Status report March 1981 thermal-gradient-test LEU fuel. [HTGR]
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; TRN: 82-015787
- Resource Relation:
- Other Information: Portions of document are illegible
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
COATED FUEL PARTICLES
CORROSION
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
HTGR TYPE REACTORS
SILICON CARBIDES
URANIUM CARBIDES
URANIUM DIOXIDE
FUEL RODS
X-RAY RADIOGRAPHY
ACTINIDE COMPOUNDS
CARBIDES
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GRAPHITE MODERATED REACTORS
INDUSTRIAL RADIOGRAPHY
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SILICON COMPOUNDS
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