Status report March 1981 thermal-gradient-test LEU fuel. [HTGR]
Technical Report
·
OSTI ID:5238832
Samples of candidate LEU fuels have been heated out-of-pile at approx. 1500/sup 0/C in a thermal gradient test. Silicon carbide failure in TRISO UO/sub 2/ and TRISO UC/sub 2/ was detected by x-radiography and by loss of Cs-137 after 163.5 hr. End-of-test ceramography showed that the SiC layer in the TRISO UC/sub 2/ (6151-21-0111-5) had been corroded on both the hot and cold sides of the particles. No fission products were associated with the hot side corrosion, but Pd, U, Ru, Rh and rare-earth metals were detected in the corrosion zone on the cold side of the particle. Ceramography of the TRISO UO/sub 2/ (6152-01-0111-3) showed that large voids had been formed in the SiC layer completely around the particle. Pd had concentrated at the interface between the inner PyC and the SiC. In addition, free Si had accumulated in the SiC. No SiC corrosion was observed in the TRISO UO/sub 2/ (6152-03-0111-6). Palladium had accumulated at the SiC interface on the cool side of the particles and had diffused at least two-thirds of the way through the SiC without any visual SiC attack.
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- DOE Contract Number:
- AT03-76ET35300
- OSTI ID:
- 5238832
- Report Number(s):
- DOE/ET/35300-T4; ON: DE82008170
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
36 MATERIALS SCIENCE
360206 -- Ceramics
Cermets
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ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
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CHEMICAL REACTIONS
COATED FUEL PARTICLES
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FUEL ELEMENTS
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FUEL RODS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
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INDUSTRIAL RADIOGRAPHY
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
SILICON CARBIDES
SILICON COMPOUNDS
TESTING
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
X-RAY RADIOGRAPHY
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
36 MATERIALS SCIENCE
360206 -- Ceramics
Cermets
& Refractories-- Radiation Effects
360604 -- Materials-- Corrosion
Erosion
& Degradation
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
CHALCOGENIDES
CHEMICAL REACTIONS
COATED FUEL PARTICLES
CORROSION
FUEL ELEMENTS
FUEL PARTICLES
FUEL RODS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
INDUSTRIAL RADIOGRAPHY
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
SILICON CARBIDES
SILICON COMPOUNDS
TESTING
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
X-RAY RADIOGRAPHY