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Journal Articles

Progress of JT-60SA Project; EU-JA joint efforts for assembly and fabrication of superconducting tokamak facilities and its research planning

Shirai, Hiroshi; Barabaschi, P.*; Kamada, Yutaka; JT-60SA Team

Fusion Engineering and Design, 109-111(Part B), p.1701 - 1708, 2016/11

 Times Cited Count:17 Percentile:5.18(Nuclear Science & Technology)

The JT-60SA Project has shown steady progress toward the first plasma in 2019. JT-60SA is a superconducting tokamak designed to operate in the break-even conditions for a long pulse duration with a maximum plasma current of 5.5 MA. Design and fabrication of JT-60SA components shared by EU and Japan started in 2007. Assembly in the torus hall started in January 2013, and welding work of the vacuum vessel sectors is currently on going on the cryostat base. Other components such as TF coils, PF coils, power supplies, cryogenic system, cryostat vessel, thermal shields and so forth were or are being delivered to Naka site for installation, assembly and commissioning. This paper gives technical progress on fabrication, installation and assembly of tokamak components and ancillary systems, as well as progress of JT-60SA Research Plan being developed jointly by EU and Japanese fusion communities.

Journal Articles

Frontier in fusion research, 2; Introduction to modern tokamak physics

Kikuchi, Mitsuru; Azumi, Masafumi*

Frontiers in Fusion Research, 2; Introduction to Modern Tokamak Physics, 402 Pages, 2015/09

This book is a textbook on modern tokamak plasma physics for graduate students and researchers based on our Reviews of Modern Physics (2012).

Journal Articles

On the spatial structure of solitary radial electric field at the plasma edge in toroidal confinement devices

Ito, Kimitaka*; Ito, Sanae*; Kamiya, Kensaku; Kasuya, Naohiro*

Plasma Physics and Controlled Fusion, 57(7), p.075008_1 - 075008_7, 2015/07

 Times Cited Count:18 Percentile:19.46(Physics, Fluids & Plasmas)

The solitary radial electric field in the edge of toroidal plasma is studied based on the electric field bifurcation model. Results are applied to tokamak and helical plasmas, and the dependence of the electric field structure on the plasma parameters and geometrical factors is analyzed. The order of magnitude estimate for tokamak plasma is not far from experimental observations. It is shown that, in helical plasmas, the height of electric field structure is reduced substantially owing to the ripple particle transport, while the width is influenced less. The implications of the results for the limit of achievable gradient in the H-mode pedestal are also discussed.

Journal Articles

Perspective of negative triangularity tokamak as fusion energy system

Kikuchi, Mitsuru; Medvedev, S.*; Takizuka, Tomonori*; Fasoli, A.*; Wu, Y.*; Diamond, P. H.*; Duan, X.*; Kishimoto, Yasuaki*; Hanada, Kazuaki*; 41 of others*

Europhysics Conference Abstracts (Internet), 39E, p.P4.179_1 - P4.179_4, 2015/06

Power and particle control in fusion reactor is quite a challenge and we have studied the negative triangularity tokamak (NTT) as an innovative concept to reduce the transient ELM heat load and the quasi steady-state heat load. A double-null NTT is stable to ideal MHD modes for a reactor relevant bN $$>$$ 3 while it is a magnetic hill configuration. In this paper, we report the configuration study of single-null NTT and its ideal MHD stability.

Journal Articles

Chaos in runaway electron motion

Matsuyama, Akinobu

Purazuma, Kaku Yugo Gakkai-Shi, 91(3), p.204 - 208, 2015/03

no abstracts in English

Journal Articles

Fokker-Planck simulation of runaway electron generation in tokamak disruptions

Nuga, Hideo; Matsuyama, Akinobu; Yagi, Masatoshi; Fukuyama, Atsushi*

Plasma and Fusion Research (Internet), 10, p.1203006_1 - 1203006_2, 2015/01

Journal Articles

Magnetic island evolution in rotating plasmas

Ishii, Yasutomo; Azumi, Masafumi*; Smolyakov, A. I.*

Journal of Plasma Physics, 72(6), p.1243 - 1248, 2006/12

 Times Cited Count:1 Percentile:96.12(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Statistical characteristics of turbulent plasmas dominated by zonal flows

Matsumoto, Taro; Kishimoto, Yasuaki; Miyato, Naoaki; Li, J.*

Journal of Plasma Physics, 72(6), p.1183 - 1187, 2006/12

 Times Cited Count:6 Percentile:76.31(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Review of recent steady-state advanced tokamak research and its further pursuit by reduction of TF ripple on JT-60U

Shinohara, Koji; JT-60 Team

Journal of the Korean Physical Society, 49, p.S56 - S62, 2006/12

The recent results of JT-60, such as the long discharge with the high normalized beta of 2.3 and the pulse length of 22.3 s which was 13 times longer than the current profile relaxation, and the observation of the increase of D$$alpha$$ emission and electron density as results of wall saturation will be reviewed. Additionally, the motivation and the design work will be reviewd on an on-going recent project of the ferritic insertion for the reduction of the toroidal field ripple. The pioneering works of JFT-2M in the ferritic insertion will be also reported.

Journal Articles

Status and prospect of JT-60 plasma control and diagnostic data processing systems for advanced operation scenarios

Kurihara, Kenichi; Yonekawa, Izuru; Kawamata, Yoichi; Sueoka, Michiharu; Hosoyama, Hiroki*; Sakata, Shinya; Oshima, Takayuki; Sato, Minoru; Kiyono, Kimihiro; Ozeki, Takahisa

Fusion Engineering and Design, 81(15-17), p.1729 - 1734, 2006/07

 Times Cited Count:13 Percentile:29.85(Nuclear Science & Technology)

A large tokamak fusion device JT-60 is expected to explore more advanced tokamak discharge scenario towards the ITER and a future power reactor. We believe the following experimental issues are expected to be solved in JT-60. To clarify how to keep a steady-state plasma with high performance, and how to avoid plasma instabilities almost completely. By stimulus of this motivation, several essential development and modifications of plasma control and data acquisition systems have been performed in JT-60. In this report, we discuss the developments to improve the JT-60 plasma control and data acquisition systems. In addition, a future plasma control and data acquisition systems leading to a standard design for a power reactor is envisaged on the basis of the 20-year plasma operation experiences.

Journal Articles

Stress analyses of the support structure and winding pack of the superconducting TF coil in National Centralized Tokamak

Tsuchiya, Katsuhiko; Kizu, Kaname; Takahashi, Hiroyuki*; Ando, Toshinari*; Matsukawa, Makoto; Tamai, Hiroshi

IEEE Transactions on Applied Superconductivity, 16(2), p.922 - 925, 2006/06

 Times Cited Count:1 Percentile:87.36(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Poloidal field coil configuration and plasma shaping capability in NCT

Matsukawa, Makoto; Tamai, Hiroshi; Fujita, Takaaki; Kizu, Kaname; Sakurai, Shinji; Tsuchiya, Katsuhiko; Kurita, Genichi; Morioka, Atsuhiko; Ando, Toshinari; Miura, Yushi

IEEE Transactions on Applied Superconductivity, 16(2), p.914 - 917, 2006/06

 Times Cited Count:4 Percentile:69.07(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Overview of the national centralized tokamak programme

Kikuchi, Mitsuru; Tamai, Hiroshi; Matsukawa, Makoto; Fujita, Takaaki; Takase, Yuichi*; Sakurai, Shinji; Kizu, Kaname; Tsuchiya, Katsuhiko; Kurita, Genichi; Morioka, Atsuhiko; et al.

Nuclear Fusion, 46(3), p.S29 - S38, 2006/03

 Times Cited Count:13 Percentile:54.28(Physics, Fluids & Plasmas)

The National Centralized Tokamak (NCT) facility program is a domestic research program for advanced tokamak research to succeed JT-60U incorporating Japanese university accomplishments. The mission of NCT is to establish high beta steady-state operation for DEMO and to contribute to ITER. The machine flexibility and mobility is pursued in aspect ratio and shape controllability, feedback control of resistive wall modes, wide current and pressure profile control capability for the demonstration of the high-b steady state.

Journal Articles

Engineering design and control scenario for steady-state high-beta operation in national centralized tokamak

Tsuchiya, Katsuhiko; Akiba, Masato; Azechi, Hiroshi*; Fujii, Tsuneyuki; Fujita, Takaaki; Fujiwara, Masami*; Hamamatsu, Kiyotaka; Hashizume, Hidetoshi*; Hayashi, Nobuhiko; Horiike, Hiroshi*; et al.

Fusion Engineering and Design, 81(8-14), p.1599 - 1605, 2006/02

 Times Cited Count:1 Percentile:89.16(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Characterization of JT-60U exhaust gas during experimental operation

Isobe, Kanetsugu; Nakamura, Hirofumi; Kaminaga, Atsushi; Tsuzuki, Kazuhiro; Higashijima, Satoru; Nishi, Masataka; Kobayashi, Yasunori*; Konishi, Satoshi*

Fusion Engineering and Design, 81(1-7), p.827 - 832, 2006/02

 Times Cited Count:10 Percentile:42.56(Nuclear Science & Technology)

Exhaust gas from JT-60U during experimental operation has been measured with Gas Chromatography (GC), and the gas exhaust characteristic from JT-60U on plasma discharge conditions has been investigated during the JT-60U experimental campaign in 2003-2004. During experimental operation of JT-60U, hydrogen isotope concentration strongly depended on the type of discharges such as high performance, long pulse and so on. On the other hand, impurity species, such as helium, hydrocarbon and carbon oxide, were detected during plasma discharges occasionally. During the experimental operation, plasma disruption remarkably tended to produce high concentration impurities. Glow discharge and Taylor discharge for wall conditioning also produced impurities. In the case of normal plasma, impurity was detected and high performance plasma, such as high $$beta$$ plasma, tended to produce high concentration impurities. This result indicated that impurities concentration might be higher in the case of normal plasma in ITER, because of its high performance.

Journal Articles

Preparation of ITER construction and operation

Shimomura, Yasuo

Fusion Engineering and Design, 81(1-7), p.3 - 11, 2006/02

 Times Cited Count:4 Percentile:66.5(Nuclear Science & Technology)

no abstracts in English

Journal Articles

JFT-2M program

Kusama, Yoshinori; Yamamoto, Masahiro; JFT-2M Group

Fusion Science and Technology, 49(2), p.89 - 95, 2006/02

 Times Cited Count:8 Percentile:46.33(Nuclear Science & Technology)

The experimental program on the JFT-2M tokamak started with the first plasma on April 27, 1983 and was completed in March, 2004. In the series of experiments for 21 years, a lot of significant results leading the fusion energy research and plasma physics have been produced. As the first paper of this special issue on all aspect of JFT-2M, this paper reviews the JFT-2M program.

Journal Articles

Ripple reduction with ferritic insert in JFT-2M

Shinohara, Koji; Sato, Masayasu; Kawashima, Hisato; Tsuzuki, Kazuhiro; Suzuki, Sadaaki; Urata, Kazuhiro*; Isei, Nobuaki; Tani, Takashi; Kikuchi, Kazuo; Shibata, Takatoshi; et al.

Fusion Science and Technology, 49(2), p.187 - 196, 2006/02

 Times Cited Count:7 Percentile:50.82(Nuclear Science & Technology)

In JFT-2M, the toroidal field ripple was reduced by ferritic insert. Two kinds of ripple reduction were carried out. In the first case, ferritic steel was installed between toroidal field coil and vacuum vessel, just under toroidal field coil, outside vacuum vessel. In the second one, ferritic steel was installed inside vacuum vessel covering almost whole inside wall. The ripple was successfully reduced in the both cases. The temperature increment on the first wall measured by infrared TV was also reduced. A new version of OFMC code was also developed to analyze fast ion behavior in the complex structure of the toroidal field. The TF ripple reduction with ferritic insert in JFT-2M is summarized in this article.

Journal Articles

Hydrogen isotopes removal from the vacuum vessel using discharges

Nakamura, Hirofumi; Higashijima, Satoru

Shinku, 49(2), p.62 - 68, 2006/02

no abstracts in English

Journal Articles

Comparison of transient electron heat transport in LHD helical and JT-60U tokamak plasmas

Inagaki, Shigeru*; Takenaga, Hidenobu; Ida, Katsumi*; Isayama, Akihiko; Tamura, Naoki*; Takizuka, Tomonori; Shimozuma, Takashi*; Kamada, Yutaka; Kubo, Shin*; Miura, Yukitoshi; et al.

Nuclear Fusion, 46(1), p.133 - 141, 2006/01

 Times Cited Count:51 Percentile:12.51(Physics, Fluids & Plasmas)

no abstracts in English

763 (Records 1-20 displayed on this page)