نتایج اخیر فعالیت های R & D در فن آوری های تریتیوم برای راکتور ITER و راکتور فیوژن در TPL در JAEA
|کد مقاله||سال انتشار||مقاله انگلیسی||ترجمه فارسی||تعداد کلمات|
|10271||2008||5 صفحه PDF||سفارش دهید||محاسبه نشده|
Publisher : Elsevier - Science Direct (الزویر - ساینس دایرکت)
Journal : Fusion Engineering and Design, Volume 83, Issues 10–12, December 2008, Pages 1359–1363
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.
The facility of Tritium Process Laboratory (TPL) in Japan Atomic Energy Agency (JAEA) is an unique laboratory for fusion technology where can handle more than 1 g of tritium in Japan . Maximum storage amount of tritium is licensed 22.2 PBq. Now, 13.7 PBq of tritium (at March 2007) is stored in the radiological controlled area of TPL and used safely in a multiple confinement system for the following R&D. The recent R&D activities in TPL are mainly (1) ITER ADS/VDS design, (2) investigation of tritium recovery system from breeding blanket, and (3) fundamental studies on tritium safety enhancement. In this paper, the above recent activities on tritium technologies at TPL in JAEA are summarized for ITER and future fusion demo reactor. Recently, it has been decided that a part of fundamental studies for a DEMO plant would be carried out at a new facility at Rokkasho in Aomori in the Broader Approach (BA) program. The present status of the BA program for tritium technologies is also reported in this paper.
نتیجه گیری انگلیسی
AT TPL, tritium technologies for the fusion reactors have been carried out since 1988 with more than 30 g of tritium. It has been a set of valuable results to obtain the experience of TPL operation as well as the fundamental data with tritium. Recent our missions are (1) the design of tritium removal systems of ITER and a series of R&D related to this task; (2) the R&D works for ITER–TBM; and the fundamental studies for ITER and DEMO plants. Experimental data for the tritium fundamental behaviors as well as the experience of tritium safety operation has been accumulated. Among them, our effort is focused on the design of the tritium removal systems of ITER as the most urgent mission. We have carried out the design work to support ITER activities with close discussion with an ITER tritium team. A part of the R&D activities for DEMO plant will be carried out at Rokkasho under the BA program. The design of the tritium facility at Rokkasho has also been started as another recent urgent mission.