precision. In addition, the first verification of calculations with post-irradiation examination data is reported for LWR-MOX fuel with a rod average burn-up up to 45 MWd/kgHM. The extension covers the inclusion of new isotopes in order to account for the production of 238Pu. The corresponding one-group cross-sections used in the equations rely on results obtained with ALEPH, a new Monte Carlo burn-up code. The experimental verification is based on electron probe microanalysis (EPMA) and on secondary ion mass spectrometry (SIMS) as well as radiochemical data of fuel irradiated in commercial power plants. The deviations are quantified in terms of frequency distributions of the relative errors. The relative errors on the burn-up distributions in both fuel types remain below 12%, corresponding to the experimental scatter.
Journal title
Journal of Nuclear Materials
Serial Year
2008
Journal title
Journal of Nuclear Materials
Record number
1367181
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