K. Une et al., CORROSION BEHAVIOR OF UNIRRADIATED OXIDE FUEL PELLETS IN HIGH-TEMPERATURE WATER, Journal of nuclear materials, 227(1-2), 1995, pp. 32-39
Citations number
22
Categorie Soggetti
Nuclear Sciences & Tecnology","Mining & Mineral Processing","Material Science
In order to elucidate fuel wash-out behavior after the degraded second
ary failure of LWR fuel rods, corrosion experiments in high temperatur
e and high pressure water of 340 degrees C and 15 MPa were conducted f
or unirradiated oxide fuels, two each of undoped UO2 with two differen
t grain sizes, 5 wt% Gd2O3- and 10 wt% Gd2O3-doped UO2. In degassed wa
ter of dissolved oxygen concentration (DO) equal to 10 ppb, no corrosi
on or oxidation was found, but the corrosion became noticeable above D
O = 3 ppm. Pellet oxidation proceeded with U4O9 formation along the gr
ain boundaries and subsequent U4O9 growth into enveloped UO2 grains. C
onsequently, the grain boundary penetration rate in the oxygenated wat
er followed a diffusion-controlled parabolic law. Mismatch in the O/U
ratio between the grain boundaries and interiors led to weakened bound
aries, which is the cause of fuel wash-out in heavily degraded fuel ro
ds. Both increases of grain size and Gd2O3 content were found to provi
de improved corrosion resistance.