Abstract
The release of crude tritium gas from neutron-irradiated LiAl alloy, and the following purification and the trapping of the gas have been preliminary studied to obtain information necessary for the development of tritium technology.The percentages of the fractions of H2 (T) and H2O (T) occupying about 99% among gaseous species (T) released were largely influenced by pre-irradiation treatment of the alloy and especially by heating temperature of the irradiated alloy. In the isothermal heating at 850°C, about 95% of tritium was released as H2 (T) . For obtaining all of tritium as H2 (T), the fraction of H2O (T) was successfully converted to H2 (T) with U turnings at 800°C. Hydrogen (T) could be effectively trapped in a pulverized U Better at room temperature.
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