RETENTION OF IODINE BY PYROLYTIC-CARBON-COATED NUCLEAR FUEL PARTICLES

Author: Langer, S
Published: United States : [publisher not identified], 1968.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1968.
Physical Description: microfiche : negative ; 11 x 15 cm
Additional Creators: Adams, C. C., Anderson, E. E., Graves, J. N., and Yamaguchi, T.

Availability

Finding items...

Report Numbers

GA-8524; CONF-680308-13

Other Subject(s)

Annealing
Carbon
Carbon/fission product retention by thorium carbide (thc2)-uranium carbide (uc2) particle-type fuel coated with pyrolytic, analysis at 1100 and 13000c of.
Coating
Configuration
Fission products
Fuels
Gas coolant
High temperature
Iodine 133
Iodine isotopes i-133/retention by pyrolytic-carbon-coated thorium ca.
N38150 -power reactor development-fuels
Reactor fuels/fission product retention by pyrolytic-carbon- coated thorium carbide (thc2)-uranium carbide (uc2) particle type, analysis at 1100 and 13000c of.
Reactors, gas-cooled/fuels for high-temperature, analysis of fission product retention at 1100 and 13000c by pyrolytic- carbon-coated thorium carbide (thc2)-uranium carbide (uc2) particle- type
Reactors, power/fuels for high-temperature gas-cooled, analysis of fission product retention at 1100 and 13000c by pyrolytic-carbon-coated thorium carbide (thc2)-uranium carbide (uc2) particle-type
Reactors
Temperature
Thorium carbides
Uranium carbides
Uranium carbides/thc2-uc2, fission product retention by pyrolytic-carbon-coated particle-type, analysis at 1100 and 13000c of.
Xenon 135

Collection

U.S. Atomic Energy Commission depository collection.

Note

DOE contract number: AT(04-3)-633
NSA number: NSA-23-009156
OSTI Identifier 4812960
Research organization: Gulf General Atomic, Inc., San Diego, Calif.

View MARC record | catkey: 45371271

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RETENTION OF IODINE BY PYROLYTIC-CARBON-COATED NUCLEAR FUEL PARTICLES

Availability