Proposal to irradiate zircaloy-clad fuel elements containing uo2 pellets of different densities

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Fabrication details for five zircaloy-4 clad fuel elements containing low density uo2 fuel pellets for irradiation in the NRU reactor

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A proposal to irradiate fuel elements containing unirradiated uo2 pellets clad in zirconium alloy tubes previously irradiated to 8 x 10 sup(20) n/cm2

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Fabrication details for zircaloy-clad fuel elements containing high and low density sintered uo2 pellets

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Irradiation of zircaloy clad uo2 fuel elements containing discs of different materials and geometries to study their efficiency in cooling the fuel pellet

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Proposal to irradiate zircaloy-clad uo2 pellets of low density in the NRU demountable bundle

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Addendum to the proposal to irradiate fuel elements containing unirradiated uo2 pellets clad in zirconium alloy tubes previously irradiated to 8 x 10 sup(24) n/m2

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A proposal to irradiate zircaloy-clad elementscontaining uo2 fuel pellets ground to various surface roughnesses

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Removal of Irradiated UO2 Fuel from the Cladding by Controlled Oxidation

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Effects of High Burnup on Zircaloy-clad, Bulk UO2, Plate Fuel Element Samples

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