Preliminary Study on Production of Xenon-133 from Neutron-Irradiated Uranium Metal and Oxides by Oxidation

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A method was developed for recovering the fission product 133Xe from several kinds of reactor-irradiated U targets, including Al-U alloy, metallic U, and uranium oxides. In order to observe the release of 133Xe from U compounds at high temperatures, irradiated targets were heated at 5001, 000°C in vacuum or under gas flow. The liberated 133Xe was trapped on charcoal beds, and the release rate of 133Xe from the compounds was determined by measuring the activity accumulating in the traps. More than 90% of the 133Xe was liberated from the alloy upon melting and from metal and uranium oxide upon oxidation. The isolated Xe was purified by a system embodying cold traps and cryogenic distillation. The final products were sealed in ampoules. They proved to possess radiochemical purity exceeding 99.9 %, and less than 1μl/ampoule (1 ml) of non-radioactive gaseous contaminants.
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