Published May 15, 2008 | Version v1
Journal article

Extension of the TRANSURANUS burn-up model

  • 1. European Commission, Joint Research Centre, Institute for Transuranium Elements, P.O. Box 2340, D-76125 Karlsruhe (Germany)
  • 2. Institut de Radioprotection et de Surete Nucleaire, BP 17, F-92262 Fontenay-aux-Roses cedex (France)

Description

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

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2008.01.006

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2008.01.006;
PII
S0022-3115(08)00021-4;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
376
Journal Issue
1
Journal Page Range
p. 1-10
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.