High enriched, low density UAlx dispersion fuel has been successfully used in research and test reactors for several decades. However, publications of detailed post irradiation examinations are limited. In this paper, a sample of a high enriched uranium fuel plate (90% 235U enriched UAlx fuel dispersed in an Al matrix), irradiated to a burn-up of 21% 235U, is investigated with transmission electron microscopy. It is observed that the fuel became completely amorphous during irradiation. The Al matrix is found to remain crystalline and contains a large number of radiation induced defects. Neither in the fuel nor in the Al matrix, fission gas bubbles were observed.
|Title of host publication||Transactions RRFM|
|Place of Publication||Brussels, Belgium|
|State||Published - Mar 2010|
|Event||2010 - RRFM - 14th ENS Topical Meeting on Research Reactor Fuel Management - European Nuclear Society, Marrakech|
Duration: 21 Mar 2010 → 25 Mar 2010
|Conference||2010 - RRFM - 14th ENS Topical Meeting on Research Reactor Fuel Management|
|Period||2010-03-21 → 2010-03-25|