Development of ZrC-coated UC--ZrC particles

Technical Report · Fri Apr 30 04:00:00 EDT 1976

OSTI ID:4175324

Savage, Jr, A W; Feber, R C; Bertino, J P; Baxman, H R; O'Rourke, J A; Bard, R J

Zirconium carbide coatings were deposited on U$sub 0$$.$$sub 3$Zr$sub 0$$.$$sub 7$C cores from zirconium tetrachloride-methane-hydrogen-helium mixtures at 1400$sup 0$C in an attempt to develop improved coated particles for use in Rover graphite-matrix fuel elements. The coated particles were tested at 2500$sup 0$C. Those with coatings thin enough to satisfy the requirements of small particle size and high uranium content survived heating in a tungsten container but failed when heated in graphite crucibles, presumably owing to rapid diffusion of carbon through the ZrC coating and formation of a low melting (2400$sup 0$C) ternary eutectic with the core. Increasing the coating thickness from about 20 to about 45 $mu$ enabled the particles to withstand heating in graphite at 2500$sup 0$C because of the interdiffusion of core and coating to form a higher melting solid solution, but the uranium content of these particles was too low for use in Rover graphite-matrix fuel elements. (auth)

• Research Organization: Los Alamos Scientific Lab., N.Mex. (USA)
• DOE Contract Number: W-7405-ENG-36
• NSA Number: NSA-33-005894
• OSTI ID: 4175324
• Report Number(s): LA--4005
• Country of Publication: United States
• Language: English

Related Subjects

*COATED FUEL PARTICLES-- PERFORMANCE TESTING
*ROVER REACTORS-- COATED FUEL PARTICLES
*URANIUM CARBIDES-- PERFORMANCE TESTING
*ZIRCONIUM CARBIDES-- PERFORMANCE TESTING
360200* --Materials--Ceramics
Cermets & Refractories
COATINGS
COMPATIBILITY
FAILURES
FUEL ELEMENTS
GRAPHITE
N50100* --Metals
Ceramics
& Other Materials--Ceramics & Cermets
NESDPS Office of Nuclear Energy Space and Defense Power Systems
THICKNESS