The mechanical strength of hot-pressed and cold-pressed and sintered dispersions of (U,Th)O2 in BeO was measured before and after irradiation using the diametral compression test. The addition of more than 5 volume per cent. (U,Th)02 lowered the unirradiated strength to about 60 per cent, of the strength of BeO. Irradiation resulted in a marked drop in strength of all coarse dispersions. Hot-pressed fine dispersions behaved similarly to coarse dispersions of the same composition but the cold-pressed fine dispersions exhibited an apparent increase of strength on irradiation. High temperatures favoured the retention of strength during irradiation
The effect of variations in temperature, pressure and pressure cycle on the density vs grain size re...
Considerations affecting the design of dispersion-type ceramic fuel materials are discussed. The res...
The effects of fission fragment damage on vacuum hot pressed fuel specimens of (U Th) Be13 dispersed...
The paper presents data on changes in strength properties, including data on microhardness, crack re...
The work reported in AAEC/E106 on the metallographic examination of (U,Th)02 dispersed in BeO irradi...
Fuel specimens having uranium—thorium beryHides as the fissile bearing phase were irradiated at 400 ...
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...
As a part of the ML-1 reactor fuel evaluation program, UO/sub 2/-- BeO bodies containing two UO/sub ...
The paper presents data on changes in strength properties, including data on microhardness, crack re...
The measured Knoop hardness of beryllium oxide was found to depend on both the indenter load and the...
Dispersions of (UTh)O2 in beryliia, containing 1.7 per cent to 25 per cent (UTh)C>2 in three fuel pa...
High-temperature tensile and thermal-shock investigations were conducted on beryllium oxide and bery...
"Contract No. W-7405-eng-92.""UC-25 Metallurgy and Ceramics (TID-4500, 15th Ed.).""December 9, 1960....
High-temperature tensile and thermal-shock investigations were conducted on beryllium oxide and bery...
The Experimental Beryllium Oxide Reactor is described. The configurations and properties of BeO bloc...
The effect of variations in temperature, pressure and pressure cycle on the density vs grain size re...
Considerations affecting the design of dispersion-type ceramic fuel materials are discussed. The res...
The effects of fission fragment damage on vacuum hot pressed fuel specimens of (U Th) Be13 dispersed...
The paper presents data on changes in strength properties, including data on microhardness, crack re...
The work reported in AAEC/E106 on the metallographic examination of (U,Th)02 dispersed in BeO irradi...
Fuel specimens having uranium—thorium beryHides as the fissile bearing phase were irradiated at 400 ...
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...
As a part of the ML-1 reactor fuel evaluation program, UO/sub 2/-- BeO bodies containing two UO/sub ...
The paper presents data on changes in strength properties, including data on microhardness, crack re...
The measured Knoop hardness of beryllium oxide was found to depend on both the indenter load and the...
Dispersions of (UTh)O2 in beryliia, containing 1.7 per cent to 25 per cent (UTh)C>2 in three fuel pa...
High-temperature tensile and thermal-shock investigations were conducted on beryllium oxide and bery...
"Contract No. W-7405-eng-92.""UC-25 Metallurgy and Ceramics (TID-4500, 15th Ed.).""December 9, 1960....
High-temperature tensile and thermal-shock investigations were conducted on beryllium oxide and bery...
The Experimental Beryllium Oxide Reactor is described. The configurations and properties of BeO bloc...
The effect of variations in temperature, pressure and pressure cycle on the density vs grain size re...
Considerations affecting the design of dispersion-type ceramic fuel materials are discussed. The res...
The effects of fission fragment damage on vacuum hot pressed fuel specimens of (U Th) Be13 dispersed...