Author/Authors :
Enoeda، نويسنده , , Mikio and Tanigawa، نويسنده , , Hisashi and Hirose، نويسنده , , Takanori and Nakajima، نويسنده , , Motoki and Sato، نويسنده , , Satoshi and Ochiai، نويسنده , , Kentaro and Konno، نويسنده , , Chikara and Kawamura، نويسنده , , Yoshinori and Hayashi، نويسنده , , Takumi and Yamanishi، نويسنده , , Toshihiko and Hoshino، نويسنده , , Tsuyoshi and Nakamichi، نويسنده , , Masaru and Tanigawa، نويسنده , , Hiroyasu and Nishi، نويسنده , , Hiroshi and Suzuki، نويسنده , , Satoshi and Ezato، نويسنده , , Koichiro and Seki، نويسنده , , Yohji and Yokoyama، نويسنده , , Kenji، نويسنده ,
Abstract :
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.
Keywords :
Tritium production test in FNS , Water cooled ceramic breeder (WCCB) TBM , Module fabrication technology , Li rich Li2TiO3 pebble , BeTi pebble
