Activities in a program to obtain UC pellets of maximum density for irradiation testing are described. A study was made of the effects of the UC powder thermal history, sintering time, sintering temperature, and additives on the UC sinterability. Preliminary results indicate that the UC powder synthesized under the most severe conditions of temperature and time (1740 deg C, 107 min) was less sinterable than powders prepared at lower temperatures, or at the same temperature for shorter time. It was also concluded that although both temperature and time of sintering pellets affect density, temperature is more important. Additions of Fe (0.1 to 1.0%) improve sinterability and promote grain growth. The final density obtained on sintering in a v...
Powder characteristics of PuO/sub 2/ prepared by oxalate and hydroxide precipitation were determined...
"Contract No. W-7405-eng-92.""UC-4 Chemistry-General (TID-4500, 13th Ed.).""September 9, 1957.""Repo...
AbstractThe preparation of uranium carbide (UC) by carbothermal reduction and its sintering into den...
The refractory uranium compounds UC and UC/sub 2/ were prepared by arc- melting methods, UN by gas s...
Batches of UC were synthesized for use in fabrication of specimens for physical property determinati...
Several synthesis experiments were carried out to provide a stock of U/ sub 3/Si/sub 2/, powders for...
Activitiee are described in an investigation to develop refractory U materiala for superior reactor ...
Additional work on the synthesis and fabrication of uranium nitride produced an improved product fre...
Preparation of about 1200 g of uranium nitride powder is reported. Experiments indicated that synthe...
The effect of initial particle size (6.2 and 14.7 mu ), forming pressure (50,000 and 100,000 psi), t...
International audienceThe sintering of uranium oxide powders prepared by hydrothermal conversion of ...
Mixed (U, Pu) carbides are potential candidate fuels for future IV th generation reactor systems bec...
AbstractResults of uranium carbide sintering using a spark plasma sintering facility are presented h...
Pacific Northwest Laboratory (PNL) has evaluted, on a laboratory scale, the characteristics and pell...
Metallographic and dilatometric studies of the heat treatment behavior of technical uranium and cert...
Powder characteristics of PuO/sub 2/ prepared by oxalate and hydroxide precipitation were determined...
"Contract No. W-7405-eng-92.""UC-4 Chemistry-General (TID-4500, 13th Ed.).""September 9, 1957.""Repo...
AbstractThe preparation of uranium carbide (UC) by carbothermal reduction and its sintering into den...
The refractory uranium compounds UC and UC/sub 2/ were prepared by arc- melting methods, UN by gas s...
Batches of UC were synthesized for use in fabrication of specimens for physical property determinati...
Several synthesis experiments were carried out to provide a stock of U/ sub 3/Si/sub 2/, powders for...
Activitiee are described in an investigation to develop refractory U materiala for superior reactor ...
Additional work on the synthesis and fabrication of uranium nitride produced an improved product fre...
Preparation of about 1200 g of uranium nitride powder is reported. Experiments indicated that synthe...
The effect of initial particle size (6.2 and 14.7 mu ), forming pressure (50,000 and 100,000 psi), t...
International audienceThe sintering of uranium oxide powders prepared by hydrothermal conversion of ...
Mixed (U, Pu) carbides are potential candidate fuels for future IV th generation reactor systems bec...
AbstractResults of uranium carbide sintering using a spark plasma sintering facility are presented h...
Pacific Northwest Laboratory (PNL) has evaluted, on a laboratory scale, the characteristics and pell...
Metallographic and dilatometric studies of the heat treatment behavior of technical uranium and cert...
Powder characteristics of PuO/sub 2/ prepared by oxalate and hydroxide precipitation were determined...
"Contract No. W-7405-eng-92.""UC-4 Chemistry-General (TID-4500, 13th Ed.).""September 9, 1957.""Repo...
AbstractThe preparation of uranium carbide (UC) by carbothermal reduction and its sintering into den...