A proposal to irradiate u-si-al alloy fuel clad in zr-1.2 wt percent cr-0.1 wt percent fe and zr-2.5 wt percent nb at 500 degrees c sheath temperatures in superheated steam

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Proposal to irradiate u-si-al alloys clad in zr-2.5 wt percent nb in pressurized water

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A proposal to irradiate deflected uo2 fuel elements clad in zr-2.5 wt percent nb and zr-1.2 wt perrcent cr-0.1 wt percent fe in superheated steam

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A proposal for the irradiation of an instrumented trefoil containing 304l, zr-cr-fe and zr-2.5 wt percent nb clad fuel at up to 500 degrees c sheath temperature in dryout in x-4

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A proposal to irradiate zr-1 wt percent nb clad fuel elements to test the low power soak-power boost behaviour and to produce specimens for an evaluation of the stress corrosion cracking resistance of the alloy in iodine vapour

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A proposal to irradiate a u-si-a1 fuel rod containing peripheral voidage and clad in a defected zr-2.5 wt percent nb sheath

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Proposal to irradiate enriched u-si-al in NPD-phase 3 fuel clad in zr-2.5 wt percent nb

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A proposal to irradiate zr-2.5 wt percent nb clad u-si-a1 fuel rods containing peripheral voidage

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A proposal to irradiate zr-2.5 wt percent nb clad u-si-a1 fuel rods containing 6 or 7 longitudinal slots as peripheral voidage

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Addendum to the proposal to irradiate u-si-a1 fuel elements containing a surface layer of rapidly corroding fuel and a graphite layer between the fuel and the defected zr-2.5 wt percent nb sheath

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