Overview of the TBM R&D activities in Japan

被引:16
作者
Akiba, Masato
Enoeda, Mikio [1 ]
Tanaka, Satoru [2 ]
机构
[1] Japan Atom Energy Agcy, Blanket Technol Grp, Fus Res & Dev Directorate, Div Fus Energy Technol, Naka, Ibaraki 3110193, Japan
[2] Univ Tokyo, Tokyo, Japan
关键词
Water cooled ceramic breeder TBM; Blanket module fabrication technology; F82H; High temperature Li-Pb blanket; Li/V blanket; Flibe blanket; WATER; DESIGN; PROGRESS; STEEL;
D O I
10.1016/j.fusengdes.2010.05.029
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
In Japan, development of Water Cooled Ceramic Breeder (WCCB) blanket is being performed as the primary candidate of Test Blanket Module (TBM) toward DEMO. Also development of high temperature Li-Pb blanket, Li/V blanket and Flibe blanket are being performed toward the advanced DEMO blanket. Regarding the WCCB TBM development, real scale First Wall (RN) was fabricated using Reduced Activation Ferritic Martensitic Steel (RAFMS), F82H and successfully tested by heat flux equivalent to ITER TBM condition, 0.5 MW/m(2), 80 cycles with the same coolant condition as DEMO. Also, real scale Side Wall (SW) and real scale breeder pebble bed structure are successfully fabricated. Furthermore, asemmbling test of the real scale FW plate mockup and SW plate mockup was performed to clarify the welding condition to form TBM box structure. All key technologies of blanket module fabrication has been addressed and almost achieved toward TBM. Regarding the development of liquid breeder blankets, all key technologies, such as, material compatibility and mass transfer, tritium recovery performance, insulation coating development, were covered, by using elementary experiments to convection loops of Li-Pb. Li and Flibe. High temperature heat exchange test up to 900 degrees C has been initiated by using Li-Pb test loop. (C) 2010 Elsevier B.V. All rights reserved.
引用
收藏
页码:1766 / 1771
页数:6
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