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

Technical Report · Mon Jan 01 00:00:00 EST 1968

OSTI ID:4812960

Langer, S; Adams, C C; Anderson, E E; Graves, J N; Yamaguchi, T

• Research Organization: Gulf General Atomic, Inc., San Diego, Calif.
• DOE Contract Number: AT(04-3)-633
• NSA Number: NSA-23-009156
• OSTI ID: 4812960
• Report Number(s): GA-8524; CONF-680308-13
• Resource Relation: Other Information: From 155th National Meeting of the American Chemical Society, San Francisco, Calif. UNCL. Orig. Receipt Date: 31-DEC-69
• Country of Publication: United States
• Language: English

Related Subjects

N38150* -Power Reactor Development-Fuels
ANNEALING
CARBON
COATING
CONFIGURATION
FISSION PRODUCTS
FUELS
GAS COOLANT
HIGH TEMPERATURE
IODINE 133
REACTORS
TEMPERATURE
THORIUM CARBIDES
URANIUM CARBIDES
XENON 135
REACTORS
GAS-COOLED/fuels for high-temperature
analysis of fission product retention at 1100 and 1300$sup 0$C by pyrolytic- carbon-coated thorium carbide (ThC$sub 2$)-uranium carbide (UC$sub 2$) particle- type
CARBON/fission product retention by thorium carbide (ThC$sub 2$)-uranium carbide (UC$sub 2$) particle-type fuel coated with pyrolytic
analysis at 1100 and 1300$sup 0$C of
REACTOR FUELS/fission product retention by pyrolytic-carbon- coated thorium carbide (ThC$sub 2$)-uranium carbide (UC$sub 2$) particle type
analysis at 1100 and 1300$sup 0$C of
REACTORS
POWER/fuels for high-temperature gas-cooled
analysis of fission product retention at 1100 and 1300$sup 0$C by pyrolytic-carbon-coated thorium carbide (ThC$sub 2$)-uranium carbide (UC$sub 2$) particle-type
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fission product retention by pyrolytic-carbon-coated particle-type
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IODINE ISOTOPES I-133/retention by pyrolytic-carbon-coated thorium ca