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Journal Articles

Status of JT-60SA tokamak under the EU-JA broader approach agreement

Matsukawa, Makoto; Kikuchi, Mitsuru; Fujii, Tsuneyuki; Fujita, Takaaki; Hayashi, Takao; Higashijima, Satoru; Hosogane, Nobuyuki; Ikeda, Yoshitaka; Ide, Shunsuke; Ishida, Shinichi; et al.

Fusion Engineering and Design, 83(7-9), p.795 - 803, 2008/12

 Times Cited Count:15 Percentile:25.93(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Superconducting tokamak JT-60SA project for ITER and DEMO researches

Hosogane, Nobuyuki; JT-60SA Design Team; JA-EU Satellite Tokamak Working Group

Fusion Science and Technology, 52(3), p.375 - 382, 2007/10

 Times Cited Count:6 Percentile:53.68(Nuclear Science & Technology)

JT-60SA is a superconducting tokamak with wide flexibility in plasma shape and single/double null divertors, capable of confining break-even class high temperature plasma for 100 s with intensive heating power of 41 MW. The design of JT-60SA is based on the National Centralized Tokamak NCT, and has been proposed as an ITER satellite tokamak in the 10 years Broader Approach (BA) program between Japan and Europe. The JT-60SA project is a combination of the BA project and the NCT project. The former mission is to support ITER by developing an understanding of physics issues, optimizing operation scenarios etc.. The latter mission is mainly to explore steady state, high beta DEMO relevant scenarios. The construction period is 7 years and 3 years will be devoted to experimental studies with a possibility of extension. The detail design of JT-60SA is progressing under their collaboration. Overview of the project and machine design is presented.

Journal Articles

Overview of national centralized tokamak program; Mission, design and strategy to contribute ITER and DEMO

Ninomiya, Hiromasa; Akiba, Masato; Fujii, Tsuneyuki; Fujita, Takaaki; Fujiwara, Masami*; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Hosogane, Nobuyuki; Ikeda, Yoshitaka; Inoue, Nobuyuki; et al.

Journal of the Korean Physical Society, 49, p.S428 - S432, 2006/12

To contribute DEMO and ITER, the design to modify the present JT-60U into superconducting coil machine, named National Centralized Tokamak (NCT), is being progressed under nationwide collaborations in Japan. Mission, design and strategy of this NCT program is summarized.

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

Design study of national centralized tokamak facility for the demonstration of steady state high-$$beta$$ plasma operation

Tamai, Hiroshi; Akiba, Masato; Azechi, Hiroshi*; Fujita, Takaaki; Hamamatsu, Kiyotaka; Hashizume, Hidetoshi*; Hayashi, Nobuhiko; Horiike, Hiroshi*; Hosogane, Nobuyuki; Ichimura, Makoto*; et al.

Nuclear Fusion, 45(12), p.1676 - 1683, 2005/12

 Times Cited Count:15 Percentile:50.76(Physics, Fluids & Plasmas)

Design studies are shown on the National Centralized Tokamak facility. The machine design is carried out to investigate the capability for the flexibility in aspect ratio and shape controllability for the demonstration of the high-beta steady state operation with nation-wide collaboration, in parallel with ITER towards DEMO. Two designs are proposed and assessed with respect to the physics requirements such as confinement, stability, current drive, divertor, and energetic particle confinement. The operation range in the aspect ratio and the plasma shape is widely enhanced in consistent with the sufficient divertor pumping. Evaluations of the plasma performance towards the determination of machine design are presented.

Journal Articles

Recent technological progress for advanced tokamak research in JT-60U and JFT-2M

Hosogane, Nobuyuki; JT-60 Team; JFT-2M Group

Fusion Science and Technology, 47(3), p.363 - 369, 2005/04

 Times Cited Count:3 Percentile:73.52(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Progress in physics and technology developments for the modification of JT-60

Tamai, Hiroshi; Matsukawa, Makoto; Kurita, Genichi; Hayashi, Nobuhiko; Urata, Kazuhiro*; Miura, Yushi; Kizu, Kaname; Tsuchiya, Katsuhiko; Morioka, Atsuhiko; Kudo, Yusuke; et al.

Plasma Science and Technology, 6(1), p.2141 - 2150, 2004/02

 Times Cited Count:2 Percentile:92.85(Physics, Fluids & Plasmas)

The dominant issue for the the modification program of JT-60 (JT-60SC) is to demonstrate the steady state reactor relevant plasma operation. Physics design on plasma parameters, operation scenarios, and the plasma control method are investigated for the achievement of high-$$beta$$. Engineering design and the R&D on the superconducting magnet coils, radiation shield, and vacuum vessel are performed. Recent progress in such physics and technology developments is presented.

Journal Articles

Objectives and design of the JT-60 superconducting tokamak

Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Chujo, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.

Nuclear Fusion, 43(7), p.606 - 613, 2003/07

no abstracts in English

Journal Articles

Objectives and design of the JT-60 superconducting tokamak

Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Cho, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.

Nuclear Fusion, 43(7), p.606 - 613, 2003/07

 Times Cited Count:33 Percentile:27.44(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Gas and pellet injection systems for JT-60 and JT-60U

Kizu, Kaname; Hiratsuka, Hajime; Miyo, Yasuhiko; Ichige, Hisashi; Sasajima, Tadayuki; Nishiyama, Tomokazu; Masaki, Kei; Honda, Masao; Miya, Naoyuki; Hosogane, Nobuyuki

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.396 - 409, 2002/09

 Times Cited Count:4 Percentile:68.96(Nuclear Science & Technology)

Designs and operations of the gas system and pellet injection systems for JT-60 were described. A gas injection valve that is a key component of the gas injection system was developed using a multi layer piezoelectric element. The maximum flow rate of this system is 43.3 Pam3/s. The valve has mechanism for adjustment at atmospheric side meaning that a repair and an adjustment can be conducted without ventilation inside a vacuum vessel. Two systems of pellet injector; one is pneumatic drive and another is centrifugal one were developed. The pneumatic type attained a pellet velocity of 2.3 km/s, which was the world record at the time in 1988. On the other hand, the centrifugal one was developed in 1998. This injector can eject trains of up to 40 cubic (2.1 mm)3 pellets at frequencies of 1~10 Hz and speed of 0.1~1.0 km/s. A guide tube for a magnetic high field side top injection HFS(top)) was also developed in 1999. The pellet injection experiment with the HFS system started in 2000. In addition, another guide tube for HFS(mid) injection was newly developed and installed in March 2001.

Journal Articles

Heat and particle control in JT-60U

Takenaga, Hidenobu; Kubo, Hirotaka; Higashijima, Satoru; Asakura, Nobuyuki; Sugie, Tatsuo; Konoshima, Shigeru; Shimizu, Katsuhiro; Nakano, Tomohide; Itami, Kiyoshi; Sakasai, Akira; et al.

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.327 - 356, 2002/09

 Times Cited Count:10 Percentile:81.82(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Fusion plasma performance and confinement studies on JT-60 and JT-60U

Kamada, Yutaka; Fujita, Takaaki; Ishida, Shinichi; Kikuchi, Mitsuru; Ide, Shunsuke; Takizuka, Tomonori; Shirai, Hiroshi; Koide, Yoshihiko; Fukuda, Takeshi; Hosogane, Nobuyuki; et al.

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.185 - 254, 2002/09

 Times Cited Count:27 Percentile:51.52(Nuclear Science & Technology)

With the main aim of providing physics basis for ITER and the steady-state tokamak reactors, JT-60/JT-60U has been developing and optimizing the operational concepts, and extending the discharge regimes toward sustainment of high integrated performance in the reactor relevant parameter regime. In addition to achievement of the equivalent break-even condition (QDTeq up to 1.25) and a high fusion triple product = 1.5E21 m-3skeV, JT-60U has demonstrated the integrated performance of high confinement, high beta-N, full non-inductive current drive with a large fraction of bootstrap current in the reversed magnetic shear and in the high-beta-p ELMy H mode plasmas characterized by both internal and edge transport barriers. The key factors in optimizing these plasmas are profile and shape controls. As represented by discovery of various Internal Transport Barriers, JT-60/JT-60U has been emphasizing freedom and restriction of profiles in various confinement modes. JT-60U has demonstrated applicability of these high confinement modes to ITER and also clarified remaining issues.

Journal Articles

Development and operational experiences of the JT-60U tokamak and power supplies

Hosogane, Nobuyuki; Ninomiya, Hiromasa; Matsukawa, Makoto; Ando, Toshiro; Neyatani, Yuzuru; Horiike, Hiroshi*; Sakurai, Shinji; Masaki, Kei; Yamamoto, Masahiro; Kodama, Kozo; et al.

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.368 - 385, 2002/09

 Times Cited Count:2 Percentile:82.04(Nuclear Science & Technology)

This paper reviews developments of the JT-60U tokamak and coil power supplies and their operational experiences obtained to date. The JT-60U is a large tokamak upgraded from the original JT-60 to obtain high plasma current, large plasma volume and highly elongated divertor configurations. In the modification, all components inside the bore of toroidal magnetic field coils, a vacuum vessel, poloidal magnetic field coils (PF-coils), divertor etc., were renewed. Furthermore, boron carbide converted CFC tiles were used as divertor tiles to reduce erosion of carbon-base tiles. Later, a semi-closed divertor with pumps was installed in the replacement of the open divertor. Various technologies and ideas introduced to develop these components their operational experiences provide important data for designing future tokamaks. Also, major troubles that had influence on the JT-60U operations are described. As a maintenance issue for tokamaks using deuterium fueling gas, a method for reducing radiation exposure of in-vessel workers are introduced.

JAEA Reports

Development of multilayer piezoelectric actuator valve for JT-60

Miyo, Yasuhiko; Hiratsuka, Hajime; Masui, Hiroshi*; Hosogane, Nobuyuki; Miya, Naoyuki

JAERI-Tech 2001-070, 33 Pages, 2001/11

JAERI-Tech-2001-070.pdf:3.02MB

In order to improve the gas injection valve used for the operation of JT-60, a new type of valve (multilayer piezoelectric actuator valve) was developed .The conventional valve (bimorph piezoelectric actuator valve) has been used for 15 years from the beginning of experimental operation in April, 1985. Consequently, it came to be hard to keep the performance of the valve as a gas injector because its driving source, piezoelectric element, has deteriorated by long time use.In the design, it is required:(1) to be hard structure for sheet leak,(2) to allow a repair work at atmosphere side without an air vent of the vacuumvessel,(3) to be more smaller and lighter compaired with the conventional one,(4) to have a high maintenance efficiency. The new valve developed was examined with various tests such as gas flow characteristic test, high magnetic field proof test, high temperature proof test and gas flow rate test for aged deterioration. As a result, the valve with desired performance for JT-60 could be obtained.

Journal Articles

A Repetitive pellet injection system for JT-60U

Kizu, Kaname; Hosogane, Nobuyuki; Hiratsuka, Hajime; Ichige, Hisashi; Sasajima, Tadayuki; Masaki, Kei; Miya, Naoyuki; Honda, Masao; Iwahashi, Takaaki*; Sasaki, Noboru*; et al.

Fusion Engineering and Design, 58-59, p.331 - 335, 2001/11

 Times Cited Count:15 Percentile:26.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Progress of JT-60U facilities and experimental research toward steady high performance plasmas

Hosogane, Nobuyuki; JT-60 Team

Fusion Engineering and Design, 56-57, p.813 - 817, 2001/10

 Times Cited Count:2 Percentile:79.11(Nuclear Science & Technology)

no abstracts in English

Journal Articles

First test results for the ITER central solenoid model coil

Kato, Takashi; Tsuji, Hiroshi; Ando, Toshinari; Takahashi, Yoshikazu; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; Kawano, Katsumi; Oshikiri, Masayuki*; et al.

Fusion Engineering and Design, 56-57, p.59 - 70, 2001/10

 Times Cited Count:17 Percentile:22.58(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Pulse operation test of the ITER central solenoid model coil using the JT-60 power supply

Terakado, Tsunehisa; Okano, Jun; Shimada, Katsuhiro; Miura, Yushi; Yamashita, Yoshiki*; Matsukawa, Makoto; Hosogane, Nobuyuki; Tsuji, Hiroshi; Ando, Toshinari*; Takahashi, Yoshikazu; et al.

JAERI-Tech 2001-056, 24 Pages, 2001/08

JAERI-Tech-2001-056.pdf:1.17MB

no abstracts in English

Journal Articles

Tomographic reconstruction of bolometry for JT-60U diverted tokamak characterization

Konoshima, Shigeru; Leonard, A. W.*; Ishijima, Tatsuo*; Shimizu, Katsuhiro; Kamata, Isao*; Meyer, W. H.*; Sakurai, Shinji; Kubo, Hirotaka; Hosogane, Nobuyuki; Tamai, Hiroshi

Plasma Physics and Controlled Fusion, 43(7), p.959 - 983, 2001/07

 Times Cited Count:27 Percentile:33.64(Physics, Fluids & Plasmas)

no abstracts in English

136 (Records 1-20 displayed on this page)