CERAMIC-COATED-PARTICLE NUCLEAR FUELS

Journal Article · Wed Jan 01 04:00:00 EST 1964 · Journal of Nuclear Materials (Netherlands)

DOI:https://doi.org/10.1016/0022-3115(64)90117-5· OSTI ID:4022262

Dayton, R W; Oxley, J H; Townley, C W

Ceramic-coated-particle nuclear fuels consist of small particles of the fuel material, coated with a thin, impermeable ceramic layer and dispersed in a ceramic matrix. Such fuel mnterials are of interest primarily because they hold promise of achieving complete fission product retertion at high temperatures, using materials having low neutron absorption cross section and good corrosion resistance. The currert technical status of such fuel materials is reviewed. Particles of fuel materials have been coated with pyrolytic carbon, beryllia, alumina, magnesia, zirconia, silicon carbide, and niobium carbide. They have been dispersed in graphite, BeO, and Al/sub 2/O/sub 3/, though few data have been reported for BeO matrices. Laboratory and inpile evaluations of these materials are showing how to overcome difficulties experienced in early studies. Recent data have shown that essentially complete fission product retention can be achieved at temperatures above 1000 deg C, for burnups in excess of 6 per cent of metal atoms. (auth)

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• NSA Number: NSA-18-019332
• OSTI ID: 4022262
• Journal Information: Journal of Nuclear Materials (Netherlands), Journal Name: Journal of Nuclear Materials (Netherlands) Vol. Vol: 11; ISSN JNUMA
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ABSORPTION
ADSORPTION
ALUMINUM OXIDES
ATOMS
BERYLLIUM OXIDES
BURNUP
CARBON
CERAMICS
COATING
CORROSION
CROSS SECTIONS
DISPERSIONS
FISSION PRODUCTS
FUELS
GRAPHITE
HIGH TEMPERATURE
IRRADIATION
LAYERS
MAGNESIUM OXIDES
MATERIALS TESTING
METALS
NEUTRONS
NIOBIUM CARBIDES
PARTICLES
PYROLYSIS
PYROLYTIC CARBON
REACTOR TECHNOLOGY
SILICON CARBIDES
THICKNESS
ZIRCONIUM OXIDES