MTR plates modeling with MAIA
- DEN/DEC, CEA Cadarache, 13108 St Paul Lez Durance (France)
- DEN/DSOE, CEA Saclay, 91191 Gif sur Yvette (France)
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 U{sub 3}Si{sub 2} 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)
- Research Organization:
- Argonne National Laboratory, Nuclear Engineering Division, RERTR Department, Argonne, IL (United States); Czech Technical University, Prague (Czech Republic)
- OSTI ID:
- 21113518
- Report Number(s):
- INIS-US-08N0001; TRN: US08N0040121056
- Resource Relation:
- Conference: RERTR-2007: 29. international meeting on reduced enrichment for research and test reactors, Prague (Czech Republic), 23-27 Sep 2007; Other Information: Country of input: International Atomic Energy Agency (IAEA); 9 refs, 11 figs; Related Information: In: 2007 international meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Abstracts and available papers presented at the meeting, vp.
- Country of Publication:
- United States
- Language:
- English
Similar Records
Temperature Effects on Interdiffusion of Al and U-Mo under Irradiation
Modeling of high-density U-Mo dispersion fuel plate performance.
Related Subjects
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