K. Nogita et K. Une, EFFECT OF GRAIN-SIZE ON MICROSTRUCTURAL CHANGE AND DAMAGE RECOVERY INUO2 FUELS IRRADIATED TO 23-GWD T/, Journal of Nuclear Science and Technology, 31(9), 1994, pp. 929-936
The effect of grain size on microstructural change and damage recovery
in UO2 fuels was studied by X-ray diffractometry (XRD) and transmissi
on electron microscopy (TEM). The as-irradiated lattice parameter of t
he standard fuel (grain size: 16 mu m) was larger than that of the lar
ge-grained fuel (43 mu m), indicating a larger number of fission-induc
ed point defects in the lattice of the former fuel. This tendency was
in contrast to previously reported results for low burnup fuels below
1 GWd/t. The lattice dilation in the present high burnup fuels was mai
nly due to the accumulation of vacancies. The lattice parameter of bot
h fuels began to recover around an irradiation temperature of 450 simi
lar to 650 degrees C, and both had a complete recovery at 850 degrees
C. On annealing at high temperatures of 1,450 similar to 1,800 degrees
C, the bubble diameter in the standard fuel was larger than that in t
he large-grained fuel. This indicated that vacancy diffusion from the
grain boundaries plays an important role during bubble coarsening at h
igh temperatures.