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

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

>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 Atomics, San Diego, CA (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AT(04-3)-314
NSA Number:
NSA-16-006214
OSTI ID:
4821311
Report Number(s):
GA-2289
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English

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Related Subjects

REACTOR TECHNOLOGY
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
SILICIDES
SINTERING
THORIUM CARBIDES
THORIUM OXIDES
THORIUM SILICATES
URANIUM CARBIDES
URANIUM OXIDES
URANIUM SILICATES