Engineering design and control scenario for steady-state high-beta operation in National Centralized Tokamak

K. Tsuchiya; M. Akiba; H. Azechi; T. Fujii; T. Fujita; M. Fujiwara; K. Hamamatsu; H. Hashizume; N. Hayashi; H. Horiike; N. Hosogane; M. Ichimura; K. Ida; Y. Ikeda; T. Imai; N. Inoue; S. Ishida; S. Itoh; Y. Kamada; H. Kawashima; M. Kikuchi; A. Kimura; K. Kizu; H. Kubo; Y. Kudo; K. Kurihara; G. Kurita; M. Kuriyama; K. Masaki; M. Matsukawa; M. Matsuoka; Y. Miura; Y. M. Miura; N. Miya; A. Morioka; K. Nakamura; H. Ninomiya; A. Nishimura; K. Okano; K. Okuno; A. Sagara; M. Sakamoto; S. Sakurai; K. Sato; R. Shimada; A. Shimizu; T. Suzuki; H. Takahashi; Y. Takase; M. Takechi; H. Tamai; S. Tanaka; H. Tsutsui; Y. Uesugi; K. Yatsu; N. Yoshida

doi:10.1016/j.fusengdes.2005.08.066

Engineering design and control scenario for steady-state high-beta operation in National Centralized Tokamak

K. Tsuchiya, M. Akiba, H. Azechi, T. Fujii, T. Fujita, M. Fujiwara, K. Hamamatsu, H. Hashizume, N. Hayashi, H. Horiike, N. Hosogane, M. Ichimura, K. Ida, Y. Ikeda, T. Imai, N. Inoue, S. Ishida, S. Itoh, Y. Kamada, H. KawashimaM. Kikuchi, A. Kimura, K. Kizu, H. Kubo, Y. Kudo, K. Kurihara, G. Kurita, M. Kuriyama, K. Masaki, M. Matsukawa, M. Matsuoka, Y. Miura, Y. M. Miura, N. Miya, A. Morioka, K. Nakamura, H. Ninomiya, A. Nishimura, K. Okano, K. Okuno, A. Sagara, M. Sakamoto, S. Sakurai, K. Sato, R. Shimada, A. Shimizu, T. Suzuki, H. Takahashi, Y. Takase, M. Takechi, H. Tamai, S. Tanaka, H. Tsutsui, Y. Uesugi, K. Yatsu, N. Yoshida

研究成果: Conference article › 査読

1 被引用数 (Scopus)

抄録

The mission of the National Centralized Tokamak (NCT) is to establish high-beta steady-state plasma operation for DEMO and to contribute to ITER. Plasma performance with high-beta conditions is discussed. It is found that near break-even class plasma (QDTeq≥0.7) with high beta (β_N ≥ 3.5) is achievable with 25 MW of NB power at I_P = 4.0 MA and an aspect ratio of 2.6. High beta with steady-state full current drive is possible with 13 MW of NB power at I_P = 1.5-1.7 MA. In the engineering design activity of NCT, the strength of the support structure and strength of material for the conductor is confirmed for the superconducting coils, and the successful progress of R&D of boron-loaded resin for neutron shielding is discussed.

本文言語	English
ページ（範囲）	1599-1605
ページ数	7
ジャーナル	Fusion Engineering and Design
巻	81
号	8-14 PART B
DOI	https://doi.org/10.1016/j.fusengdes.2005.08.066
出版ステータス	Published - 2006 2月
外部発表	はい
イベント	Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B - 継続期間: 2005 5月 22 → 2005 5月 27

ASJC Scopus subject areas

土木構造工学
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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10.1016/j.fusengdes.2005.08.066

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Tsuchiya, K., Akiba, M., Azechi, H., Fujii, T., Fujita, T., Fujiwara, M., Hamamatsu, K., Hashizume, H., Hayashi, N., Horiike, H., Hosogane, N., Ichimura, M., Ida, K., Ikeda, Y., Imai, T., Inoue, N., Ishida, S., Itoh, S., Kamada, Y., ... Yoshida, N. (2006). Engineering design and control scenario for steady-state high-beta operation in National Centralized Tokamak. Fusion Engineering and Design, 81(8-14 PART B), 1599-1605. https://doi.org/10.1016/j.fusengdes.2005.08.066

Tsuchiya, K, Akiba, M, Azechi, H, Fujii, T, Fujita, T, Fujiwara, M, Hamamatsu, K, Hashizume, H, Hayashi, N, Horiike, H, Hosogane, N, Ichimura, M, Ida, K, Ikeda, Y, Imai, T, Inoue, N, Ishida, S, Itoh, S, Kamada, Y, Kawashima, H, Kikuchi, M, Kimura, A, Kizu, K, Kubo, H, Kudo, Y, Kurihara, K, Kurita, G, Kuriyama, M, Masaki, K, Matsukawa, M, Matsuoka, M, Miura, Y, Miura, YM, Miya, N, Morioka, A, Nakamura, K, Ninomiya, H, Nishimura, A, Okano, K, Okuno, K, Sagara, A, Sakamoto, M, Sakurai, S, Sato, K, Shimada, R, Shimizu, A, Suzuki, T, Takahashi, H, Takase, Y, Takechi, M, Tamai, H, Tanaka, S, Tsutsui, H, Uesugi, Y, Yatsu, K & Yoshida, N 2006, 'Engineering design and control scenario for steady-state high-beta operation in National Centralized Tokamak', Fusion Engineering and Design, vol. 81, no. 8-14 PART B, pp. 1599-1605. https://doi.org/10.1016/j.fusengdes.2005.08.066

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title = "Engineering design and control scenario for steady-state high-beta operation in National Centralized Tokamak",

abstract = "The mission of the National Centralized Tokamak (NCT) is to establish high-beta steady-state plasma operation for DEMO and to contribute to ITER. Plasma performance with high-beta conditions is discussed. It is found that near break-even class plasma (QDTeq≥0.7) with high beta (βN ≥ 3.5) is achievable with 25 MW of NB power at IP = 4.0 MA and an aspect ratio of 2.6. High beta with steady-state full current drive is possible with 13 MW of NB power at IP = 1.5-1.7 MA. In the engineering design activity of NCT, the strength of the support structure and strength of material for the conductor is confirmed for the superconducting coils, and the successful progress of R&D of boron-loaded resin for neutron shielding is discussed.",

keywords = "Break-even, High beta, NCT, Steady state",

author = "K. Tsuchiya and M. Akiba and H. Azechi and T. Fujii and T. Fujita and M. Fujiwara and K. Hamamatsu and H. Hashizume and N. Hayashi and H. Horiike and N. Hosogane and M. Ichimura and K. Ida and Y. Ikeda and T. Imai and N. Inoue and S. Ishida and S. Itoh and Y. Kamada and H. Kawashima and M. Kikuchi and A. Kimura and K. Kizu and H. Kubo and Y. Kudo and K. Kurihara and G. Kurita and M. Kuriyama and K. Masaki and M. Matsukawa and M. Matsuoka and Y. Miura and Miura, {Y. M.} and N. Miya and A. Morioka and K. Nakamura and H. Ninomiya and A. Nishimura and K. Okano and K. Okuno and A. Sagara and M. Sakamoto and S. Sakurai and K. Sato and R. Shimada and A. Shimizu and T. Suzuki and H. Takahashi and Y. Takase and M. Takechi and H. Tamai and S. Tanaka and H. Tsutsui and Y. Uesugi and K. Yatsu and N. Yoshida",

year = "2006",

month = feb,

doi = "10.1016/j.fusengdes.2005.08.066",

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journal = "Fusion Engineering and Design",

issn = "0920-3796",

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number = "8-14 PART B",

note = "Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B ; Conference date: 22-05-2005 Through 27-05-2005",

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T1 - Engineering design and control scenario for steady-state high-beta operation in National Centralized Tokamak

AU - Tsuchiya, K.

AU - Akiba, M.

AU - Azechi, H.

AU - Fujii, T.

AU - Fujita, T.

AU - Fujiwara, M.

AU - Hamamatsu, K.

AU - Hashizume, H.

AU - Hayashi, N.

AU - Horiike, H.

AU - Hosogane, N.

AU - Ichimura, M.

AU - Ida, K.

AU - Ikeda, Y.

AU - Imai, T.

AU - Inoue, N.

AU - Ishida, S.

AU - Itoh, S.

AU - Kamada, Y.

AU - Kawashima, H.

AU - Kikuchi, M.

AU - Kimura, A.

AU - Kizu, K.

AU - Kubo, H.

AU - Kudo, Y.

AU - Kurihara, K.

AU - Kurita, G.

AU - Kuriyama, M.

AU - Masaki, K.

AU - Matsukawa, M.

AU - Matsuoka, M.

AU - Miura, Y.

AU - Miura, Y. M.

AU - Miya, N.

AU - Morioka, A.

AU - Nakamura, K.

AU - Ninomiya, H.

AU - Nishimura, A.

AU - Okano, K.

AU - Okuno, K.

AU - Sagara, A.

AU - Sakamoto, M.

AU - Sakurai, S.

AU - Sato, K.

AU - Shimada, R.

AU - Shimizu, A.

AU - Suzuki, T.

AU - Takahashi, H.

AU - Takase, Y.

AU - Takechi, M.

AU - Tamai, H.

AU - Tanaka, S.

AU - Tsutsui, H.

AU - Uesugi, Y.

AU - Yatsu, K.

AU - Yoshida, N.

PY - 2006/2

Y1 - 2006/2

N2 - The mission of the National Centralized Tokamak (NCT) is to establish high-beta steady-state plasma operation for DEMO and to contribute to ITER. Plasma performance with high-beta conditions is discussed. It is found that near break-even class plasma (QDTeq≥0.7) with high beta (βN ≥ 3.5) is achievable with 25 MW of NB power at IP = 4.0 MA and an aspect ratio of 2.6. High beta with steady-state full current drive is possible with 13 MW of NB power at IP = 1.5-1.7 MA. In the engineering design activity of NCT, the strength of the support structure and strength of material for the conductor is confirmed for the superconducting coils, and the successful progress of R&D of boron-loaded resin for neutron shielding is discussed.

AB - The mission of the National Centralized Tokamak (NCT) is to establish high-beta steady-state plasma operation for DEMO and to contribute to ITER. Plasma performance with high-beta conditions is discussed. It is found that near break-even class plasma (QDTeq≥0.7) with high beta (βN ≥ 3.5) is achievable with 25 MW of NB power at IP = 4.0 MA and an aspect ratio of 2.6. High beta with steady-state full current drive is possible with 13 MW of NB power at IP = 1.5-1.7 MA. In the engineering design activity of NCT, the strength of the support structure and strength of material for the conductor is confirmed for the superconducting coils, and the successful progress of R&D of boron-loaded resin for neutron shielding is discussed.

KW - Break-even

KW - High beta

KW - NCT

KW - Steady state

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U2 - 10.1016/j.fusengdes.2005.08.066

DO - 10.1016/j.fusengdes.2005.08.066

M3 - Conference article

AN - SCOPUS:32444447711

SN - 0920-3796

VL - 81

SP - 1599

EP - 1605

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

IS - 8-14 PART B

T2 - Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B

Y2 - 22 May 2005 through 27 May 2005

ER -

Engineering design and control scenario for steady-state high-beta operation in National Centralized Tokamak

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