@article{oai:repo.qst.go.jp:00048657,
 author = {Tobita, Kenji and Asakura, Nobuyuki and Hiwatari, Ryoji and Someya, Youji and Utoh, Hiroyasu and Katayama, Kazunari and Nishimura, Arata and Sakamoto, Yoshiteru and Homma, Yuki and Kudou, Hironobu and Miyoshi, Yuya and Nakamura, Makoto and Tokunaga, Shunsuke and Aoki, Akira and 飛田 健次 and 朝倉 伸幸 and 日渡 良爾 and 染谷 洋二 and 宇藤 裕康 and 坂本 宜照 and 本間 裕貴 and 工藤 広信 and 三善 悠矢 and 中村 誠 and 徳永 晋介},
 issue = {4},
 journal = {Fusion Science and Technology},
 month = {Oct},
 note = {The Joint Special Design Team for Fusion DEMO was organized in 2015 to enhance Japan’s DEMO design activity and coordinate relevant research and development (R&D) toward DEMO. This paper presents the fundamental concept of DEMO and its key components with main arguments on DEMO design strategy. Superconducting magnet technology on toroidal field coils is based on the ITER scheme where a cable-in-conduit Nb3Sn conductor is inserted in the groove of a radial plate. Development of cryogenic steel with higher strength is a major challenge on the magnet. Divertor study has led to a baseline concept based on water-cooled single-null divertor assuming plasma detachment. Regarding breeding blanket, fundamental design study has been continued with focuses on tritium self-sufficiency, pressure tightness in case of in-box LOCA (loss of coolant accident) and material compatibility. An important finding on tritium permeation to the cooling water is also reported, indicating that the permeation to the cooling water is manageable with existing technology.},
 pages = {537--545},
 title = {Design strategy and recent design activity on Japan's DEMO},
 volume = {72},
 year = {2017}
}