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Development of the Water Cooled Ceramic Breeder Test Blanket Module in Japan
Authors:Mikio Enoeda  Hisashi Tanigawa  Takanori Hirose  Satoshi Suzuki  Kentaro Ochiai  Chikara Konno  Yoshinori Kawamura  Toshihiko Yamanishi  Tsuyoshi Hoshino  Masaru Nakamichi  Hiroyasu Tanigawa  Koichiro Ezato  Yohji Seki  Akira Yoshikawa  Daigo Tsuru  Masato Akiba
Affiliation:Japan Atomic Energy Agency, Naka-shi, Ibaraki-ken 311-0193, Japan
Abstract:The development of a Water Cooled Ceramic Breeder (WCCB) Test Blanket Module (TBM) is being performed as one of the most important steps toward DEMO blanket in Japan. For the TBM testing and evaluation toward DEMO blanket, the module fabrication technology development by a candidate structural material, reduced activation martensitic/ferritic steel, F82H, is one of the most critical items from the viewpoint of realization of TBM testing in ITER. In Japan, fabrication of a real scale first wall, side walls, a breeder pebble bed box and assembling of the first wall and side walls have succeeded. Recently, the real scale partial mockup of the back wall was fabricated. The fabrication procedure of the back wall, whose thickness is up to 90 mm, was confirmed toward the fabrication of the real scale back wall by F82H. Important key technologies are almost clarified for the fabrication of the real scale TBM module mockup. From the view point of testing and evaluation, development of the technology of the blanket tritium recovery, development of advanced breeder and multiplier pebbles and the development of the blanket neutronics measurement technology are also performed. Also, tritium production and recovery test using D-T neutron in the Fusion Neutronics Source (FNS) facility has been started as the verification test of tritium production performance. This paper overviews the recent achievements of the development of the WCCB TBM in Japan.
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