研究報告6 - 1 総説 - Review
ゲッターによるトリチウムプロセッシング
Tritium Processing by Getter Materials
市村憲司、渡辺国昭
富山大学トリチウム科学センター
〒930 富山市五福3190
Kenji ICHIMURA, Kuniaki WATANABE
Tritium Research Center, Toyama University,Gofuku 3190, Toyama 930, JAPAN
(Received December 25, 1986)
Abstract
In the research and development of nuclear
fusion, getter materials have been widely applied to tritium processing
and/or handling techniques such as evacuation, recovery, storage, supply,
purification, enrichment, and separation. Some getters have been already
developed and applied to tritium handling as well as impurity control in
tokamaks. In this paper, we have described the present status of getter
applications: (1) plasma-vacuum conditioning, (2) storage-supply-recovery,
(3) purification, enrichment and separation, (4) removal and waste management.
The improvement of getter properties, however,
is required so as to apply them to a wider variety of the unit processes
of the tritium handling techniques. It has been pointed out that there
is a need for investigations on (1) the activation-deactivation mechanism,
(2) absorption-desorption properties and mechanism, (3) durability and/or
reactivity against impurity gases, (4) isotope effect and (5) alloying
effect.