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[1981_01]
Journal of Nuclear Materials, 99 (1981) 320-323
LETTER TO THE EDITORS - LETTRE AUX REDACTEURS
[1981_02]
International Journal of Applied Radiation and Isotopes, 32, (1981) 839-842
Tritium present in H2 or D2, 1.7 x 10-2 Ci/mol, was enriched using a hot-wire type vertical glass thermal-diffusion column with a gas reservoir on top. Four columns with different diameters (mmf), 8, 20, 30 and 41, were tested, while the temperature of a DC heated nichrome wire along the axis of each column was changed over a range from 200 to 450 °C. The maximum equilibrium separation factors in hydrogen and in deuterium were 17 and 4.5 respectively. The optimum diameters were calculated by a modification of Waldmann's equation which can be used for the separation using parallel plates.
[1981_03]
J. of Nuclear Science and Technology, 18 (1981) 15-20
The ability of trapping of tritium by silica and
alumina which were preliminarily doped with Li and irradiated with neutrons,
and the removal of tritium from these materials by ethylene were investigated.
Tritium formed in almina was not liberated by the elevation of temperature
to 350 °C. Tritium in silica was very slightly liberated at above 250 °C.
The trap of tritium by silica and alumina was explained in terms of the
exchange reaction of hydrogen of OH and the bounding of tritum with oxygen
produced freshly by the radiation damage. Tritium in silica was removed
in the form of T-ethylene at 300 °C and that in alumina at 100 °C. The doping
of 10% Ni to silica and alumina promoted the liberation of tritium gas
and the formation of T-compounds. The promotion of these reactions were
explained in terms of "reversing spillover".
Keywords: traps, tritium, removal silica, alumina, exchange
reaction, temperature dependence, ethylene, leaks