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Nuclear Technology Volume 68, 1985 - Issue 1
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Technical Paper

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

Ian J. HastingsAtomic Energy of Canada Limited–Research Company Chalk River Nuclear Laboratories, Chalk River, Ontario KOJ 1J0, Canada
,
Elio MizzanAtomic Energy of Canada Limited–Research Company Chalk River Nuclear Laboratories, Chalk River, Ontario KOJ 1J0, Canada
,
Alan M. RossAtomic Energy of Canada Limited–Research Company Chalk River Nuclear Laboratories, Chalk River, Ontario KOJ 1J0, Canada
,
John R. KelmAtomic Energy of Canada Limited–Research Company Chalk River Nuclear Laboratories, Chalk River, Ontario KOJ 1J0, Canada
,
Real J. ChenierAtomic Energy of Canada Limited–Research Company Chalk River Nuclear Laboratories, Chalk River, Ontario KOJ 1J0, Canada
,
D. H. RoseAtomic Energy of Canada Limited–Research Company Chalk River Nuclear Laboratories, Chalk River, Ontario KOJ 1J0, Canada
&
J. NovakOntario Hydro, Central Nuclear Services Toronto, Ontario M5G 1X6 Canada
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Pages 40-47 | Published online: 12 May 2017

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Bernd Grambow, R. S. Forsyth, Lars O. Werme & Jordi Bruno. (1990) Fission Product Release from Spent UO2 Fuel Under Uranium-Saturated Oxic Conditions. Nuclear Technology 92:2, pages 204-213.
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Robert E. Woodley, Robert E. Einziger & H. Craig Buchanan. (1989) Measurement of the Oxidation of Spent Fuel Between 140 and 225°C. Nuclear Technology 85:1, pages 74-88.
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Ian J. Hastings, David R. McCracken, Elio Mizzan, Roger D. Barrand, John R. Kelm, Ken E. Nash & J. Novak. (1985) Postirradiation Dimensional Stability and Fission Product Behavior of Deliberately Defected UO2 Fuel at 200 and 400°C. Nuclear Technology 70:2, pages 268-273.
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