Published 1985
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Dimensional changes in operating UO2 fuel elements: effects of pellet density, burnup and ramp rate
Description
We have used an in-reactor diameter measuring rig, in combination with a He-3 coil associated with the X-6 loop of the NRX reactor, to determine the dimensional response of CANDU-type UO2 fuel elements as a function of power, prior irradiation, fuel density and ramp rate. The maximum diametral increase accompanying a ramp was about 1% for high density fuel. No elements failed, despite, in the most severe case, a 1.5 h hold at 56 kW/m, after a ramp from 30 kW/m in less than three minutes. (author).
Availability note (English)
Also published in: Proceedings of the Conference on Nuclear Fuel Performance, Stratford-upon-Avon, U.K., 25-29 March 1985, Vol. 1, p. 25-30.Files
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Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- AECL--8605
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 44045094
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; DENSITY; DIMENSIONS; FAILED ELEMENT DETECTION; FUEL PELLETS; FUEL RODS; HELIUM 3; IN PILE LOOPS; IRRADIATION; PERFORMANCE; REACTOR EXPERIMENTAL FACILITIES; URANIUM COMPOUNDS; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; DETECTION; EVEN-ODD NUCLEI; FUEL ELEMENTS; HELIUM ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEI; OXIDES; OXYGEN COMPOUNDS; PELLETS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIES; STABLE ISOTOPES; URANIUM COMPOUNDS
Optional Information
- Notes
- 7 refs., 2 tabs., 5 figs.