SiC-fission product reactions in HTGR TRISO UC/sub 2/ and UC/sub x/O/sub y/ fissile fuel: II, reactions under isothermal conditions
Conference
·
· J. Am. Ceram. Soc.; (United States)
OSTI ID:5648894
The performance of irradiated TRISO UC/sub 2/ and TRISO UC/sub 4/ /sub 3/O/sub 1/ /sub 3/ HTGR fissile fuel particles was studied by postirradiation isothermal heating at 1600 to 2000/sup 0/C to evaluate HTGR fuel performance models. Test conditions were similar to reactor conditions predicted for hypothetical core heatup events evaluated during safety and licensing studies. Less than 2% of the particles experienced failure of all coating layers with rapid gaseous and metallic fission product release (pressure vessel failure). Lanthanide fission product, Cs-137, and Kr-85 release occurred in the remaining particles by diffusion through intact outer pyrocarbon layers after SiClanthanide fission product reactions had penetrated the SiC layers. The rates of SiC-fission product reactions depended on the fission density of the test samples and were less than or equal to those observed in a thermal gradient. Test results showed the HTGR fuel performance models to be very conservative.
- Research Organization:
- General Atomic Co., San Diego, CA
- DOE Contract Number:
- EY-76-C-03-0167
- OSTI ID:
- 5648894
- Conference Information:
- Journal Name: J. Am. Ceram. Soc.; (United States) Journal Volume: 61:11-12
- Country of Publication:
- United States
- Language:
- English
Similar Records
SiC-fission product reactions in HTGR TRISO UC/sub 2/ and UC/sub x/O/sub y/ fissile fuel: I, kinetics of reactions in a thermal gradient
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Two decades of DOE investment lays the foundation for TRISO-fueled reactors
Conference
·
Wed Oct 31 23:00:00 EST 1979
· J. Am. Ceram. Soc.; (United States)
·
OSTI ID:5648942
Head-end reprocessing studies with irradiated HTGR-type fuels. III. Studies with RTE-7: TRISO UC$sub 2$-TRISO ThC$sub 2$
Technical Report
·
Fri Oct 31 23:00:00 EST 1975
·
OSTI ID:4139386
Two decades of DOE investment lays the foundation for TRISO-fueled reactors
Journal Article
·
Fri Jul 31 20:00:00 EDT 2020
· Nuclear News
·
OSTI ID:1659600
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
36 MATERIALS SCIENCE
360206* -- Ceramics
Cermets
& Refractories-- Radiation Effects
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
CHALCOGENIDES
FISSION PRODUCT RELEASE
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEATING
HTGR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
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TEMPERATURE GRADIENTS
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM OXIDES
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
36 MATERIALS SCIENCE
360206* -- Ceramics
Cermets
& Refractories-- Radiation Effects
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
CHALCOGENIDES
FISSION PRODUCT RELEASE
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEATING
HTGR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTORS
TEMPERATURE GRADIENTS
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM OXIDES