Search Results - "Mitarai, O."

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  1. 1

    Refueling of field-reversed configuration core via axial plasmoids injection by Asai, T., Takahashi, T., Kobayashi, D., Seki, T., Takeuchi, Y., Mitarai, O., Morelli, J., Mizuguchi, N., Dettrick, S., Gota, H., Roche, T., Matsumoto, T., Binderbauer, M., Tajima, T., Inomoto, M., Takahashi, T.

    Published in Nuclear fusion (01-09-2024)
    “…Abstract This study successfully developed a refueling technique for a field-reversed configuration (FRC) via axial plasmoid injection and demonstrated it on…”
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    Journal Article
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    Improvements to the High-Field-Side Transient CHI System on QUEST by Kuroda, K., Raman, R., Hasegawa, M., Onchi, T., Hanada, K., Ono, M., Nelson, B. A., Rogers, J., Ikezoe, R., Idei, H., Ido, T., Mitarai, O., Nagata, M., Kawasaki, S., Nagata, T., Higashijima, A., Shimabukuro, S., Niiya, I., Sekiya, I., Kojima, S., Nakamura, K., Takase, Y., Murakami, S.

    Published in Journal of fusion energy (01-12-2022)
    “…Transient coaxial helicity injection (CHI) is a promising candidate for solenoid-free plasma current start-up in a low-aspect-ratio tokamak in support of…”
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    Journal Article
  4. 4

    Design activities on helical DEMO reactor FFHR-d1 by Sagara, A., Goto, T., Miyazawa, J., Yanagi, N., Tanaka, T., Tamura, H., Sakamoto, R., Tanaka, M., Tsumori, K., Mitarai, O., Imagawa, S., Muroga, T.

    Published in Fusion engineering and design (01-08-2012)
    “…► Conceptual design studies of the helical DEMO reactor FFHR-d1 have been conducted. ► Design window analyses with core plasma and engineering designs have…”
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    Journal Article
  5. 5

    Particle balance in long duration RF driven plasmas on QUEST by Hanada, K., Zushi, H., Yoshida, N., Yugami, N., Honda, T., Hasegawa, M., Mishra, K., Kuzmin, A., Nakamura, K., Fujisawa, A., Idei, H., Nagashima, Y., Watanabe, O., Onchi, T., Watanabe, H., Tokunaga, K., Higashijima, A., Kawasaki, S., Nakashima, H., Takase, Y., Fukuyama, A., Mitarai, O., Peng, Y.K.M.

    Published in Journal of nuclear materials (01-08-2015)
    “…Global particle balance in non-inductive long-duration plasma on QUEST has been investigated. Approximately 70% of the fuel hydrogen (H) was retained in the…”
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    Journal Article
  6. 6

    Plasma equilibrium based on EC-driven current profile with toroidal rotation on QUEST by Nakamura, K., Alam, M.M., Jiang, Y.Z., Mitarai, O., Takechi, M., Hasegawa, M., Tokunaga, K., Hanada, K., Idei, H., Nagashima, Y., Onchi, T., Kuroda, K., Watanabe, O., Higashijima, A., Nagata, T., Shimabukuro, S., Kawasaki, S., Fukuyama, A.

    Published in Fusion engineering and design (01-09-2019)
    “…•Plasma current seems to flow in the open magnetic surface in the outside of the closed magnetic surface in the low-field region.•Considering the toroidal…”
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    Journal Article
  7. 7

    Plasma current sustainment after iron core saturation in the STOR-M tokamak by Mitarai, O., Ding, Y., Hubeny, M., Lu, Y., Onchi, T., McColl, D., Xiao, C., Hirose, A.

    Published in Fusion engineering and design (01-10-2014)
    “…•Plasma current can be started up by small iron core without central solenoid.•Iron core removes central solenoid.•Plasma current can be maintained after iron…”
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    Journal Article
  8. 8

    Comparative studies of inner and outer divertor discharges and a fueling study in QUEST by Mitarai, O., Nakamura, K., Hasegawa, M., Onchi, T., Idei, H., Fujisawa, A., Hanada, K., Zushi, H., Higashijima, A., Nakashima, H., Kawasaki, S., Matsuoka, K., Koike, S., Takahashi, T., Tsutsui, H.

    Published in Fusion engineering and design (01-11-2016)
    “…•Central solenoid has a small flux in QUEST.•Large plasma current is obtained when the position is shifted to the inboard side.•Two types of divertor operation…”
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    Journal Article
  9. 9

    Feedback control of the heating power to access the thermally unstable ignition regime in FFHR helical reactor by Mitarai, O., Sagara, A., Sakamoto, R., Yanagi, N., Goto, T.

    Published in Fusion engineering and design (01-10-2013)
    “…•We discovered feedback control method of heating power in helical reactor.•Thermally unstable high-density ignition regime can be accessed by this…”
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  10. 10
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    Optimization activities on design studies of LHD-type reactor FFHR by Sagara, A., Mitarai, O., Tanaka, T., Imagawa, S., Kozaki, Y., Kobayashi, M., Morisaki, T., Watanabe, T., Takahata, K., Tamura, H., Yanagi, N., Nishimura, K., Chikaraishi, H., Yamada, S., Fukada, S., Masuzaki, S., Shishkin, A., Igitkhanov, Y., Goto, T., Ogawa, Y., Muroga, T., Mito, T., Motojima, O.

    Published in Fusion engineering and design (01-12-2008)
    “…Recent activities on optimizing the base design of the large helical device (LHD)-type helical reactor FFHR (force free helical reactor) are presented. Three…”
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    Journal Article Conference Proceeding
  12. 12

    Heating by an electron Bernstein wave in a spherical tokamak plasma via mode conversion by Shiraiwa, S, Hanada, K, Hasegawa, M, Idei, H, Kasahara, H, Mitarai, O, Nakamura, K, Nishino, N, Nozato, H, Sakamoto, M, Sasaki, K, Sato, K, Takase, Y, Yamada, T, Zushi, H

    Published in Physical review letters (12-05-2006)
    “…The first successful high power heating of a high dielectric constant spherical tokamak plasma by an electron Bernstein wave (EBW) is reported. An EBW was…”
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    Journal Article
  13. 13

    Development of plasma control system for divertor configuration on QUEST by Hasegawa, M., Nakamura, K., Zushi, H., Hanada, K., Fujisawa, A., Matsuoka, K., Mitarai, O., Idei, H., Nagashima, Y., Tokunaga, K., Kawasaki, S., Nakashima, H., Higashijima, A.

    Published in Fusion engineering and design (01-10-2013)
    “…A plasma control system to sustain divertor configurations is developed on QUEST (Q-shu university experiment with steady-state spherical tokamak). Magnetic…”
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    Journal Article
  14. 14

    Formation of advanced tokamak plasmas without the use of an ohmic-heating solenoid by Shiraiwa, S, Ide, S, Itoh, S, Mitarai, O, Naito, O, Ozeki, T, Sakamoto, Y, Suzuki, T, Takase, Y, Tanaka, S, Taniguchi, T, Aramasu, M, Fujita, T, Fukuda, T, Gao, X, Gryaznevich, M, Hanada, K, Jotaki, E, Kamada, Y, Maekawa, T, Miura, Y, Nakamura, K, Nishi, T, Tanaka, H, Ushigusa, K

    Published in Physical review letters (23-01-2004)
    “…A new operational scenario of advanced tokamak formation was demonstrated in the JT-60U tokamak. This was accomplished by electron cyclotron and lower hybrid…”
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    Journal Article
  15. 15

    Conceptual design activities and key issues on LHD-type reactor FFHR by Sagara, A., Mitarai, O., Imagawa, S., Morisaki, T., Tanaka, T., Mizuguchi, N., Dolan, T., Miyazawa, J., Takahata, K., Chikaraishi, H., Yamada, S., Seo, K., Sakamoto, R., Masuzaki, S., Muroga, T., Yamada, H., Fukada, S., Hashizume, H., Yamazaki, K., Mito, T., Kaneko, O., Mutoh, T., Ohyabu, N., Noda, N., Komori, A., Sudo, S., Motojima, O.

    Published in Fusion engineering and design (01-11-2006)
    “…An overview of conceptual design activities on the LHD-type helical reactor FFHR is presented, mainly focusing on optimization studies on the reactor size and…”
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    Journal Article Conference Proceeding
  16. 16

    Eddy current-adjusted plasma shape reconstruction by Cauchy condition surface method on QUEST by Nakamura, K., Jiang, Y., Liu, X.L., Mitarai, O., Kurihara, K., Kawamata, Y., Sueoka, M., Hasegawa, M., Tokunaga, K., Zushi, H., Hanada, K., Fujisawa, A., Sakamoto, M., Idei, H., Kawasaki, S., Nakashima, H., Higashijima, A., Araki, K.

    Published in Fusion engineering and design (01-10-2011)
    “…CCS (Cauchy Condition Surface) method is a numerical approach to reproduce plasma shape, which has good precision in conventional tokamaks. In order to apply…”
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    Journal Article Conference Proceeding
  17. 17

    Aspect ratio dependencies of D– 3He fueled tokamak reactors by Mitarai, O., Matsuura, H., Tomita, Y.

    Published in Fusion engineering and design (01-11-2006)
    “…Ignition capability is studied and compared for two types of D– 3He spherical tokamak (ST) and medium aspect ratio tokamak (MT) reactors. The required power…”
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    Journal Article Conference Proceeding
  18. 18

    Progress of design studies on an LHD-type steady state reactor by Motojima, O., Komori, A., Sagara, A., Yamada, H., Mitarai, O., Sakamoto, R., Miyazawa, J., Kobayashi, M., Morisaki, T., Masuzaki, S., Imagawa, S., Kozaki, Y., Tanaka, T.

    Published in Fusion engineering and design (01-12-2008)
    “…Progress of design studies on a heliotron reactor is reported. Recent experimental achievements in large helical device (LHD) are building up the physical…”
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    Journal Article Conference Proceeding
  19. 19

    Pellet injection algorithm for the FFHR helical reactor by Mitarai, O., Oda, A., Sagara, A., Yamazaki, K., Motojima, O.

    Published in Fusion engineering and design (01-07-2004)
    “…Pellet injection algorithm has been proposed for engineering developments in the force free helical reactor (FFHR) based on the zero-dimensional equations. In…”
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  20. 20

    Carbon tiles as spectral-shifter for long-life liquid blanket in LHD-type reactor FFHR by Sagara, A., Imagawa, S., Tanaka, T., Muroga, T., Kubota, Y., Dolan, T., Hashizume, H., Kunugi, T., Fukada, S., Shimizu, A., Terai, T., Mitarai, O.

    Published in Fusion engineering and design (01-02-2006)
    “…In terms of engineering feasibility for long-life Flibe blanket in LHD-type reactor FFHR, the Spectral-shifter and Tritium breeder Blanket (STB) concept is…”
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    Journal Article Conference Proceeding