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The test assembly IFA-585 was designed to study in-reactor creep behaviour of Zircaloy cladding under variable stress conditions. The first loading of the assembly contained two short rods, one fabricated from pre-irradiated Zr-2 (the BWR rod) and the other from unirradiated Zr-4 (the PWR rod). The diameter gauge on the PWR rod ceased functioning after about 8500 hours, but that on the BWR rod continued to give results until the end of the first loading in October 1995.
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Keywords: compression, hoop stress, in-reactor creep, nuclear fuels, rod diameter, tension, zircaloy cladding.