Methods of fabricating uranium monocarbide, mononitride, and carbonitride cores for fast reactor fuel elements

Journal Article · Sat Dec 01 04:00:00 EST 1973 · At. Energ. (USSR), v. 35, no. 6, pp. 377-386

OSTI ID:4350762

Reshetnikov, F G; Kotel'nikov, R B; Rogozkin, B D; Bashlykov, S N; Samokhvalov, I A; Titov, G V; Shishkov, M G; Belevantsev, V S; Fedorov, Yu E; Simonov, V P

Laboratory methods of obtaining uranium carbide, nitride, and carbonitride, and fabricating fuel-element cores from them were developed. The uranium compounds were obtained from reactions between metallic uranium and nitrogen, preceded by hydrogenation of the metal. A continuous process was achieved using specially developed equipment that yielded 1.5 to 2 kg of product per hour. Uranium compounds were obtained also by carbo-thermal reduction of uranium dioxide in a boiling layer. From compound powders, pellets were obtained by cold pressing followed by sintering and long rods by extrusion through a die and sintering. Parameters of the processes yielding products of the required composition, structure, density and other properties are presented. (auth)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-29-021373
• OSTI ID: 4350762
• Journal Information: At. Energ. (USSR), v. 35, no. 6, pp. 377-386, Journal Name: At. Energ. (USSR), v. 35, no. 6, pp. 377-386; ISSN AENGA
• Country of Publication: Country unknown/Code not available
• Language: Russian

Related Subjects

*FAST REACTORS-- FUEL ELEMENTS
*FUEL ELEMENTS-- FABRICATION
*URANIUM CARBIDES-- FABRICATION
*URANIUM NITRIDES-- FABRICATION
CHEMICAL COMPOSITION
COLD PRESSING
DENSITY
DIES
EXTRUSION
FUEL PELLETS
N50120* --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Preparation & Fabrication
NITRIDATION
POWDERS
REDUCTION
SINTERING
URANIUM
URANIUM DIOXIDE