R&D status on Water Cooled Ceramic Breeder Blanket Technology

被引:20
|
作者
Enoeda, Mikio [1 ]
Tanigawa, Hisashi [1 ]
Hirose, Takanori [1 ]
Nakajima, Motoki [1 ]
Sato, Satoshi [1 ]
Ochiai, Kentaro [1 ]
Konno, Chikara [1 ]
Kawamura, Yoshinori [1 ]
Hayashi, Takumi [1 ]
Yamanishi, Toshihiko [1 ]
Hoshino, Tsuyoshi [1 ]
Nakamichi, Masaru [1 ]
Tanigawa, Hiroyasu [1 ]
Nishi, Hiroshi [1 ]
Suzuki, Satoshi [1 ]
Ezato, Koichiro [1 ]
Seki, Yohji [1 ]
Yokoyama, Kenji [1 ]
机构
[1] Japan Atom Energy Agcy, Naka, Ibaraki 3110193, Japan
关键词
Water Cooled Ceramic Breeder (WCCB); TBM; Module fabrication technology; Li rich Li2TiO3 pebble; BeTi pebble; Tritium production test in FNS; ITER; MODULE; FABRICATION; DESIGN; JAPAN;
D O I
10.1016/j.fusengdes.2014.01.035
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
Japan Atomic Energy Agency (JAEA) is performing the development of a Water Cooled Ceramic Breeder (WCCB) Test Blanket Module (TBM) as one of the most important steps toward DEMO blanket. Regarding the blanket module fabrication technology development using F82H, the fabrication of a real scale mockup of the back wall of TBM was completed. In the design activity of the TBM, electromagnetic analysis under plasma disruption events and thermo-mechanical analysis under steady state and transient state of tokamak operation have been performed and showed bright prospect toward design justification. Regarding the development of advanced breeder and multiplier pebbles for DEMO blanket, fabrication technology development of Li rich Li2TiO3 pebble and BeTi pebble was performed. Regarding the research activity on the evaluation of tritium generation performance, the evaluation of tritium production and recovery test using D-T neutron in the Fusion Neutronics Source (FNS) facility has been performed. This paper overviews the recent achievements of the development of the WCCB Blanket in JAEA. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码:1131 / 1136
页数:6
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