Design studies of helical-type fusion reactor FFHR

A. Sagara; O. Motojima; S. Imagawa; O. Mitarai; T. Noda; T. Uda; K. Watanabe; H. Yamanishi; H. Chikaraishi; A. Kohyama; H. Matsui; T. Muroga; N. Noda; N. Ohyabu; T. Satow; A. A. Shishkin; Dai Kai Sze; A. Suzuki; S. Tanaka; T. Terai; K. Yamazaki; J. Yamamoto

doi:10.1016/S0920-3796(97)00145-2

Design studies of helical-type fusion reactor FFHR

A. Sagara, O. Motojima, S. Imagawa, O. Mitarai, T. Noda, T. Uda, K. Watanabe, H. Yamanishi, H. Chikaraishi, A. Kohyama, H. Matsui, T. Muroga, N. Noda, N. Ohyabu, T. Satow, A. A. Shishkin, Dai Kai Sze, A. Suzuki, S. Tanaka, T. TeraiK. Yamazaki, J. Yamamoto

High Field Laboratory for Superconducting Materials

Research output: Contribution to journal › Article › peer-review

23 Citations (Scopus)

Abstract

The main feature of FFHR is force-free-like configuration of helical coils, which makes it possible to simplify the coil supporting structure and to use high magnetic field instead of high plasma beta. The other feature is the selection of molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety. Collaboration works based on the LHD project have made great progress in the reactor studies by focusing on engineering aspects of the high magnetic field and Flibe system design. Encouraging positive results are shown on ignition access, mechanical stress in coils supporting structures, improvement in the blanket system including materials selection and tritium recovery. Critical issues on fundamental safety analysis and maintainability of reactor components are also discussed, and many subjects are pointed out as future works.

Original language	English
Pages (from-to)	349-355
Number of pages	7
Journal	Fusion Engineering and Design
Volume	41
Issue number	1-4
DOIs	https://doi.org/10.1016/S0920-3796(97)00145-2
Publication status	Published - 1998 Sept 1

ASJC Scopus subject areas

Civil and Structural Engineering
Nuclear Energy and Engineering
Materials Science(all)
Mechanical Engineering

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10.1016/S0920-3796(97)00145-2

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Sagara, A., Motojima, O., Imagawa, S., Mitarai, O., Noda, T., Uda, T., Watanabe, K., Yamanishi, H., Chikaraishi, H., Kohyama, A., Matsui, H., Muroga, T., Noda, N., Ohyabu, N., Satow, T., Shishkin, A. A., Sze, D. K., Suzuki, A., Tanaka, S., ... Yamamoto, J. (1998). Design studies of helical-type fusion reactor FFHR. Fusion Engineering and Design, 41(1-4), 349-355. https://doi.org/10.1016/S0920-3796(97)00145-2

Sagara, A, Motojima, O, Imagawa, S, Mitarai, O, Noda, T, Uda, T, Watanabe, K, Yamanishi, H, Chikaraishi, H, Kohyama, A, Matsui, H, Muroga, T, Noda, N, Ohyabu, N, Satow, T, Shishkin, AA, Sze, DK, Suzuki, A, Tanaka, S, Terai, T, Yamazaki, K & Yamamoto, J 1998, 'Design studies of helical-type fusion reactor FFHR', Fusion Engineering and Design, vol. 41, no. 1-4, pp. 349-355. https://doi.org/10.1016/S0920-3796(97)00145-2

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abstract = "The main feature of FFHR is force-free-like configuration of helical coils, which makes it possible to simplify the coil supporting structure and to use high magnetic field instead of high plasma beta. The other feature is the selection of molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety. Collaboration works based on the LHD project have made great progress in the reactor studies by focusing on engineering aspects of the high magnetic field and Flibe system design. Encouraging positive results are shown on ignition access, mechanical stress in coils supporting structures, improvement in the blanket system including materials selection and tritium recovery. Critical issues on fundamental safety analysis and maintainability of reactor components are also discussed, and many subjects are pointed out as future works.",

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AU - Sagara, A.

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AU - Imagawa, S.

AU - Mitarai, O.

AU - Noda, T.

AU - Uda, T.

AU - Watanabe, K.

AU - Yamanishi, H.

AU - Chikaraishi, H.

AU - Kohyama, A.

AU - Matsui, H.

AU - Muroga, T.

AU - Noda, N.

AU - Ohyabu, N.

AU - Satow, T.

AU - Shishkin, A. A.

AU - Sze, Dai Kai

AU - Suzuki, A.

AU - Tanaka, S.

AU - Terai, T.

AU - Yamazaki, K.

AU - Yamamoto, J.

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AB - The main feature of FFHR is force-free-like configuration of helical coils, which makes it possible to simplify the coil supporting structure and to use high magnetic field instead of high plasma beta. The other feature is the selection of molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety. Collaboration works based on the LHD project have made great progress in the reactor studies by focusing on engineering aspects of the high magnetic field and Flibe system design. Encouraging positive results are shown on ignition access, mechanical stress in coils supporting structures, improvement in the blanket system including materials selection and tritium recovery. Critical issues on fundamental safety analysis and maintainability of reactor components are also discussed, and many subjects are pointed out as future works.

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Design studies of helical-type fusion reactor FFHR

Abstract

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