Recent results of R&D activities on tritium technologies for ITER and fusion reactors at TPL of JAEA

被引:4
|
作者
Yamanishi, T. [1 ]
Hayashi, T. [1 ]
Shu, W. [1 ]
Kawamura, Y. [1 ]
Nakamura, H. [1 ]
Iwai, Y. [1 ]
Kobayashi, K. [1 ]
Isobe, K. [1 ]
Arita, T. [1 ]
Hoshi, S. [1 ]
Suzuki, T. [1 ]
Yamada, M. [1 ]
机构
[1] Japan Atom Energy Agcy, Tritium Technol Grp, Toka Mura, Ibaraki 3191195, Japan
关键词
Tritium; Fusion; ITER; TPL; JAEA; Broader Approach;
D O I
10.1016/j.fusengdes.2008.08.010
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
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. (c) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码:1359 / 1363
页数:5
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