JOPSS - Search Results

Journal Articles

Prototype tokamak fusion power reactor based on SiC/SiC composite material, focussing on easy maintenance

Nishio, Satoshi; Ueda, Shuzo; Kurihara, Ryoichi; Kuroda, Toshimasa*; Miura, H.*; Sako, Kiyoshi*; Takase, Kazuyuki; Seki, Yasushi; Adachi, Junichi*; Yamazaki, Seiichiro*; et al.

Fusion Engineering and Design, 48(3-4), p.271 - 279, 2000/09

https://doi.org/10.1016/S0920-3796(00)00167-8

Times Cited Count：17 Percentile：72(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Improved tokamak concept focusing on easy maintenance

Nishio, Satoshi; Ueda, Shuzo; Aoki, Isao; Kurihara, Ryoichi; Kuroda, Toshimasa*; Miura, H.*; Kunugi, Tomoaki; Takase, Kazuyuki; Seki, Yasushi; Shinya, K.*; et al.

Fusion Engineering and Design, 41, p.357 - 364, 1998/00

https://doi.org/10.1016/S0920-3796(98)00119-7

Times Cited Count：51 Percentile：95.41(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Japanese contribution of ITER PF systems design during CDA

Azumi, Masafumi; Hasegawa, Mitsuru*; *; Kurihara, Kenichi; Nakamura, Yukiharu; Nishio, Satoshi; Shimomura, Yasuo; Shinya, K.*; Sugihara, Masayoshi; *; et al.

JAERI-M 92-041, 100 Pages, 1992/03

JAERI-M-92-041.pdf:2.59MB

no abstracts in English

Journal Articles

Separatrix sweeping by in-vessel coils on a fusion reactor

Nishio, Satoshi; Araki, Masanori; Shinya, K.*; Shimizu, Katsusuke*; Kuroda, Toshimasa*; Sugihara, Masayoshi; Shimomura, Yasuo

Fusion Engineering and Design, 19, p.203 - 211, 1992/00

https://doi.org/10.1016/0920-3796(92)90030-8

Times Cited Count：2 Percentile：27.49(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Control of the plasma configuration in ITER

Yoshino, Ryuji; Nishio, Satoshi; Shinya, K.*; Sugihara, Masayoshi

JAERI-M 91-049, 15 Pages, 1991/03

JAERI-M-91-049.pdf:0.52MB

no abstracts in English

Journal Articles

A Method for mapping plasma operational space within the engineering constraints of the poloidal field coil system in a tokamak reactor

Nishio, Satoshi; Shinya, K.*

Fusion Technology, 19, p.86 - 94, 1991/01

no abstracts in English

JAEA Reports

Study on poloidal field coil optimization and equilibrium control of ITER

Shinya, K.*; Sugihara, Masayoshi; Nishio, Satoshi

JAERI-M 89-028, 56 Pages, 1989/03

JAERI-M-89-028.pdf:1.41MB

no abstracts in English

JAEA Reports

Japanese contributions to IAEA INTOR Workshop, Phase two A,Part 3; Chapter VII; Configuration and maintenance

Iida, Hiromasa; *; *; Adachi, Junichi*; *; *; Hamajima, Takataro*; Hatayama, Akiyoshi*; *; *; et al.

JAERI-M 88-011, 261 Pages, 1988/02

JAERI-M-88-011.pdf:6.44MB

no abstracts in English

JAEA Reports

Japanese contributions to IAEA INTOR Workshop,Phase two A,Part 3; Chapter VI: Electromagnetics

*; *; *; Ando, Toshinari; Fujisawa, Noboru; Hasegawa, Mitsuru*; *; *; *; Iida, Hiromasa; et al.

JAERI-M 88-010, 206 Pages, 1988/02

JAERI-M-88-010.pdf:3.83MB

no abstracts in English

JAEA Reports

A Toroidal plasma MHD equilibrium code EQUCIR version 3

Shinya, K.*; Nishio, Satoshi

JAERI-M 87-133, 16 Pages, 1987/09

JAERI-M-87-133.pdf:0.48MB

no abstracts in English

JAEA Reports

Development of tokamak reactor conceptual design code TRESCODE Conceptual design study of FY86 FER

Mizoguchi, Tadanori*; Sugihara, Masayoshi; Shinya, K.*; *; *; Nakajima, Kunihiko*; *; *; Fujisawa, Noboru; Yamamoto, Shin; et al.

JAERI-M 87-120, 49 Pages, 1987/08

JAERI-M-87-120.pdf:0.94MB

no abstracts in English

JAEA Reports

Two-dimensional analysis for a scrapeoff and divertor regions with an MHD model; Conceptual design study of FY86 FER

*; *; Hitoki, Shigehisa*; Fujisawa, Noboru; Sugihara, Masayoshi; Yamamoto, Shin; Mizoguchi, Tadanori*; Abe, Mitsushi*; *; *; et al.

JAERI-M 87-119, 19 Pages, 1987/08

JAERI-M-87-119.pdf:0.5MB

no abstracts in English

JAEA Reports

Preliminary analysis on plasma equilibrium control; Conceptual design study of FY86 FER

Abe, Mitsushi*; *; *; *; *; *; Shinya, K.*; Sugihara, Masayoshi; Hatayama, Akiyoshi*; Hitoki, Shigehisa*; et al.

JAERI-M 87-116, 13 Pages, 1987/08

JAERI-M-87-116.pdf:0.49MB

no abstracts in English

JAEA Reports

Effect of discrete RF spectrum on fast wave current drive; Conceptual design study of FY86 FER

*; *; Sugihara, Masayoshi; Yamamoto, Shin; Mizoguchi, Tadanori*; Hitoki, Shigehisa*; Abe, Mitsushi*; *; *; *; et al.

JAERI-M 87-110, 11 Pages, 1987/08

JAERI-M-87-110.pdf:0.38MB

no abstracts in English

JAEA Reports

Consistency between current ramp-up/recharging scenario by non-inductive current drive and dense and cold divertor plasma; Conceptual design study of FY86 FER

Hitoki, Shigehisa*; Sugihara, Masayoshi; Yamamoto, Shin; Abe, Mitsushi*; *; *; *; *; Shinya, K.*; Hatayama, Akiyoshi*; et al.

JAERI-M 87-109, 33 Pages, 1987/08

JAERI-M-87-109.pdf:0.81MB

no abstracts in English

JAEA Reports

Plasma physics design and major specifications of candidate reactors for FER design studies; Conceptual design study of FY86 FER

Sugihara, Masayoshi; Mizoguchi, Tadanori*; Hatayama, Akiyoshi*; Shinya, K.*; Yamamoto, Shin; Abe, Mitsushi*; *; *; *; *; et al.

JAERI-M 87-108, 49 Pages, 1987/08

JAERI-M-87-108.pdf:1.42MB

no abstracts in English

JAEA Reports

Main physics features driving design concept and physics design constraints; Conceptual design study of FY86 FER

Fujisawa, Noboru; Sugihara, Masayoshi; Yamamoto, Shin; Mizoguchi, Tadanori*; Hitoki, Shigehisa*; Abe, Mitsushi*; *; *; *; *; et al.

JAERI-M 87-093, 64 Pages, 1987/07

JAERI-M-87-093.pdf:1.45MB

no abstracts in English

Presentation/Publication Type

Journal/Book Title

Meeting title

First Author

Keyword

Language

Publication Year

Held year of conference

Prototype tokamak fusion power reactor based on SiC/SiC composite material, focussing on easy maintenance

Improved tokamak concept focusing on easy maintenance

Japanese contribution of ITER PF systems design during CDA

Separatrix sweeping by in-vessel coils on a fusion reactor

Control of the plasma configuration in ITER

A Method for mapping plasma operational space within the engineering constraints of the poloidal field coil system in a tokamak reactor

Study on poloidal field coil optimization and equilibrium control of ITER

Japanese contributions to IAEA INTOR Workshop, Phase two A,Part 3; Chapter VII; Configuration and maintenance

Japanese contributions to IAEA INTOR Workshop,Phase two A,Part 3; Chapter VI: Electromagnetics

A Toroidal plasma MHD equilibrium code EQUCIR version 3

Development of tokamak reactor conceptual design code TRESCODE Conceptual design study of FY86 FER

Two-dimensional analysis for a scrapeoff and divertor regions with an MHD model; Conceptual design study of FY86 FER

Preliminary analysis on plasma equilibrium control; Conceptual design study of FY86 FER

Effect of discrete RF spectrum on fast wave current drive; Conceptual design study of FY86 FER

Consistency between current ramp-up/recharging scenario by non-inductive current drive and dense and cold divertor plasma; Conceptual design study of FY86 FER

Plasma physics design and major specifications of candidate reactors for FER design studies; Conceptual design study of FY86 FER

Main physics features driving design concept and physics design constraints; Conceptual design study of FY86 FER