Observation on the irradiation behavior of U-Mo alloy dispersion fuel

摘要

Initial results from the postirradiation examination of high-density dispersionfuel test RERTR-3 are discussed. The U-MO alloy fuels in this test were irradiated to 40% U-235 burnup at temperature ranging from 140 degr.C to 240 degr.C. Temperature has a significant effect on overall swelling of the test plates. The magnitude of the swelling appears acceptable and no unstable irradiation behavior is evident.