THE DEVELOPMENT AND EVALUATION OF GRAPHITE-MATRIX FUEL COMPACTS FOR THE HTGR

Technical Report · Tue Aug 01 04:00:00 EDT 1961

DOI:https://doi.org/10.2172/4821311· OSTI ID:4821311

Goeddel, W V

>A summary of development and evaluation of graphitematrix fuel compacts for the high-temperature gas-cooled reactor is presented. The fuel compacts consist of Th-- U dicarbide particles dispersed in a high-density graphite matrix and are produced by a hot-pressing process. Compacts prepared from Th--U oxide, Th-- U silicide, and Th--U dicarbide coated with pyrolytic C were subjected to radiation and fission-product-retention testing. Results of these tests are included and are discussed in detail. (J.R.D.)

• Research Organization: General Atomic Div., General Dynamics Corp., San Diego, Calif.
• Sponsoring Organization: USDOE
• NSA Number: NSA-16-006214
• OSTI ID: 4821311
• Report Number(s): GA-2289
• Country of Publication: United States
• Language: English

Related Subjects

CARBON
COATING
CONTAMINATION
DENSITY
DISPERSIONS
FABRICATION
FISSION PRODUCTS
FUEL ELEMENTS
FUELS
GAS COOLANT
GRAPHITE
GRAPHITE MODERATOR
HIGH TEMPERATURE
HOT WORKING
HTGR
IRRADIATION
MATERIALS TESTING
MECHANICAL STRUCTURES
PLANNING
POROSITY
POWER PLANTS
PRESSURE
PYROLYSIS
REACTOR TECHNOLOGY
SILICIDES
SINTERING
THORIUM CARBIDES
THORIUM OXIDES
THORIUM SILICATES
URANIUM CARBIDES
URANIUM OXIDES
URANIUM SILICATES