Design and development of the Flibe blanket for helical-type fusion reactor FFHR

A. Sagara; H. Yamanishi; S. Imagawa; T. Muroga; T. Uda; T. Noda; S. Takahashi; K. Fukumoto; T. Yamamoto; H. Matsui; A. Kohyama; H. Hasizume; S. Toda; A. Shimizu; A. Suzuki; Y. Hosoya; S. Tanaka; T. Terai; Dai Kai Sze; O. Motojima

doi:10.1016/S0920-3796(00)00360-4

Design and development of the Flibe blanket for helical-type fusion reactor FFHR

A. Sagara, H. Yamanishi, S. Imagawa, T. Muroga, T. Uda, T. Noda, S. Takahashi, K. Fukumoto, T. Yamamoto, H. Matsui, A. Kohyama, H. Hasizume, S. Toda, A. Shimizu, A. Suzuki, Y. Hosoya, S. Tanaka, T. Terai, Dai Kai Sze, O. Motojima

ENG - Quantum Science and Energy Engineering

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

59 Citations (Scopus)

Abstract

Blanket design is in progress in helical-type compact reactor FFHR-2. A localized blanket concept is proposed by selecting molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety: low tritium solubility, low reactivity with air and water, low pressure operation, and low MHD resistance which is compatible with the high magnetic field design in force-free helical reactor (FFHR). Numerical results are presented on nuclear analyzes using the MCNP-4B code, on thermal and stress analyzes using the ABAQUS code, and heat exchange efficiency from Flibe to He. R&D programs on Flibe engineering are also in progress in material dipping-tests and in construction of molten salt loop. Preliminary results in these experiments are also presented.

Original language	English
Pages (from-to)	661-666
Number of pages	6
Journal	Fusion Engineering and Design
Volume	49-50
DOIs	https://doi.org/10.1016/S0920-3796(00)00360-4
Publication status	Published - 2000 Nov

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Sagara, A., Yamanishi, H., Imagawa, S., Muroga, T., Uda, T., Noda, T., Takahashi, S., Fukumoto, K., Yamamoto, T., Matsui, H., Kohyama, A., Hasizume, H., Toda, S., Shimizu, A., Suzuki, A., Hosoya, Y., Tanaka, S., Terai, T., Sze, D. K., & Motojima, O. (2000). Design and development of the Flibe blanket for helical-type fusion reactor FFHR. Fusion Engineering and Design, 49-50, 661-666. https://doi.org/10.1016/S0920-3796(00)00360-4

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title = "Design and development of the Flibe blanket for helical-type fusion reactor FFHR",

abstract = "Blanket design is in progress in helical-type compact reactor FFHR-2. A localized blanket concept is proposed by selecting molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety: low tritium solubility, low reactivity with air and water, low pressure operation, and low MHD resistance which is compatible with the high magnetic field design in force-free helical reactor (FFHR). Numerical results are presented on nuclear analyzes using the MCNP-4B code, on thermal and stress analyzes using the ABAQUS code, and heat exchange efficiency from Flibe to He. R&D programs on Flibe engineering are also in progress in material dipping-tests and in construction of molten salt loop. Preliminary results in these experiments are also presented.",

author = "A. Sagara and H. Yamanishi and S. Imagawa and T. Muroga and T. Uda and T. Noda and S. Takahashi and K. Fukumoto and T. Yamamoto and H. Matsui and A. Kohyama and H. Hasizume and S. Toda and A. Shimizu and A. Suzuki and Y. Hosoya and S. Tanaka and T. Terai and Sze, {Dai Kai} and O. Motojima",

year = "2000",

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doi = "10.1016/S0920-3796(00)00360-4",

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Sagara, A, Yamanishi, H, Imagawa, S, Muroga, T, Uda, T, Noda, T, Takahashi, S, Fukumoto, K, Yamamoto, T, Matsui, H, Kohyama, A, Hasizume, H, Toda, S, Shimizu, A, Suzuki, A, Hosoya, Y, Tanaka, S, Terai, T, Sze, DK & Motojima, O 2000, 'Design and development of the Flibe blanket for helical-type fusion reactor FFHR', Fusion Engineering and Design, vol. 49-50, pp. 661-666. https://doi.org/10.1016/S0920-3796(00)00360-4

TY - JOUR

T1 - Design and development of the Flibe blanket for helical-type fusion reactor FFHR

AU - Sagara, A.

AU - Yamanishi, H.

AU - Imagawa, S.

AU - Muroga, T.

AU - Uda, T.

AU - Noda, T.

AU - Takahashi, S.

AU - Fukumoto, K.

AU - Yamamoto, T.

AU - Matsui, H.

AU - Kohyama, A.

AU - Hasizume, H.

AU - Toda, S.

AU - Shimizu, A.

AU - Suzuki, A.

AU - Hosoya, Y.

AU - Tanaka, S.

AU - Terai, T.

AU - Sze, Dai Kai

AU - Motojima, O.

PY - 2000/11

Y1 - 2000/11

N2 - Blanket design is in progress in helical-type compact reactor FFHR-2. A localized blanket concept is proposed by selecting molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety: low tritium solubility, low reactivity with air and water, low pressure operation, and low MHD resistance which is compatible with the high magnetic field design in force-free helical reactor (FFHR). Numerical results are presented on nuclear analyzes using the MCNP-4B code, on thermal and stress analyzes using the ABAQUS code, and heat exchange efficiency from Flibe to He. R&D programs on Flibe engineering are also in progress in material dipping-tests and in construction of molten salt loop. Preliminary results in these experiments are also presented.

AB - Blanket design is in progress in helical-type compact reactor FFHR-2. A localized blanket concept is proposed by selecting molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety: low tritium solubility, low reactivity with air and water, low pressure operation, and low MHD resistance which is compatible with the high magnetic field design in force-free helical reactor (FFHR). Numerical results are presented on nuclear analyzes using the MCNP-4B code, on thermal and stress analyzes using the ABAQUS code, and heat exchange efficiency from Flibe to He. R&D programs on Flibe engineering are also in progress in material dipping-tests and in construction of molten salt loop. Preliminary results in these experiments are also presented.

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SN - 0920-3796

VL - 49-50

SP - 661

EP - 666

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

ER -

Design and development of the Flibe blanket for helical-type fusion reactor FFHR

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