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Technical Paper

Postirradiation Behavior of UO2 Fuel II: Fragments at 175 to 275°C in Air

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Pages 40-47 | Published online: 12 May 2017

References

  • I. J. HASTINGS and J. NOVAK, “Low Temperature Oxidation of Irradiated UO2 Fuel,” presented at 85th Annual Meeting, American Ceramic Society, Chicago, Illinois, April 24-27, 1983.
  • J. NOVAK, I. J. HASTINGS, E. MIZZAN and R. CHENIER, “Postirradiation Behavior of UO2 Fuel I: Elements at 220 to 250°C in Air,” Nucl. Technol., 63, 254 (1983).
  • G. D. WHITE, E. R. GILBERT and A. B. JOHNSON, Jr., “Oxidation of UO2 at 150 to 350°C,” Proc. Nuclear Regulatory Commission Workshop Spent Fuel/Cladding Reaction During Dry Storage, Gaithersburg, Maryland, August 17-18, 1983, NUREG/CP-0049, p. 102 plus Appendix F-l (1984).
  • K. A. SIMPSON and P. WOOD, “Uranium Dioxide Fuel Oxidation in Air Below 350°C”, Proc. Nuclear Regulatory Commission Workshop Spent Fuel/Cladding Reaction During Dry Storage, Gaithersburg, Maryland, August 17-18, 1983, NUREG/CP-0049, p. 70 plus Appendix D-l (1984).
  • P. TAYLOR, E. BURGESS and O. OWEN, “An X-Ray Diffraction Study of the Formation of Beta-UO233 on UO2 Pellet Surfaces in Air at 229-275°C,” J. Nucl. Mater., 88, 153 (1980).
  • D. G. BOASE and T. T. VANDERGRAAF, “The Canadian Spent Fuel Storage Canister: Some Material Aspects,” Nucl. Technol., 32, 60 (1977).

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