Search

Abstract: At Tritium Process Laboratory (TPL) of Japan Atomic Energy Agency (JAEA), tritium technologies for a fusion reactor have been carried out up to date. The design studies of Air Detrtiation and Vent Detritiation System (ADS/VDS) of ITER have been carried out in JAEA as a contribution of Japan to ITER. For the tritium processing technologies, our efforts have been focused on the R&D of the tritium recovery system of ITER test blanket system. A ceramic proton conductor has been studied as an advanced blanket system. A series of fundamental studies on tritium safety technologies for ITER and for fusion DEMO plants has also been carried out. The main R&D activities in this field are the tritium behavior in a confinement and its barrier materials, monitoring, accountancy, detritiation and decontamination, etc. Especially, for the fundamental studies for a DEMO plants, a part of the studies will be carries out a new facility at Rokkasho in Aomori in the Broader Approach (BA) program in coming 10 years. For this purpose, a design study of the facility at Rokkasho has first been started. [Copyright &y& Elsevier]

Abstract: In order to establish the effective surface decontamination methods for the ITER construction materials, the so-called ‘soaking’ effect is important and more systematic data of tritium sorption and desorption for various materials are required under actually conditions. In order to obtain and summarize data on the amount of sorbed tritium on the various materials such as stainless steel (SS), acrylic resin, and epoxy paint, a series of tritiated water vapor exposure experiments have been carried out as a function of time. The materials were almost saturated with tritium within a period from several weeks to 1 month, and it was larger in the order of epoxy paint>acrylic resin=butyl rubber>SS304. The sorption rate and subsequent desorption rate for various materials were evaluated. [Copyright &y& Elsevier]