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.2008.01.006Additional 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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40002086
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- BURNUP; COMPUTER CODES; CROSS SECTIONS; ELECTRON MICROPROBE ANALYSIS; ION MICROPROBE ANALYSIS; IRRADIATION; MASS SPECTROSCOPY; MIXED OXIDE FUELS; MONTE CARLO METHOD; PLUTONIUM 238; POST-IRRADIATION EXAMINATION; POWER DENSITY; RADIOCHEMISTRY; URANIUM DIOXIDE; VALIDATION; VERIFICATION
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; CHALCOGENIDES; CHEMICAL ANALYSIS; CHEMISTRY; ENERGY SOURCES; EVEN-EVEN NUCLEI; FUELS; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; ISOTOPES; MATERIALS; MICROANALYSIS; NONDESTRUCTIVE ANALYSIS; NUCLEAR FUELS; NUCLEI; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM ISOTOPES; RADIOISOTOPES; REACTOR MATERIALS; SILICON 32 DECAY RADIOISOTOPES; SOLID FUELS; SPECTROSCOPY; SPONTANEOUS FISSION RADIOISOTOPES; TESTING; URANIUM COMPOUNDS; URANIUM OXIDES; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.