Postirradiation Behavior of Naturally and Artificially Defected UO2Fuel Elements at 250°C in Air
Author:
Affiliation:
1. Atomic Energy of Canada Limited Research Company Chalk River Nuclear Laboratories, Chalk River, Ontario KOJ 1J0
2. Ontario Hydro, Central Nuclear Services, Toronto, Ontario MSG 1X6
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT85-A33586
Reference1 articles.
1. Postirradiation Behavior of UO2Fuel I: Elements at 220 to 250°C in Air
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1. Behavior of a Defective Nuclear Fuel Rod in Dry Storage Conditions Studied with a New Experimental Setup;Nuclear Technology;2008-08
2. A conceptual model for the fuel oxidation of defective fuel;Journal of Nuclear Materials;2007-06
3. Heavy Water Reactor Fuel Design and Performance;Encyclopedia of Materials: Science and Technology;2001
4. OXIDATION OF FUEL-ROD UNDER DRY STORAGE CONDITION;J NUCL SCI TECHNOL;1995
5. Oxidation of Fuel Rod under Dry Storage Condition;Journal of Nuclear Science and Technology;1995-04
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