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Compact DEMO, SlimCS: design progress and issues

2009; IOP Publishing; Volume: 49; Issue: 7 Linguagem: Inglês

10.1088/0029-5515/49/7/075029

1741-4326

K. Tobita, Shuichi Nishio, Mikio Enoeda, H. Kawashima, G. Kurita, Hiroyasu Tanigawa, H. Nakamura, M. Honda, A. Saito, Sennosuke SATO, T. Hayashi, N. Asakura, S. Sakurai, T. Nishitani, T. Ozeki, Masami Ando, K. Ezato, K. Hamamatsu, Takanori Hirose, Tsuyoshi Hoshino, S. Ide, Takashi Inoue, T. Isono, C. Liu, Satoshi Kakudate, Yoshihito Kawamura, Tatsuya Mori, Masaru Nakamichi, Hiroshi Nishi, Takashi Nozawa, K. Ochiai, Hideaki Ogiwara, N. Oyama, K. Sakamoto, Y. Sakamoto, Yohji Seki, Yusuke Shibama, K. Shimizu, S. Suzuki, Koji Takahashi, Hiroyasu Tanigawa, Daigo Tsuru, T. Yamanishi, T. Yoshida,

Nuclear Materials and Properties

The design progress in a compact low aspect ratio (low A ) DEMO reactor, ‘SlimCS’, and its design issues are reported. The design study focused mainly on the torus configuration including the blanket, divertor, materials and maintenance scheme. For continuity with the Japanese ITER-TBM, the blanket is based on a water-cooled solid breeder blanket. For vertical stability of the elongated plasma and high beta access, the blanket is segmented into replaceable and permanent blankets and a sector-wide conducting shell is arranged inbetween these blankets. A numerical calculation indicates that fuel self-sufficiency can be satisfied when the blanket interior is ideally fabricated. An allowable heat load to the divertor plate should be 8 MW m −2 or lower, which can be a critical constraint for determining a handling power of DEMO.