Abstracts and Available Papers Presented at the 1999 International RERTR Meeting
INITIAL ASSESMENT OF RADIATION BEHAVIOR OF
G. L. Hofman, M.
K. Meyer, J. L. SNELGROVE
M. L. Dietz, R. V. STRAIN, and K-H. KIM*
South Cass Avenue
Illinois 60439-4815 U.S.A.
Atomic Energy Research Institute
Dukjin-Dong, Yusong-Ku, Taejon, 305-353, Korea
Results from the postirradiation examinations of
microplates irradiated in the RERTR-1 and -2 experiments in the ATR
have shown several binary and ternary U-Mo alloys to be promising candidates
for use in aluminum-based dispersion fuels with uranium densities up to 8 to
9 g/cm3. Ternary alloys
of uranium, niobium, and zirconium performed poorly, however, both in terms of
fuel/matrix reaction and fission-gas-bubble behavior, and have been dropped
from further study. Since irradiation
temperatures achieved in the present experiments (approximately 70°C) are
considerably lower than might be experienced in a high-performance reactor, a
new experiment is being planned with beginning-of-cycle temperatures greater
than 200°C in 8-g U/cm3 fuel.