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核融合炉システム研究グループ

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更新日 2009-06-25 | 作成日 2008-07-03

研究発表 

炉工学

超伝導コイル

  1. T. Isono, N. Koizumi, K. Okuno et al., "Design study for superconducting coils for fusion DEMO plant at JAERI", Fusion. Eng. Design 81 (2006) 1257-1261.
  2. Y. Song, Q. Yang, S. Nishio, "Bucking analysis of TF coil inter leg for center solenoidless tokamak", Plasma Sci. Technol. 8 (2006) 468-472.
  3. Y. Song, S. Nishio, "A consideration on increasing current density in normal conducting toroidal field coil for spherical tokamak power plant", Plasma Sci. Technol. 7 (2005) 2731-2733.

ブランケット

  1. T. Hayashi, K. Tobita, S. Nishio et al., "Possibility of tritium self-sufficiency in low aspect ratio tokamak reactor with the outboard blanket only", Fusion Eng. Design 81 (2006) 2779-2784.
  2. A.R. Raffray, R. Jones, G. Aiello, M. Billone, L. Giancari, H. Golfier, A. Hasagawa, Y. Kato, A. Kohyama, S. Nishio, B. Riccardi, M.S. Tillack, "Design and material issues for high performance SiCf/SiC-based fusion power cores", Fusion Eng. Design 55(2001) 55-91.
  3. S. Nishio, S. Ueda, R. Kurihara et al., "Prototype fusion power reactor based on SiC/SiC composite material focusing on easy maintenance", Fusion Eng. Design 48 (2000) 271-279.

先進遮蔽材料

  1. K. Tobita, S. Konishi, S. Nishio et al., "Fusion reactor design towards radwaste minimum with advanced shield material", J. Plasma Fusion Res. 77 (2001) 1035-1039.
  2. T. Hayashi, K. Tobita, S. Nishio et al., "Neutronics assessment of advanced shield materials using metal hydride and borohydride for fusion reactors", Fusion Eng. Design 81(2006) 1285-1290.

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