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 & 36 others 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, Kunihiko 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

Research output: Contribution to journalArticle

1 Citation (Scopus)

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.

Original languageEnglish
Pages (from-to)1599-1605
Number of pages7
JournalFusion Engineering and Design
Volume81
Issue number8-14 PART B
DOIs
Publication statusPublished - 2006 Feb
Externally publishedYes

Fingerprint

Plasmas
Boron
Shielding
Strength of materials
Aspect ratio
Neutrons
Resins
Superconducting coils

Keywords

  • Break-even
  • High beta
  • NCT
  • Steady state

ASJC Scopus subject areas

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

Cite this

Tsuchiya, K., Akiba, M., Azechi, H., Fujii, T., Fujita, T., Fujiwara, M., ... 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

Engineering design and control scenario for steady-state high-beta operation in National Centralized Tokamak. / 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, Y. M.; Miya, N.; Morioka, A.; Nakamura, K.; Ninomiya, H.; Nishimura, A.; Okano, Kunihiko; 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.

In: Fusion Engineering and Design, Vol. 81, No. 8-14 PART B, 02.2006, p. 1599-1605.

Research output: Contribution to journalArticle

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
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, Y. M. ; Miya, N. ; Morioka, A. ; Nakamura, K. ; Ninomiya, H. ; Nishimura, A. ; Okano, Kunihiko ; 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. / Engineering design and control scenario for steady-state high-beta operation in National Centralized Tokamak. In: Fusion Engineering and Design. 2006 ; Vol. 81, No. 8-14 PART B. pp. 1599-1605.
@article{f1dae8efef5944c59c9629f1908cc150,
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 Kunihiko 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 = "2",
doi = "10.1016/j.fusengdes.2005.08.066",
language = "English",
volume = "81",
pages = "1599--1605",
journal = "Fusion Engineering and Design",
issn = "0920-3796",
publisher = "Elsevier BV",
number = "8-14 PART B",

}

TY - JOUR

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, Kunihiko

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

UR - http://www.scopus.com/inward/record.url?scp=32444447711&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=32444447711&partnerID=8YFLogxK

U2 - 10.1016/j.fusengdes.2005.08.066

DO - 10.1016/j.fusengdes.2005.08.066

M3 - Article

VL - 81

SP - 1599

EP - 1605

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

SN - 0920-3796

IS - 8-14 PART B

ER -