Design strategy and recent design activity on Japan's DEMO

Kenji Tobita, Nobuyuki Asakura, Ryoji Hiwatari, Youji Someya, Hiroyasu Utoh, Kazunari Katayama, Arata Nishimura, Yoshiteru Sakamoto, Yuki Homma, Hironobu Kudo, Yuya Miyoshi, Makoto Nakamura, Shunsuke Tokunaga, Akira Aoki

研究成果: Contribution to journalArticle査読

26 被引用数 (Scopus)

抄録

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 cablein-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 watercooled 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.

本文言語英語
ページ(範囲)537-545
ページ数9
ジャーナルFusion Science and Technology
72
4
DOI
出版ステータス出版済み - 11 2017

All Science Journal Classification (ASJC) codes

  • 土木構造工学
  • 核物理学および高エネルギー物理学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 機械工学

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