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U.S. Department of Energy
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Postirradiation examinations of the BG-9 element. [GCFR type reactors]

Technical Report ·
OSTI ID:7310532

Postirradiation examinations were performed on the GB-9 element irradiated in the Oak Ridge Reactor. This vented fuel element was irradiated to a peak burnup of 54,000 MWd/MT at a peak power rating of 14.8 kW/ft and a maximum outside surface temperature of 685 +- 15/sup 0/C. The maximum diametral increase of the element was 0.2% ..delta..D/D. Volatile fission products migrated to the ends of the fuel column but had not been transported beyond the blanket region of the element. Fission-product attack of the cladding was found to a depth of 4.4 mils adjacent to the mixed-oxide fuel. The maximum fission-product attack (approximately 6.2 mils) was found adjacent to slightly hyperstoichiometric UO/sub 2/ pellets at the upper end of the fuel column. The more severe attack in this region has been attributed to the higher oxygen potential adjacent to the hyperstoichiometric UO/sub 2/ fuel. A stress-rupture test was performed on a section of the element. The cladding ruptured after 30 min at 700/sup 0/C and approximately 21,500-psi loop stress, resulting in a diametral strain of 1.6%.

Research Organization:
Argonne National Lab., IL (USA)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
7310532
Report Number(s):
ANL-8067
Country of Publication:
United States
Language:
English