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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:41.76(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:9.98(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:45.53(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

Application of react-and-wind method to D-shaped test coil using the 20 kA Nb$$_{3}$$Al conductor developed for JT-60SC

Kizu, Kaname; Miura, Yushi; Tsuchiya, Katsuhiko; Koizumi, Norikiyo; Matsui, Kunihiro; Ando, Toshinari*; Hamada, Kazuya; Hara, Eiji*; Imahashi, Koichi*; Ishida, Shinichi; et al.

IEEE Transactions on Applied Superconductivity, 14(2), p.1535 - 1538, 2004/06

 Times Cited Count:1 Percentile:11.57(Engineering, Electrical & Electronic)

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:6.49(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

Development of the Nb$$_{3}$$Al D-shaped coil fabricated by react-and-wind method for JT-60 superconducting Tokamak

Kizu, Kaname; Miura, Yushi; Tsuchiya, Katsuhiko; Koizumi, Norikiyo; Matsui, Kunihiro; Ando, Toshinari*; Hamada, Kazuya; Hara, Eiji*; Imahashi, Koichi*; Ishida, Shinichi; et al.

Proceedings of 6th European Conference on Applied Superconductivity (EUCAS 2003), p.400 - 407, 2003/00

Toroidal field coils (TFC) of the JT-60SC consist of 18 D-shape coils. The maximum magnetic field is 7.4 T at an operational current of 19.4 kA. An advanced Nb$$_{3}$$Al superconductor was developed for the TFC conductor material in JAERI. The Nb$$_{3}$$Al has lower strain sensitivity on superconducting performances, and allows us to fabricate the TFC by react-and-wind (R&W) method that makes that the coil fabrication with high reliability becomes easier and the fabrication cost becomes lower. To demonstrate the coil fabrication by R&W method, a two-turn D-shape coil was developed. The D-shape coil was tested at 4.3-4.4K and 7-12T. Measured critical current (Ic) was 30 kA at 7.3 T and 4.4 K. Using the measured conductor and strand Ic values, the strain of the conductor was estimated to be -0.6%. The Ic-B-T characteristic expected by an empirical equation substituting this strain shows that the required temperature margin for TFC is satisfied. Thus, the R&W method was demonstrated to be the applicable fabrication method of the TFC.

Oral presentation

Development of waste disposal system for sustainable nuclear power programme, 4; Development of methodology for optimisation of waste disposal

Makino, Hitoshi; Hioki, Kazumasa; Umeki, Hiroyuki; Sugiyama, Naoki; Ochi, Yasuhiro; Okazaki, Wataru; Naito, Morimasa; Miyahara, Kaname; Okubo, Hiroo*; Ishihara, Yoshinao*

no journal, , 

This presentation will introduce developmenmt of methodology for optimisation of waste disposal considering variation of waste charcteristics from LWR cycle and also advanced cycle.

Oral presentation

Strontium decontamination from the contaminated water containing seawater by titanium oxide adsorption, 2; Preparation and mutual separation of alkaline earths

Koma, Yoshikazu; Takahatake, Yoko; Ohata, Fumikazu; Nakajima, Yasuo; Kaneko, Masashi*; Kubo, Kaname*; Hashimoto, Jun*

no journal, , 

Titanate oxide hydrates were prepared base on two methods and their properties on adsorption of Sr were examined. Adsorption of Sr was fast and a difference on adsorption between the preparation method was observed. Selectivity among alkaline earth metals were similar.

Oral presentation

Strontium decontamination from the contaminated water containing seawater by titanium oxide adsorption, 3; Behavior of some components contained in the contaminated water

Koma, Yoshikazu; Takahatake, Yoko; Ohata, Fumikazu; Nakajima, Yasuo; Kaneko, Masashi*; Kubo, Kaname*; Hashimoto, Jun*

no journal, , 

Adsorption of metals contained in the contaminated water onto the titanium oxide adsorbent was examined by using the solution resulted from ferrocyanide decontamination. Decontamination effect for Co and Sb as well as Sr was confirmed.

Oral presentation

Strontium decontamination from the contaminated water containing seawater by titanium oxide adsorbent; An Influence for separation and crystal structures by changes of dehydration temperature of sodium titanate

Ogawa, Tsuyoshi; Takahatake, Yoko; Koma, Yoshikazu; Nakajima, Yasuo; Sano, Kyohei*; Arai, Tsuyoshi*; Hashimoto, Jun*; Kubo, Kaname*; Kaneko, Masashi*

no journal, , 

no abstracts in English

Oral presentation

Development of titanate adsorbent with silica gel support, 1; Column property of adsorbent and Sr adsorption ability

Takahatake, Yoko; Shibata, Atsuhiro; Koma, Yoshikazu; Nakajima, Yasuo; Sano, Kyohei*; Arai, Tsuyoshi*; Hashimoto, Jun*; Kubo, Kaname*; Kaneko, Masashi*

no journal, , 

no abstracts in English

Oral presentation

Development of titanate adsorbent with silica gel support, 2; Optimization of the immersion regent concentration

Hashimoto, Jun*; Kubo, Kaname*; Kaneko, Masashi*; Arai, Tsuyoshi*; Takahatake, Yoko; Shibata, Atsuhiro; Koma, Yoshikazu; Nakajima, Yasuo

no journal, , 

no abstracts in English

13 (Records 1-13 displayed on this page)
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