Microstructural analysis of ground U(Mo) fuel with and without Si in the matrix, irradiated to high burn-up

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Abstract

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.

Details

Original languageEnglish
Title of host publicationRERTR 2009 - 31th International Meeting on Reduced Enrichment for Research and Test Reactors
Place of PublicationArgonne, IL, United States
Publication statusPublished - Nov 2009
Event31st International Meeting on Reduced Enrichment for Research and Test Reactors - Beijing, China
Duration: 1 Nov 20095 Nov 2009

Conference

Conference31st International Meeting on Reduced Enrichment for Research and Test Reactors
Country/TerritoryChina
CityBeijing
Period2009-11-012009-11-05

Keywords

  • MTR fuel, ground UMo

ID: 214379