Recent results of R&D activities on tritium technologies for ITER and fusion reactors at TPL of JAEA
Recent results of R&D activities on tritium technologies for ITER and fusion reactors at TPL of JAEA
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R的最新结果
DOI：
10.1016/j.fusengdes.2008.08.010
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发表时间：
2008
影响因子：
1.7
通讯作者：
M. Yamada
中科院分区：
文献类型：
--
作者：
T. Yamanishi;T. Hayashi;W. Shu;Y. Kawamura;H. Nakamura;Y. Iwai;Kazuhiro Kobayashi;K. Isobe;T. Arita;S. Hoshi;Takumi Suzuki;M. Yamada
在日本原子能机构（JAEA）的氚工艺实验室（TPL），用于聚变反应堆的氚技术已经被实施到目前为止。作为日本对ITER的贡献，日本原子能机构开展了ITER空气除氚和排气除氚系统（ADS/VDS）的设计研究。在氚处理技术方面，我们致力于ITER实验包层系统氚回收系统的研发。陶瓷质子导体作为一种先进的包层系统进行了研究。还开展了一系列关于ITER和聚变演示装置氚安全技术的基础研究。该领域的主要研发活动是氚在密封中的行为及其屏障材料、监测、计算、净化和去污等。特别是对于DEMO工厂的基础研究，其中一部分研究将在未来10年的更广泛方法（BA）计划中在青森的六所新设施中进行。为此目的，已首先开始对六所村的设施进行设计研究。
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.