Abstract
Tritium research activities at universities in Japan are reviewed. The typical experiments of in-situ tritium recovery from fission or fusion neutron-irradiated lithium compounds show that the tritium release are enhanced by 1 per cent H2 gas addition to the He sweep gas. Permeation, solubility, and diffusion coefficient of tritium in various organic and metallic materials are surveyed and are listed in Table 1 for inorganic materials.
The fundamental works have been made extensively on the enrichment of used fusion fuel and propose the optimized operating conditions for hot wire column with a cold or a cryogenic wall. An effective removal of tritium from contaminated ceramic multiplier by the photon irradiation are elaborated more fully in the reference cited.
