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Notley, M.J.F.; Fitzsimmons, W.D.C.
Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)1962
Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)1962
AbstractAbstract
[en] Specimens of UO2 sheathed in 0.51 mm aluminum or 0.25 mm or 0.66 mm stainless steel were irradiated in the Hydraulic Rabbit of NRX to study sheath deformations. Axial expansions were in accordance with a model in which the UO2 is assumed to have a plastic core, sheath expansion being caused by expansion of the innermost non-plastic ring of UO2. It was shown that the weaker the sheath the greater is the axial expansion. Diametral expansions increased with increasing specimen heat rating, increasing rapidly at ratings corresponding to the onset of central melting. Volume expansions of the Hydraulic Rabbit specimens were approximately the same as volume expansions of elements irradiated in pressurized water loops. (author)
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Dec 1962; 19 p; CRFD--1119; 12 refs., 4 tabs., 3 figs.
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Report
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ACTINIDE COMPOUNDS, ALLOYS, CARBON ADDITIONS, CHALCOGENIDES, COOLING SYSTEMS, ELEMENTS, ENERGY SYSTEMS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MATERIALS TESTING REACTORS, METALS, NATURAL URANIUM REACTORS, OXIDES, OXYGEN COMPOUNDS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, STEELS, TANK TYPE REACTORS, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, URANIUM COMPOUNDS, URANIUM OXIDES
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