Postirradiation examination and evaluation of Fort St. Vrain fuel element 1-0743
Fort St. Vrain (FSV) fuel element 1-0743 was irradiated in core location 17.04.F.06 from July 3, 1976 until February 1, 1979. The element experienced an average fast neutron exposure of about 0.95 x 10/sup 25/ n/m/sup 2/ (E > 29 fJ)/sub HTGR/, a time-and-volume-averaged fuel temperature in the vicinity of 680/sup 0/C, fissile and fertile particle burnups of approximately 6.2% and 0.3%, respectively, and a total burnup of 12,210 MWd/tonne. The postirradiation examination revealed that the element was in excellent condition. No cracks were observed on any of the element surfaces. The structural integrity of the fuel rods was good. No evidence of mechanical interaction between the fuel rods and fuel body was observed. Calculated irradiation parameters obtained with HTGR design codes were compared with measured data. Radial and axial power distributions, irradiation temperatures, neutron fluences, and fuel burnups were in good agreement with measurements. Calculated fuel rod strains were about a factor of three greater than were observed.
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- DOE Contract Number:
- AT03-76ET35301
- OSTI ID:
- 6350918
- Report Number(s):
- GA-A-16258; ON: DE81028505
- Country of Publication:
- United States
- Language:
- English
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ACTINIDE COMPOUNDS
BURNUP
CARBIDES
CARBON COMPOUNDS
COATED FUEL PARTICLES
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
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PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
POWER DISTRIBUTION
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RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
TESTING
THORIUM CARBIDES
THORIUM COMPOUNDS
URANIUM CARBIDES
URANIUM COMPOUNDS
VRAIN REACTOR