Overview of confinement and MHD stability in the Large Helical Device

O. Motojima, K. Ida, K. Y. Watanabe, Y. Nagayama, A. Komori, T. Morisaki, B. J. Peterson, Y. Takeiri, K. Ohkubo, K. Tanaka, T. Shimozuma, S. Inagaki, T. Kobuchi, S. Sakakibara, J. Miyazawa, H. Yamada, N. Ohyabu, K. Narihara, K. Nishimura, M. YoshinumaS. Morita, T. Akiyama, N. Ashikawa, C. D. Beidler, M. Emoto, T. Fujita, T. Fukuda, H. Funaba, P. Goncharov, M. Goto, T. Ido, K. Ikeda, A. Isayama, M. Isobe, H. Igami, K. Ishii, K. Itoh, O. Kaneko, K. Kawahata, H. Kawazome, S. Kubo, R. Kumazawa, S. Masuzaki, K. Matsuoka, T. Minami, S. Murakami, S. Muto, T. Mutoh, Y. Nakamura, H. Nakanishi, Y. Narushima, M. Nishiura, A. Nishizawa, N. Noda, T. Notake, H. Nozato, S. Ohdachi, Y. Oka, S. Okajima, M. Osakabe, T. Ozaki, A. Sagara, T. Saida, K. Saito, M. Sakamoto, R. Sakamoto, Y. Sakamoto, M. Sasao, K. Sato, M. Sato, T. Seki, M. Shoji, S. Sudo, N. Takeuchi, H. Takenaga, N. Tamura, K. Toi, T. Tokuzawa, Y. Torii, K. Tsumori, T. Uda, A. Wakasa, T. Watari, I. Yamada, S. Yamamoto, K. Yamazaki, M. Yokoyama, Y. Yoshimura

Research output: Contribution to journalArticle

34 Citations (Scopus)

Abstract

The Large Helical Device is a heliotron device with L ≤ 2 and M ≤ 10 continuous helical coils with a major radius of 3.5-4.1 m, a minor radius of 0.6 m and a toroidal field of 0.5-3 T, which is a candidate among toroidal magnetic confinement systems for a steady state thermonuclear fusion reactor. There has been significant progress in extending the plasma operational regime in various plasma parameters by neutral beam injection with a power of 13 MW and electron cyclotron heating (ECH) with a power of 2 MW. The electron and ion temperatures have reached up to 10 keV in the collisionless regime, and the maximum electron density, the volume averaged beta value and stored energy are 2.4 × 1020 m-3, 4.1% and 1.3 MJ, respectively. In the last two years, intensive studies of the magnetohydrodynamics stability providing access to the high beta regime and of healing of the magnetic island in comparison with the neoclassical tearing mode in tokamaks have been conducted. Local island divertor experiments have also been performed to control the edge plasma aimed at confinement improvement. As for transport study, transient transport analysis was executed for a plasma with an internal transport barrier and a magnetic island. The high ion temperature plasma was obtained by adding impurities to the plasma to keep the power deposition to the ions reasonably high even at a very low density. By injecting 72 kW of ECH power, the plasma was sustained for 756 s without serious problems of impurities or recycling.

Original languageEnglish
Pages (from-to)S255-S265
JournalNuclear Fusion
Volume45
Issue number10
DOIs
Publication statusPublished - Oct 1 2005

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electron cyclotron heating
magnetic islands
ion temperature
impurities
radii
beam injection
fusion reactors
magnetohydrodynamic stability
healing
neutral beams
recycling
coils
electron energy
ions
energy

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Condensed Matter Physics

Cite this

Motojima, O., Ida, K., Watanabe, K. Y., Nagayama, Y., Komori, A., Morisaki, T., ... Yoshimura, Y. (2005). Overview of confinement and MHD stability in the Large Helical Device. Nuclear Fusion, 45(10), S255-S265. https://doi.org/10.1088/0029-5515/45/10/S21

Overview of confinement and MHD stability in the Large Helical Device. / Motojima, O.; Ida, K.; Watanabe, K. Y.; Nagayama, Y.; Komori, A.; Morisaki, T.; Peterson, B. J.; Takeiri, Y.; Ohkubo, K.; Tanaka, K.; Shimozuma, T.; Inagaki, S.; Kobuchi, T.; Sakakibara, S.; Miyazawa, J.; Yamada, H.; Ohyabu, N.; Narihara, K.; Nishimura, K.; Yoshinuma, M.; Morita, S.; Akiyama, T.; Ashikawa, N.; Beidler, C. D.; Emoto, M.; Fujita, T.; Fukuda, T.; Funaba, H.; Goncharov, P.; Goto, M.; Ido, T.; Ikeda, K.; Isayama, A.; Isobe, M.; Igami, H.; Ishii, K.; Itoh, K.; Kaneko, O.; Kawahata, K.; Kawazome, H.; Kubo, S.; Kumazawa, R.; Masuzaki, S.; Matsuoka, K.; Minami, T.; Murakami, S.; Muto, S.; Mutoh, T.; Nakamura, Y.; Nakanishi, H.; Narushima, Y.; Nishiura, M.; Nishizawa, A.; Noda, N.; Notake, T.; Nozato, H.; Ohdachi, S.; Oka, Y.; Okajima, S.; Osakabe, M.; Ozaki, T.; Sagara, A.; Saida, T.; Saito, K.; Sakamoto, M.; Sakamoto, R.; Sakamoto, Y.; Sasao, M.; Sato, K.; Sato, M.; Seki, T.; Shoji, M.; Sudo, S.; Takeuchi, N.; Takenaga, H.; Tamura, N.; Toi, K.; Tokuzawa, T.; Torii, Y.; Tsumori, K.; Uda, T.; Wakasa, A.; Watari, T.; Yamada, I.; Yamamoto, S.; Yamazaki, K.; Yokoyama, M.; Yoshimura, Y.

In: Nuclear Fusion, Vol. 45, No. 10, 01.10.2005, p. S255-S265.

Research output: Contribution to journalArticle

Motojima, O, Ida, K, Watanabe, KY, Nagayama, Y, Komori, A, Morisaki, T, Peterson, BJ, Takeiri, Y, Ohkubo, K, Tanaka, K, Shimozuma, T, Inagaki, S, Kobuchi, T, Sakakibara, S, Miyazawa, J, Yamada, H, Ohyabu, N, Narihara, K, Nishimura, K, Yoshinuma, M, Morita, S, Akiyama, T, Ashikawa, N, Beidler, CD, Emoto, M, Fujita, T, Fukuda, T, Funaba, H, Goncharov, P, Goto, M, Ido, T, Ikeda, K, Isayama, A, Isobe, M, Igami, H, Ishii, K, Itoh, K, Kaneko, O, Kawahata, K, Kawazome, H, Kubo, S, Kumazawa, R, Masuzaki, S, Matsuoka, K, Minami, T, Murakami, S, Muto, S, Mutoh, T, Nakamura, Y, Nakanishi, H, Narushima, Y, Nishiura, M, Nishizawa, A, Noda, N, Notake, T, Nozato, H, Ohdachi, S, Oka, Y, Okajima, S, Osakabe, M, Ozaki, T, Sagara, A, Saida, T, Saito, K, Sakamoto, M, Sakamoto, R, Sakamoto, Y, Sasao, M, Sato, K, Sato, M, Seki, T, Shoji, M, Sudo, S, Takeuchi, N, Takenaga, H, Tamura, N, Toi, K, Tokuzawa, T, Torii, Y, Tsumori, K, Uda, T, Wakasa, A, Watari, T, Yamada, I, Yamamoto, S, Yamazaki, K, Yokoyama, M & Yoshimura, Y 2005, 'Overview of confinement and MHD stability in the Large Helical Device', Nuclear Fusion, vol. 45, no. 10, pp. S255-S265. https://doi.org/10.1088/0029-5515/45/10/S21
Motojima O, Ida K, Watanabe KY, Nagayama Y, Komori A, Morisaki T et al. Overview of confinement and MHD stability in the Large Helical Device. Nuclear Fusion. 2005 Oct 1;45(10):S255-S265. https://doi.org/10.1088/0029-5515/45/10/S21
Motojima, O. ; Ida, K. ; Watanabe, K. Y. ; Nagayama, Y. ; Komori, A. ; Morisaki, T. ; Peterson, B. J. ; Takeiri, Y. ; Ohkubo, K. ; Tanaka, K. ; Shimozuma, T. ; Inagaki, S. ; Kobuchi, T. ; Sakakibara, S. ; Miyazawa, J. ; Yamada, H. ; Ohyabu, N. ; Narihara, K. ; Nishimura, K. ; Yoshinuma, M. ; Morita, S. ; Akiyama, T. ; Ashikawa, N. ; Beidler, C. D. ; Emoto, M. ; Fujita, T. ; Fukuda, T. ; Funaba, H. ; Goncharov, P. ; Goto, M. ; Ido, T. ; Ikeda, K. ; Isayama, A. ; Isobe, M. ; Igami, H. ; Ishii, K. ; Itoh, K. ; Kaneko, O. ; Kawahata, K. ; Kawazome, H. ; Kubo, S. ; Kumazawa, R. ; Masuzaki, S. ; Matsuoka, K. ; Minami, T. ; Murakami, S. ; Muto, S. ; Mutoh, T. ; Nakamura, Y. ; Nakanishi, H. ; Narushima, Y. ; Nishiura, M. ; Nishizawa, A. ; Noda, N. ; Notake, T. ; Nozato, H. ; Ohdachi, S. ; Oka, Y. ; Okajima, S. ; Osakabe, M. ; Ozaki, T. ; Sagara, A. ; Saida, T. ; Saito, K. ; Sakamoto, M. ; Sakamoto, R. ; Sakamoto, Y. ; Sasao, M. ; Sato, K. ; Sato, M. ; Seki, T. ; Shoji, M. ; Sudo, S. ; Takeuchi, N. ; Takenaga, H. ; Tamura, N. ; Toi, K. ; Tokuzawa, T. ; Torii, Y. ; Tsumori, K. ; Uda, T. ; Wakasa, A. ; Watari, T. ; Yamada, I. ; Yamamoto, S. ; Yamazaki, K. ; Yokoyama, M. ; Yoshimura, Y. / Overview of confinement and MHD stability in the Large Helical Device. In: Nuclear Fusion. 2005 ; Vol. 45, No. 10. pp. S255-S265.
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abstract = "The Large Helical Device is a heliotron device with L ≤ 2 and M ≤ 10 continuous helical coils with a major radius of 3.5-4.1 m, a minor radius of 0.6 m and a toroidal field of 0.5-3 T, which is a candidate among toroidal magnetic confinement systems for a steady state thermonuclear fusion reactor. There has been significant progress in extending the plasma operational regime in various plasma parameters by neutral beam injection with a power of 13 MW and electron cyclotron heating (ECH) with a power of 2 MW. The electron and ion temperatures have reached up to 10 keV in the collisionless regime, and the maximum electron density, the volume averaged beta value and stored energy are 2.4 × 1020 m-3, 4.1{\%} and 1.3 MJ, respectively. In the last two years, intensive studies of the magnetohydrodynamics stability providing access to the high beta regime and of healing of the magnetic island in comparison with the neoclassical tearing mode in tokamaks have been conducted. Local island divertor experiments have also been performed to control the edge plasma aimed at confinement improvement. As for transport study, transient transport analysis was executed for a plasma with an internal transport barrier and a magnetic island. The high ion temperature plasma was obtained by adding impurities to the plasma to keep the power deposition to the ions reasonably high even at a very low density. By injecting 72 kW of ECH power, the plasma was sustained for 756 s without serious problems of impurities or recycling.",
author = "O. Motojima and K. Ida and Watanabe, {K. Y.} and Y. Nagayama and A. Komori and T. Morisaki and Peterson, {B. J.} and Y. Takeiri and K. Ohkubo and K. Tanaka and T. Shimozuma and S. Inagaki and T. Kobuchi and S. Sakakibara and J. Miyazawa and H. Yamada and N. Ohyabu and K. Narihara and K. Nishimura and M. Yoshinuma and S. Morita and T. Akiyama and N. Ashikawa and Beidler, {C. D.} and M. Emoto and T. Fujita and T. Fukuda and H. Funaba and P. Goncharov and M. Goto and T. Ido and K. Ikeda and A. Isayama and M. Isobe and H. Igami and K. Ishii and K. Itoh and O. Kaneko and K. Kawahata and H. Kawazome and S. Kubo and R. Kumazawa and S. Masuzaki and K. Matsuoka and T. Minami and S. Murakami and S. Muto and T. Mutoh and Y. Nakamura and H. Nakanishi and Y. Narushima and M. Nishiura and A. Nishizawa and N. Noda and T. Notake and H. Nozato and S. Ohdachi and Y. Oka and S. Okajima and M. Osakabe and T. Ozaki and A. Sagara and T. Saida and K. Saito and M. Sakamoto and R. Sakamoto and Y. Sakamoto and M. Sasao and K. Sato and M. Sato and T. Seki and M. Shoji and S. Sudo and N. Takeuchi and H. Takenaga and N. Tamura and K. Toi and T. Tokuzawa and Y. Torii and K. Tsumori and T. Uda and A. Wakasa and T. Watari and I. Yamada and S. Yamamoto and K. Yamazaki and M. Yokoyama and Y. Yoshimura",
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TY - JOUR

T1 - Overview of confinement and MHD stability in the Large Helical Device

AU - Motojima, O.

AU - Ida, K.

AU - Watanabe, K. Y.

AU - Nagayama, Y.

AU - Komori, A.

AU - Morisaki, T.

AU - Peterson, B. J.

AU - Takeiri, Y.

AU - Ohkubo, K.

AU - Tanaka, K.

AU - Shimozuma, T.

AU - Inagaki, S.

AU - Kobuchi, T.

AU - Sakakibara, S.

AU - Miyazawa, J.

AU - Yamada, H.

AU - Ohyabu, N.

AU - Narihara, K.

AU - Nishimura, K.

AU - Yoshinuma, M.

AU - Morita, S.

AU - Akiyama, T.

AU - Ashikawa, N.

AU - Beidler, C. D.

AU - Emoto, M.

AU - Fujita, T.

AU - Fukuda, T.

AU - Funaba, H.

AU - Goncharov, P.

AU - Goto, M.

AU - Ido, T.

AU - Ikeda, K.

AU - Isayama, A.

AU - Isobe, M.

AU - Igami, H.

AU - Ishii, K.

AU - Itoh, K.

AU - Kaneko, O.

AU - Kawahata, K.

AU - Kawazome, H.

AU - Kubo, S.

AU - Kumazawa, R.

AU - Masuzaki, S.

AU - Matsuoka, K.

AU - Minami, T.

AU - Murakami, S.

AU - Muto, S.

AU - Mutoh, T.

AU - Nakamura, Y.

AU - Nakanishi, H.

AU - Narushima, Y.

AU - Nishiura, M.

AU - Nishizawa, A.

AU - Noda, N.

AU - Notake, T.

AU - Nozato, H.

AU - Ohdachi, S.

AU - Oka, Y.

AU - Okajima, S.

AU - Osakabe, M.

AU - Ozaki, T.

AU - Sagara, A.

AU - Saida, T.

AU - Saito, K.

AU - Sakamoto, M.

AU - Sakamoto, R.

AU - Sakamoto, Y.

AU - Sasao, M.

AU - Sato, K.

AU - Sato, M.

AU - Seki, T.

AU - Shoji, M.

AU - Sudo, S.

AU - Takeuchi, N.

AU - Takenaga, H.

AU - Tamura, N.

AU - Toi, K.

AU - Tokuzawa, T.

AU - Torii, Y.

AU - Tsumori, K.

AU - Uda, T.

AU - Wakasa, A.

AU - Watari, T.

AU - Yamada, I.

AU - Yamamoto, S.

AU - Yamazaki, K.

AU - Yokoyama, M.

AU - Yoshimura, Y.

PY - 2005/10/1

Y1 - 2005/10/1

N2 - The Large Helical Device is a heliotron device with L ≤ 2 and M ≤ 10 continuous helical coils with a major radius of 3.5-4.1 m, a minor radius of 0.6 m and a toroidal field of 0.5-3 T, which is a candidate among toroidal magnetic confinement systems for a steady state thermonuclear fusion reactor. There has been significant progress in extending the plasma operational regime in various plasma parameters by neutral beam injection with a power of 13 MW and electron cyclotron heating (ECH) with a power of 2 MW. The electron and ion temperatures have reached up to 10 keV in the collisionless regime, and the maximum electron density, the volume averaged beta value and stored energy are 2.4 × 1020 m-3, 4.1% and 1.3 MJ, respectively. In the last two years, intensive studies of the magnetohydrodynamics stability providing access to the high beta regime and of healing of the magnetic island in comparison with the neoclassical tearing mode in tokamaks have been conducted. Local island divertor experiments have also been performed to control the edge plasma aimed at confinement improvement. As for transport study, transient transport analysis was executed for a plasma with an internal transport barrier and a magnetic island. The high ion temperature plasma was obtained by adding impurities to the plasma to keep the power deposition to the ions reasonably high even at a very low density. By injecting 72 kW of ECH power, the plasma was sustained for 756 s without serious problems of impurities or recycling.

AB - The Large Helical Device is a heliotron device with L ≤ 2 and M ≤ 10 continuous helical coils with a major radius of 3.5-4.1 m, a minor radius of 0.6 m and a toroidal field of 0.5-3 T, which is a candidate among toroidal magnetic confinement systems for a steady state thermonuclear fusion reactor. There has been significant progress in extending the plasma operational regime in various plasma parameters by neutral beam injection with a power of 13 MW and electron cyclotron heating (ECH) with a power of 2 MW. The electron and ion temperatures have reached up to 10 keV in the collisionless regime, and the maximum electron density, the volume averaged beta value and stored energy are 2.4 × 1020 m-3, 4.1% and 1.3 MJ, respectively. In the last two years, intensive studies of the magnetohydrodynamics stability providing access to the high beta regime and of healing of the magnetic island in comparison with the neoclassical tearing mode in tokamaks have been conducted. Local island divertor experiments have also been performed to control the edge plasma aimed at confinement improvement. As for transport study, transient transport analysis was executed for a plasma with an internal transport barrier and a magnetic island. The high ion temperature plasma was obtained by adding impurities to the plasma to keep the power deposition to the ions reasonably high even at a very low density. By injecting 72 kW of ECH power, the plasma was sustained for 756 s without serious problems of impurities or recycling.

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