Behavior of LASL-made graphite, ZrC, and ZrC-containing coated particles in irradiation tests HT-28 and HT-29

Technical Report · Thu Jan 01 04:00:00 EST 1976

DOI:https://doi.org/10.2172/7363491· OSTI ID:7363491

Reiswig, R D; Wagner, P; Hollabaugh, C M; White, R W; O'Rourke, J A; Davidson, K V; Schell, D H

Three types of materials, extruded graphite, hot-pressed ZrC, and particles with ZrC coatings, were irradiated in ORNL High Fluence Isotope Reactor Irradiation tests HT-28 and HT-29. The ZrC seemed unaffected. The graphite changed in dimensions, x-ray diffraction parameters, and thermal conductivity. The four types of coated particles tested all resisted the irradiation well, except one set of particles with double-graded C-ZrC-C coats. Overall, the results were considered encouraging for use of ZrC and extruded graphite fuel matrices. 16 fig.

• Research Organization: Los Alamos Scientific Lab., N.Mex. (USA)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 7363491
• Report Number(s): LA-6211
• Country of Publication: United States
• Language: English

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CARBIDES
CARBON
CARBON COMPOUNDS
COATED FUEL PARTICLES
ELEMENTS
EXTRUSION
FABRICATION
FUEL PARTICLES
GRAPHITE
MATERIALS WORKING
NONMETALS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
TRANSITION ELEMENT COMPOUNDS
ZIRCONIUM CARBIDES
ZIRCONIUM COMPOUNDS