The creep behaviour of uranium dioxide and uranium carbide has been examined in both bend and compression experiments in DIDO Materials Test Reactor. In UO 2 no significant variation in creep rate with dose and temperature occured above ~10 25 fissions m −3 between 450°C and 1230°C, the high strain rates measured in compression at low doses being largely attributable to pore sintering. Both a linear rating and stress dependence were observed up to 40 MNm −2 and creep rates were found to be independent of grain size. At higher doses ( >6 × 10 26 fissions m −3 ) transient strains were incurred on varying stress and temperature due to the development of grain boundary gas bubbles. This also resulted in a six fold increase in the radiation creep constant between 6 × 10 26 and 1.2 × 10 27 fissions m −3. A similar pattern of behaviour with respect to rating and stress was observed in hyperstoichiometric UC between 450 and 800°C up to 1 × 10 27 fissions m −3. However the nominally steady state creep rate was a factor 8 lower than in UO 2 irradiated under the same conditions. The experimental results also suggest that the primary creep contribution to the initial strain in compression is much higher than in UO 2. There was no evidence of either transient strain on changing stress or of an increasing creep rate at high doses. The experimental observations are reported and discussed in relation to models for irradiation induced low temperature creep in ceramic fuels.