Annual Progress Report on Fuel Element Development for Fy 1963

Irradiation and Postirradiation Annealing of Some Aluminum-Base Fuels

“…The data at 100°C were obtained from Ref. 21, which described tests of samples having 0.020-in.-thick fuel cores clad with 0.015 in. of various aluminum alloy claddings.…”

“…(9-11) Themechanism by which it occurs, however, is not thoroughly understood.! 12) The fact that shrinkage occurred suggests that either lattice diffusion or plastic flow is an important mechanism 21 involved m the sintering process. The lattice diffusion model, discussed by Burke,(13) seems the most reasonable of the two.…”

Results of Atr Sample Fuel Plate Irradiation Experiment

“…(6) Fluorescent Penetration -A Zyglo test was performsd to inspect for pits and cracks. (7) Whole Plate Alpha Counting -The samples were alpha counted on both sides before anodizing to insure that no uranium had diffused through the cladding during fabrication.…”

“…Design objectives for this test are (a) maximum heat flux of 2.25 x 106 Btu/hr-ftz, (b) maximum thermal flux of 3.8 x 101't n/cmz-sec, (c) starting surface temperature of 17OOC (without anodization), and (d) burnup of 7 and 12 x 1020 fiss/cc. To accomplish this test a new loop facility is being designed with construction scheduled to be completed the latter part of F Y 1964.…”