In the framework of the IRIS-TUM irradiation program, several full size, flat dispersion fuel plates containing ground U(Mo) fuel kernels in an aluminum matrix, with and without addition of silicon (2.1 w%), have been irradiated in the OSIRIS reactor. After unloading, the highest burn-up fuel plates, irradiated to local maximum burn-up of 66.5 and 88.3 % 235U LEU-equivalent, showed a local maximum thickness increase of respectively 178 and 323 m, but were still intact. Microstructural analyses (optical and scanning electron microscopy) on samples from these plates were performed at the hot laboratory (LHMA) of SCK•CEN in Mol, Belgium and provides information on the behavior of ground U(Mo) fuel irradiated to high burn-up.
|Title of host publication||RERTR 2009 - 31th International Meeting on Reduced Enrichment for Research and Test Reactors|
|Place of Publication||Argonne, IL, United States|
|State||Published - Nov 2009|
|Event||31st International Meeting on Reduced Enrichment for Research and Test Reactors - Beijing|
Duration: 1 Nov 2009 → 5 Nov 2009
|Conference||31st International Meeting on Reduced Enrichment for Research and Test Reactors|
|Period||2009-11-01 → 2009-11-05|