MTR plates modeling with MAIA
- 1. DEN/DEC, CEA Cadarache, 13108 St Paul Lez Durance (France)
- 2. DEN/DSOE, CEA Saclay, 91191 Gif sur Yvette (France)
Description
MAIA is a thermo-mechanical code dedicated to the modeling of MTR fuel plates. The main physical phenomena modeled in the code are the cladding oxidation, the interaction between fuel and Al-matrix, the swelling due to fission products and the Al/fuel particles interaction. The creeping of the plate can be modeled in the mechanical calculation. MAIA has been validated on U-Mo dispersion fuel experiments such as IRIS 1 and 2 and FUTURE. The results are in rather good agreement with post-irradiation examinations. MAIA can also be used to calculate in-pile behavior of U3Si2 plates as in the SHARE experiment irradiated in the SCK/Mol BR2 reactor. The main outputs given by MAIA throughout the irradiation are temperatures, cladding oxidation thickness, interaction thickness, volume fraction of meat constituents, swelling, displacements, strains and stresses. MAIA is originally a two-dimensional code but a three-dimensional version is currently under development. (author)
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Additional details
Identifiers
Publishing Information
- Imprint Title
- 2007 international meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Abstracts and available papers presented at the meeting
- Imprint Pagination
- vp.
- Journal Page Range
- 9 p.
- Report number
- INIS-US--08N0001
Conference
- Title
- 29. international meeting on reduced enrichment for research and test reactors
- Acronym
- RERTR-2007
- Dates
- 23-27 Sep 2007
- Place
- Prague (Czech Republic)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39121056
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BR-2 REACTOR; FISSION PRODUCTS; FUEL PARTICLES; FUEL PLATES; IRRADIATION; NUCLEAR FUELS; OXIDATION; PLATES; POST-IRRADIATION EXAMINATION; SIMULATION; STRAINS; STRESSES; SWELLING; THICKNESS; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; URANIUM SILICIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHEMICAL REACTIONS; DEFORMATION; DIMENSIONS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; IRRADIATION REACTORS; ISOTOPES; MATERIALS; MATERIALS TESTING REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SILICIDES; SILICON COMPOUNDS; TANK TYPE REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs, 11 figs