Fuel specimens having uranium—thorium beryHides as the fissile bearing phase were irradiated at 400 to 700 ºC to burn—ups between 7 and lla/0 uranium in a predominantly thermal flux, two specimens of massive (U.;Th)Be 13 exhibited good dimensional stability and low fission gas release. Dispersion specimens containing 20, 35, and 50v/o (U,Th)Be13 swelled by 3 to 18 per cent0 and released up to 33 per cent, of the gaseous fission products. The results indicate that the mixed beryllide is an inherently good fuel material and lead to the conclusion that the poor irradiation stability of hot—pressed specimens may not be typical of (U,Th) Be 13— Be dispersions prepared by other techniques
Progress in fuels and materials development is reported. Irradiation tests on powdered UAl/sub 3/ in...
Increasing numbers of designers are choosing beryllium for fusion reactor blankets because it, among...
Activities in a project aimed at the improvement of fuel elements for high flux test reactors are re...
The effects of fission fragment damage on vacuum hot pressed fuel specimens of (U Th) Be13 dispersed...
The mechanical strength of hot-pressed and cold-pressed and sintered dispersions of (U,Th)O2 in BeO ...
As a part of the ML-1 reactor fuel evaluation program, UO/sub 2/-- BeO bodies containing two UO/sub ...
The work reported in AAEC/E106 on the metallographic examination of (U,Th)02 dispersed in BeO irradi...
One capsule containing BeO-30 vol% UO/sub 2/ fuel pellets was irradiated to a uranium burnup of appr...
Dispersions of (UTh)O2 in beryliia, containing 1.7 per cent to 25 per cent (UTh)C>2 in three fuel pa...
A controlled radiation experiment was performed to determine the stability of fuel containing 28 wt....
A fuel development campaign that results in an aluminum plate-type fuel of unlimited LEU burnup capa...
Considerations affecting the design of dispersion-type ceramic fuel materials are discussed. The res...
"Presented at the American Ceramic Society Symposium on Ceramic Materials for Nuclear Power and Spac...
Fission gas release from spherical BeO-based fuel elements designed for the conceptual ABORIGINE rea...
Uranium and thorium beryllides and their solid solutions were prepared by reaction-sintering, reacti...
Progress in fuels and materials development is reported. Irradiation tests on powdered UAl/sub 3/ in...
Increasing numbers of designers are choosing beryllium for fusion reactor blankets because it, among...
Activities in a project aimed at the improvement of fuel elements for high flux test reactors are re...
The effects of fission fragment damage on vacuum hot pressed fuel specimens of (U Th) Be13 dispersed...
The mechanical strength of hot-pressed and cold-pressed and sintered dispersions of (U,Th)O2 in BeO ...
As a part of the ML-1 reactor fuel evaluation program, UO/sub 2/-- BeO bodies containing two UO/sub ...
The work reported in AAEC/E106 on the metallographic examination of (U,Th)02 dispersed in BeO irradi...
One capsule containing BeO-30 vol% UO/sub 2/ fuel pellets was irradiated to a uranium burnup of appr...
Dispersions of (UTh)O2 in beryliia, containing 1.7 per cent to 25 per cent (UTh)C>2 in three fuel pa...
A controlled radiation experiment was performed to determine the stability of fuel containing 28 wt....
A fuel development campaign that results in an aluminum plate-type fuel of unlimited LEU burnup capa...
Considerations affecting the design of dispersion-type ceramic fuel materials are discussed. The res...
"Presented at the American Ceramic Society Symposium on Ceramic Materials for Nuclear Power and Spac...
Fission gas release from spherical BeO-based fuel elements designed for the conceptual ABORIGINE rea...
Uranium and thorium beryllides and their solid solutions were prepared by reaction-sintering, reacti...
Progress in fuels and materials development is reported. Irradiation tests on powdered UAl/sub 3/ in...
Increasing numbers of designers are choosing beryllium for fusion reactor blankets because it, among...
Activities in a project aimed at the improvement of fuel elements for high flux test reactors are re...