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 neutrons/cm/ (>1 Mev), with irradiation times of 2.03 x 105 to 5.60 x 106 sec, at 110 to 1025 C, and gamma heat generation rates of 18 to 25 w/g. The greatest damage appeared in bodies irradiated for high neutron doses at low temperatures. Greater doses could be tolerated at higher temperatures. Specimens irradiated at 110 deg C powdered at an accumulated dose of 1.5 x 10/sup 21/ 1.1 x 10/sup 21/ neutrons/cm/sup 2/ and at 737 deg C at a dose of 1.6 x 10 /sup 21/ neutrons/cm/sup 2/ remained intact. Specimens irradiated at 827 to 950 deg C at a dose of 2.1 to 2.6 x 10/sup 21/ neutrons/cm/sup 2/ fractured. Changes in linear dimensions up to 4% ...
Beryllium oxide bend test specimens of two grain sizes, 1—2 microns and 8—35 microns, were irradiate...
In recent years, beryllium oxide has been widely utilized in multiple compact nuclear reactors as th...
This paper presents the results of the study of the effect of irradiation temperature on structural ...
Neutron and gamma penetrations through and behind BeO were measured. Neutron spectra measurements by...
Fuelled beryllium oxide spheres, with a thin layer of porous BeO separating the fuelled core from th...
The work reported in AAEC/E106 on the metallographic examination of (U,Th)02 dispersed in BeO irradi...
Dispersions of (UTh)O2 in beryliia, containing 1.7 per cent to 25 per cent (UTh)C>2 in three fuel pa...
Increasing numbers of designers are choosing beryllium for fusion reactor blankets because it, among...
"Date issued Apr 2 1962"."ORNL-3164."Bibliography references included.Mode of access: Internet
A simple analytical model is developed which adequately describes the available data on the lattice ...
As a part of the ML-1 reactor fuel evaluation program, UO/sub 2/-- BeO bodies containing two UO/sub ...
Beside carbon materials and tungsten, beryllium will play an important role as plasma facing materia...
The effects of fission fragment damage on vacuum hot pressed fuel specimens of (U Th) Be13 dispersed...
The Experimental Beryllium Oxide Reactor is described. The configurations and properties of BeO bloc...
The mechanical strength of hot-pressed and cold-pressed and sintered dispersions of (U,Th)O2 in BeO ...
Beryllium oxide bend test specimens of two grain sizes, 1—2 microns and 8—35 microns, were irradiate...
In recent years, beryllium oxide has been widely utilized in multiple compact nuclear reactors as th...
This paper presents the results of the study of the effect of irradiation temperature on structural ...
Neutron and gamma penetrations through and behind BeO were measured. Neutron spectra measurements by...
Fuelled beryllium oxide spheres, with a thin layer of porous BeO separating the fuelled core from th...
The work reported in AAEC/E106 on the metallographic examination of (U,Th)02 dispersed in BeO irradi...
Dispersions of (UTh)O2 in beryliia, containing 1.7 per cent to 25 per cent (UTh)C>2 in three fuel pa...
Increasing numbers of designers are choosing beryllium for fusion reactor blankets because it, among...
"Date issued Apr 2 1962"."ORNL-3164."Bibliography references included.Mode of access: Internet
A simple analytical model is developed which adequately describes the available data on the lattice ...
As a part of the ML-1 reactor fuel evaluation program, UO/sub 2/-- BeO bodies containing two UO/sub ...
Beside carbon materials and tungsten, beryllium will play an important role as plasma facing materia...
The effects of fission fragment damage on vacuum hot pressed fuel specimens of (U Th) Be13 dispersed...
The Experimental Beryllium Oxide Reactor is described. The configurations and properties of BeO bloc...
The mechanical strength of hot-pressed and cold-pressed and sintered dispersions of (U,Th)O2 in BeO ...
Beryllium oxide bend test specimens of two grain sizes, 1—2 microns and 8—35 microns, were irradiate...
In recent years, beryllium oxide has been widely utilized in multiple compact nuclear reactors as th...
This paper presents the results of the study of the effect of irradiation temperature on structural ...