Fuel element development program for the Pebble Bed Reactor. Final Report
The basic fuel element consisted of a uniform dispersion of fuel in a 1 1/2 inch diameter graphite sphere. Ceramic coatings for the retention of fission products were studied. It was found that molecularly deposited ceramics such as alumina, siliconized silicon carbide, and pyrolytic carbon were excellent barriers to fission product leakage. The most advantageous location for ceramic coatings was found to be on the individual fuel particles, where the coating was subject to smaller forces and where a larger thickness-todiameter ratio could be used than if the coating were on the surface of the graphite sphere. Fuel elements were irradiated to burnups ranging up to about 6 at.% U/sup 235/. In all specimens containing a uniform dispersion of fuel, the graphite spheres were found to retain their structural properties after irradiation. Data are given on fuel particle coatings of A1/sub 2/O/sub 3/, pyrolytic carbon, and metals: surface coatings of siliconized silicon carbide, pyrolytic carbon, and metal carbides; properties of and the effects of irradiation on graphite spheres; the use of natural graphite in preparing a high-density matrix material; graphite fueling by thorium nitrate infiltration; subsurface metal and metal carbide coatings for graphite; and an in-pile loop program on the behavior of fission products in a recycle helium stream. (auth)
- Research Organization:
- Sanderson and Porter, New York, NY (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- NSA Number:
- NSA-16-009663
- OSTI ID:
- 4804887
- Report Number(s):
- NYO--9064
- Country of Publication:
- United States
- Language:
- English
Similar Records
FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Phase II Summary Report, November 1, 1959 to October 31, 1960
FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Quarterly Progress Report for November 1, 1959 to January 31, 1960
Related Subjects
ALUMINUM OXIDES
BURNUP
CARBIDES
CARBON
CERAMICS
COATING
CONFIGURATION
CONTAMINATION
COOLANT LOOPS
DENSITY
DIFFUSION
DISPERSIONS
FABRICATION
FISSION PRODUCTS
FISSIONABLE MATERIALS
FUEL ELEMENTS
FUELS
GAS COOLANT
GAS FLOW
GRAPHITE
GRAPHITE MODERATOR
HELIUM
IMPURITIES
IN PILE LOOPS
INERT GASES
IRRADIATION
LEAKS
MATERIALS TESTING
MECHANICAL PROPERTIES
METALS
MOLECULES
PEBBLE BED
PELLETS
POWER PLANTS
PYROLYSIS
RADIATION EFFECTS
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
SILICON CARBIDES
SPHERES
SURFACES
THERMAL STRESSES
THICKNESS
THORIUM NITRATES
URANIUM 235