Simulated fission product-SiC interaction in Triso-coated LEU or MEU HTGR fuel particles
Proliferation issues relating to the use of highly enriched uranium (HEU) have led to an evaluation of the fission product-SiC interaction problems that might arise if low enriched uranium (LEU) or medium enriched uranium (MEU) were used as fissile fuel in HTGR systems. Simulated Triso-coated UO/sub 2/, UC/sub 2/, and UO/sub 2//UC/sub 2/ particles mixed with varying amounts of Mo, Ru, Rh, Pd, Ag, and Cd were prepared. These fission products were chosen because, after full burnup, their concentrations are higher in LEU and MEU fuels than in HEU fuel. After the particles were heat treated in the laboratory, their behavior was examined by use of metallography, scanning electron microscopy, and electron microprobe x-ray analysis.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6918829
- Report Number(s):
- ORNL/TM-6991
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
ACTINIDE COMPOUNDS
BURNUP
CARBIDES
CARBON COMPOUNDS
CHALCOGENIDES
COATED FUEL PARTICLES
FISSION PRODUCTS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
ISOTOPES
MATERIALS
OXIDES
OXYGEN COMPOUNDS
RADIOACTIVE MATERIALS
REACTORS
SILICON CARBIDES
SILICON COMPOUNDS
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES