STUDIES ON TRITIUM INTERACTIONS WITH PLASMA FACING MATERIAL AT THE TRITIUM PROCESS LABORATORY OF JAERI

摘要

From a view point of safety evaluation of fusion reactors, estimation of permeation amounts of tritium to coolant through plasma facing components (PFC) is one of the critical issues. Moreover, estimation of tritium inventory in plasma facing materials is important subject not only for safety, but also for tritium accountability in fusion reactors. In TPL/JAERI, to simulate tritium permeation behavior in PFC materials, such as Be and W, implantation driven permeation (IDP) behavior have been investigated for deuterium, as well as the other pure metals. Furthermore, IDP study using pure tritium ion beam was just started to check the isotope effect. On the other hand, to obtain tritium inventory information in PFC materials, such as Be, W and CFC, thermal desorption behavior have also been investigated after various hydrogen beam irradiation source. Moreover, tritium micro-autoradiography investigation was just started to investigate depth profile of tritium in the bulk of PFC materials. In this paper, we summarize recent topics on tritium permeation and retention study in TPL/JAERI.