Published November 1983
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Behavior of mixed-oxide fuel subjected to multiple thermal transients
Description
The microstructural behavior of irradiated mixed-oxide fuel subjected to multiple, mild thermal transients was investigated using direct electrical heating. The results demonstrate that significant intergranular porosity, accompanied by large-scale (>90%) release of the retained fission gas, developed as a result of the cyclic heating. Microstructural examination of the fuel indicated that thermal-shock-induced cracking of the fuel contributed significantly to the increased swelling and gas release
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01; 1 as DE84005409.Files
15047343.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 36 p.
- Report number
- CONF-840113--3
Conference
- Title
- Symposium on space nuclear power systems.
- Dates
- 10-13 Jan 1984.
- Place
- Albuquerque, NM (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15047343
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CRACKS; FISSION PRODUCT RELEASE; FUEL RODS; MICROSTRUCTURE; PERFORMANCE TESTING; PLUTONIUM DIOXIDE; SPACE POWER REACTORS; SPATIAL DISTRIBUTION; TEMPERATURE DISTRIBUTION; THERMAL SHOCK; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CRYSTAL STRUCTURE; DISTRIBUTION; FUEL ELEMENTS; MOBILE REACTORS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES