IRRADIATION BEHAVIOUR OF A 500 MM LONG HOLLOW U$sub 3$Si FUEL ELEMENT IRRADIATED UNDER BLW CONDITIONS.
A 500 mm long Zircaloy-clad element of U{sub 3} Si (4.3 wt% Si) containing a 13% central void was irradiated to an average burnup of 3600 MWd/tonne U at an average linear power output of 790 W/cm, in boiling water coolant at 55 bars pressure. A larger diameter increase (1.5%) at the mid-plane of the element than elsewhere was attributed to the reduced restraint imposed on the fuel in this area as a reduced restraint imposed on the fuel in this area as a consequence of {Beta} annealing a section of the cold worked sheath. Diameter increases in the cold worked portions of the sheath (average 0.7%) were greater than in similar elements irradiated in pressurized water at 96 bars pressure; the difference is attributed to higher linear power output of the element in this test. External swelling of the element before filling of the central void was complete is attributed to the higher silicon content of the fuel compared with previous tests. No reaction between U{sub 3}Si and Zircaloy was observed at a fuel sheath interface temperature near 400 degC.
- Research Organization:
- Atomic Energy of Canada Ltd., Chalk River (Ontario) Canada. Chalk River Nuclear Labs.
- NSA Number:
- NSA-24-004854
- OSTI ID:
- 4737224
- Report Number(s):
- AECL-3381; EXP-NRX-61015
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-70
- Country of Publication:
- Canada
- Language:
- English
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Related Subjects
Ceramics
& Other Materials-Ceramics & Cermets-Radiation Effects
N38700 -Reactor Components
Fuels & Accessories
FUEL CANS
FUEL ELEMENTS
METALLOGRAPHY
MICROSTRUCTURE
REACTOR CORE
SILICIDES
URANIUM COMPOUNDS
VOLUME
ZIRCALOY
NESDPS Office of Nuclear Energy Space and Defense Power Systems
URANIUM SILICIDES/radiation effects on Zircaloy-clad fuel elements of
in-pile
REACTOR FUEL ELEMENTS/radiation effects on structure and volume of Zircaloy-clad uranium silicide
in-pile