Add to ORKGDispersions of (UTh)O2 in beryliia, containing 1.7 per cent to 25 per cent (UTh)C>2 in three fuel particle sizes, coarse (150 —200μ)> medium (33 — 35μ and fine (<10 and <5º) were irradiated to burnups of 3—10 per cent of heavy metal atoms in the range 300-900ºC, in both fast and thermal fluxes. Changes in volume, lattice parameter, line breadth, and modulus of rupture were measured. Volume changes in the fine dispersions were ascribed wholly to fission fragment damage and were about 50 per cent greater than those caused by fast neutrons alone; they increased with increasing fission fragment flux, and decreased as irradiation temperature increased. Volume changes in medium and coarse dispersions were about 25 per cent greater than those ca...
The mechanical strength of hot-pressed and cold-pressed and sintered dispersions of (U,Th)O2 in BeO ...
Neutron and gamma penetrations through and behind BeO were measured. Neutron spectra measurements by...
From topical conference on energy; Chicago, Illinois, USA (4 Feb 1974). Fuel, cladding, structural m...
The effects of fission fragment damage on vacuum hot pressed fuel specimens of (U Th) Be13 dispersed...
The work reported in AAEC/E106 on the metallographic examination of (U,Th)02 dispersed in BeO irradi...
Fuelled beryllium oxide spheres, with a thin layer of porous BeO separating the fuelled core from th...
Specimens of 0.428 to 1.18 in. dia. BeO were irradiated at 1.4 x 10/sup 20/ to 2.8 x 10/sup 21/ fast...
A beryllium primary vacuum-to-air beam ‘window’ of the “Neutrinos at the Main Injector” (NuMI) beaml...
Fuel specimens having uranium—thorium beryHides as the fissile bearing phase were irradiated at 400 ...
One capsule containing BeO-30 vol% UO/sub 2/ fuel pellets was irradiated to a uranium burnup of appr...
The effect of grain size on microstructural change and damage recovery in U0 fuels was studied by X-...
Long-life fast reactors receive considerable attention for their potential of using uranium efficien...
As a part of the ML-1 reactor fuel evaluation program, UO/sub 2/-- BeO bodies containing two UO/sub ...
The effect of grain size on microstructural change and damage recovery in UOfuels was studied by X-r...
Fission gas release from spherical BeO-based fuel elements designed for the conceptual ABORIGINE rea...
The mechanical strength of hot-pressed and cold-pressed and sintered dispersions of (U,Th)O2 in BeO ...
Neutron and gamma penetrations through and behind BeO were measured. Neutron spectra measurements by...
From topical conference on energy; Chicago, Illinois, USA (4 Feb 1974). Fuel, cladding, structural m...
The effects of fission fragment damage on vacuum hot pressed fuel specimens of (U Th) Be13 dispersed...
The work reported in AAEC/E106 on the metallographic examination of (U,Th)02 dispersed in BeO irradi...
Fuelled beryllium oxide spheres, with a thin layer of porous BeO separating the fuelled core from th...
Specimens of 0.428 to 1.18 in. dia. BeO were irradiated at 1.4 x 10/sup 20/ to 2.8 x 10/sup 21/ fast...
A beryllium primary vacuum-to-air beam ‘window’ of the “Neutrinos at the Main Injector” (NuMI) beaml...
Fuel specimens having uranium—thorium beryHides as the fissile bearing phase were irradiated at 400 ...
One capsule containing BeO-30 vol% UO/sub 2/ fuel pellets was irradiated to a uranium burnup of appr...
The effect of grain size on microstructural change and damage recovery in U0 fuels was studied by X-...
Long-life fast reactors receive considerable attention for their potential of using uranium efficien...
As a part of the ML-1 reactor fuel evaluation program, UO/sub 2/-- BeO bodies containing two UO/sub ...
The effect of grain size on microstructural change and damage recovery in UOfuels was studied by X-r...
Fission gas release from spherical BeO-based fuel elements designed for the conceptual ABORIGINE rea...
The mechanical strength of hot-pressed and cold-pressed and sintered dispersions of (U,Th)O2 in BeO ...
Neutron and gamma penetrations through and behind BeO were measured. Neutron spectra measurements by...
From topical conference on energy; Chicago, Illinois, USA (4 Feb 1974). Fuel, cladding, structural m...