FISSION PRODUCT RELEASE FROM AN OVERHEATED HTGR FUEL (ORR POOLSIDE CAPSULE 06-11).

Technical Report · Wed Jan 01 00:00:00 EST 1969

OSTI ID:4812806

Freid, S H; de Nordwall, H J; Cuneo, D R; Conlin, J A; Segaser, C L; Long, Jr, E L

• Research Organization: Oak Ridge National Lab., Tenn.
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-23-017234
• OSTI ID: 4812806
• Report Number(s): ORNL-TM-2388
• Resource Relation: Other Information: UNCL. Orig. Receipt Date: 31-DEC-69
• Country of Publication: United States
• Language: English

Related Subjects

N38180* -Power Reactor Development-Safety & Siting
ACCIDENTS
BONDING
CAPSULES
FISSION PRODUCTS
FUELS
GAS COOLANT
HEATING
HIGH TEMPERATURE
IRRADIATION
LOSSES
PARTICLES
REACTOR SAFETY
REACTORS
URANIUM CARBIDES
VESSELS
URANIUM CARBIDES/fission product release from bonded fuel particles of
in simulated HTGR coolant loss accidents
(E)
REACTOR FUELS/ fission product release from overheated bonded uranium carbide (UC$sub 2$)
in simulated HTGR coolant loss accidents
(E)
REACTORS
GAS-COOLED/coolant loss accidents in high-temperature
fission product release from overheated bonded uranium carbide (UC$sub 2$) fuel in simulated
(E)
REACTOR SAFETY/fission product release from overheated bonded uranium carbide (UC$sub 2$) fuel in simulated HTGR coolant loss accidents
(E)
FISSION PRODUCTS/release from overheated bonded uranium carbide (UC$sub 2$) fuel in simulated HTGR coolant loss accidents
(E)