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Post-irradiation behavior of UO/sub 2/ fuel 1: Elements at 220 to 250/sup 0/C in air

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:6715530

Irradiated UO/sub 2/ fuel elements with and without deliberately induced 0.8-mm-diam defects were heated in air at 220, 230, and 250/sup 0/C for times up to 685 h. Pretest burnup was typically 190 MW X h/kg U (7600 MW X d/TeU) at a maximum linear power of 45 kW/m; cooling times were 1 to 3 yr. In fuel elements with six defects, diametral increases in excess of 5% and sheath splitting occurred after about200 h at 250/sup 0/C, consistent with oxidation to U/sub 3/O/sub 8/. There was a maximum 2% increase in elements with one defect at 250/sup 0/C, but no change in an irradiated but undefected control. Dimensional increases in defected elements at 220 and 230/sup 0/C were typically <1% for times in excess of 600 h, consistent with oxidation primarily to nonswelling U/sub 3/O/sub 7/. The rate of weight change at 230 and 250/sup 0/C was up to 50 times greater in defected irradiated elements, compared with that for defected unirradiated elements. There was no significant effect of power history or cooling time in the elements studied.

Research Organization:
Atomic Energy of Canada Limited--Research Company Chalk River Nuclear Laboratories, Chalk River, Ontario
OSTI ID:
6715530
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 63:2; ISSN NUTYB
Country of Publication:
United States
Language:
English