Published November 1985
| Version v1
Journal article
Graphite disk UO2 fuel elements designed for extended burnups at high powers
Description
Zircaloy-clad fuel elements containing UO2 pellets separated by thin graphite disks have been irradiated to maximum burnups of 800 MWh/kg U (33 000 MWd/tonne U) at a linear power range of 30 to 70 kW/m. Fission gas release and sheath strains were lower than experienced for conventional fuel under comparable conditions because of the lower bulk average fuel temperatures in disk elements. The irradiated disk elements also showed good internal stability, tolerance to power ramping, and acceptable defect behavior
Additional details
Publishing Information
- Journal Title
- Nucl. Technol.
- Journal Volume
- 71
- Journal Issue
- 2
- Series
- Nucl. Technol.
- Journal Page Range
- 430-444
- ISSN
- 0029-5450
- CODEN
- NUTYB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17069127
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BURNUP; FISSION PRODUCT RELEASE; FUEL ELEMENTS; FUEL PELLETS; FUEL-CLADDING INTERACTIONS; GRAPHITE; IRRADIATION; MATERIALS TESTING; PERFORMANCE; PHYSICAL RADIATION EFFECTS; SPACERS; STRAINS; URANIUM DIOXIDE; ZIRCALOY
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOYS; CARBON; CHALCOGENIDES; ELEMENTS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; RADIATION EFFECTS; REACTOR COMPONENTS; TESTING; URANIUM COMPOUNDS; URANIUM OXIDES; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS