Title: Extension of the TRANSURANUS Burn-up Model
Authors: SCHUBERT ARNDTVAN UFFELEN PAULVAN DE LAAR JACQUESWALKER CLIVEHAECK W.
Citation: JOURNAL OF NUCLEAR MATERIALS vol. 376 p. 1-10
Publisher: ELSEVIER SCIENCE BV
Publication Year: 2008
JRC Publication N°: JRC45286
ISSN: 0022-3115
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC45286
DOI: 10.1016/j.jnucmat.2008.01.006
Type: Articles in Journals
Abstract: The validation range of the model in the TRANSURANUS fuel performance code for calculating the radial power density and burnup 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.
JRC Institute:Institute for Transuranium Elements

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