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Journal Articles

Present status of manufacturing and R&Ds for the JT-60SA tokamak

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

Fusion Science and Technology, 68(2), p.259 - 266, 2015/09

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

Journal Articles

Fracture mechanics analysis including the butt joint geometry for the superconducting conductor conduit of the national centralized tokamak

Takahashi, Hiroyuki*; Kudo, Yusuke; Tsuchiya, Katsuhiko; Kizu, Kaname; Ando, Toshinari*; Matsukawa, Makoto; Tamai, Hiroshi; Miura, Yukitoshi

Fusion Engineering and Design, 81(8-14), p.1005 - 1011, 2006/02

 Times Cited Count:2 Percentile:81.05(Nuclear Science & Technology)

This paper presents dependence of the stress intensity factor, around the defect in the butt joint welding of a superconducting conductor conduit, on a geometrical factor estimated by fracture mechanics analysis. The stress intensity factor can be estimated by the Newman-Raju equation about CICC section, but the effect of the difference between the geometry assumed in the equation and CICC has not been clarified yet. Therefore, the three-dimensional finite element method (3D-FEM) is performed to estimate the geometrical factor. As a result, the Newman-Raju equation is considered to be available for the assessment of the fracture toughness of the conduit of rectangular shape because the maximum stress intensity factor by 3-D FEM is only 3% larger than that by the Newman-Raju equation in the maximum postulated defect.

Journal Articles

An Approach for development of technical structural standard in ITER

Nakahira, Masataka; Takeda, Nobukazu

Hozengaku, 4(4), p.47 - 52, 2006/01

The technical structural standard for ITER (International Thermonuclear Experimental Fusion Reactor) should be innovative because of their quite different features of safety and mechanical components from nuclear fission reactors, and the necessity of introducing several new fabrication and examination technologies. Recognizing the international importance of Fusion Standard, Japan and ASME has started the cooperation development of the Fusion Standard. This paper shows the special features of ITER from view points of safety, design and fabrication, and proposes approach for development of the fusion standard.

Journal Articles

Updating the design of the feeder components for the ITER magnet system

Yoshida, Kiyoshi; Takahashi, Yoshikazu; Isono, Takaaki; Mitchell, N.*

Fusion Engineering and Design, 75-79, p.241 - 247, 2005/11

 Times Cited Count:10 Percentile:39.42(Nuclear Science & Technology)

The ITER superconducting magnet system stores energy of 50 GJ during plasma operation, and generates an average heat load of 23 kW at 4 K to cryoplant. The helium is distributed to the coil through 30 separate feeder lines. The feeders also contain the electrical supplies to the coil and are integrated into the current lead transition to room temperature. The interface components between the coils and the service facilities (power supply and cryogenic plant) consist of the in-cryostat feeders, the cryostat feedthroughs, and the coil terminal boxes (CTBs). The cryostat feedthroughs with S-bend boxes allow thermal contraction of the magnet system. The layout of the in-cryostat feeders takes into consideration routing restrictions in the cryostat and initial assembly with other Tokamak components. The forced-flow-cooled current leads with a conventional copper heat exchanger in the CTBs are adapted to fit in the limited space in the building. This paper presents the latest design concept and parameters of the feeder components.

Journal Articles

Steady-state operation scenarios with a central current hole for JT-60SC

Tamai, Hiroshi; Ishida, Shinichi; Kurita, Genichi; Shirai, Hiroshi; Tsuchiya, Katsuhiko; Sakurai, Shinji; Matsukawa, Makoto; Sakasai, Akira

Fusion Science and Technology, 45(4), p.521 - 528, 2004/06

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

The 1.5D time-dependent transport analysis has been carried out to investigate steady state operation scenarios with a central current hole by off-axis current drive schemes consistent with a high bootstrap current fraction for a large superconducting tokamak JT-60SC. A steady state operation scenario with HH$$_{y2}$$=1.4 and $$beta$$$$_{N}$$=3.7 has been obtained at I$$_{p}$$=1.5 MA, B$$_{t}$$=2 T and q$$_{95}$$=5 where non-inductive currents are developed during the discharge to form a current hole with beam driven currents by tangential off-axis beams in combination with bootstrap currents by additional on-axis perpendicular beams. The bootstrap fraction increases up to nearly 75% of the plasma current and the current hole region is enlarged up to about 30% of the minor radius at 35 s from the discharge initiation. The current hole is confirmed to be sustained afterward for a long duration of 60 s. The stability analysis shows that the beta limit with the conducting wall can be about $$beta$$$$_{N}$$=4.5, which is substantially above the no wall ideal MHD limit.

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:27.31(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Research activities on Tokamaks in Japan; JT-60U, JFT-2M and TRIAM-1M

Ninomiya, Hiromasa; Kitsunezaki, Akio; Shimizu, Masatsugu; Kuriyama, Masaaki; JT-60 Team; Kimura, Haruyuki; Kawashima, Hisato; Tsuzuki, Kazuhiro; Sato, Masayasu; Isei, Nobuaki; et al.

Fusion Science and Technology, 42(1), p.7 - 31, 2002/07

 Times Cited Count:12 Percentile:75.76(Nuclear Science & Technology)

In order to establish scientific basis for the sustainment of highly integrated performance required in the advanced steady-state operation, JT-60U has been optimizing the discharge control scenarios of improved confinement plasmas and expanding the operation regions. Promising results toward the steady-state tokamak were obtained. The detail of such results is reported. JFT-2M has performed advanced and basic research for the development of high performance tokamak plasma as well as the structural material for a fusion reactor. The toroidal ripple reduction with ferritic steel plates outside the vacuum vessel was successfully demonstrated. No adverse effects were observed in the pre-testing on compatibility between ferritic steel plates, covering ~20% of the inside wall of the vacuum vessel, and plasma. The results of TRIAM-1M is also reported.

Journal Articles

Analytical studies on hotspot temperature of cable-in-conduit conductors

Yoshida, Kiyoshi; Takigami, Hiroyuki*; Kubo, Hiroatsu*

Teion Kogaku, 36(11), p.617 - 625, 2001/11

no abstracts in English

Journal Articles

Analytical studies on the hotspot temperature of cable-in-conduit conductors

Yoshida, Kiyoshi; Takigami, Hiroyuki*; Kubo, Hiroatsu*

Cryogenics, 41(8), p.583 - 594, 2001/08

 Times Cited Count:8 Percentile:60.58(Thermodynamics)

no abstracts in English

Journal Articles

Design of the pancake-winding central solenoid coil

Yoshida, Kiyoshi; Nishi, Masataka; Tsuji, Hiroshi; Sasaki, Takashi*; Yasukawa, Yukio*; Tsukamoto, Hideo*; *; *; *; Hasegawa, Mitsuru*

Nippon Genshiryoku Gakkai-Shi, 37(10), p.938 - 947, 1995/00

 Times Cited Count:2 Percentile:70.67(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Verification tsets of the Nb$$_{3}$$Sn demo poloidal coil(DPC-EX)

Takahashi, Yoshikazu; Ando, Toshinari; Nishi, Masataka; Tsuji, Hiroshi; Hiyama, Tadao; Okuno, Kiyoshi; Yoshida, Kiyoshi; Nakajima, Hideo; Koizumi, Koichi; Tada, Eisuke; et al.

Proc. of the 11th Int. Conf. on Magnet Technology,Vol. 2, p.862 - 867, 1990/00

no abstracts in English

Journal Articles

Development of large superconducting coils for fusion reactors

;

Kaku Yugo Kenkyu, 57(3), p.139 - 154, 1987/03

no abstracts in English

Journal Articles

Design selections for the fabrication of the demonstration poloidal coil

Tsuji, Hiroshi; ; ; ; ; ; ; ; ; Kato, Takashi; et al.

Transactions of the American Nuclear Society, 52, P. 311, 1986/00

no abstracts in English

Journal Articles

A 16-T superconducting toroidal coil development for a tokamak fusion machine

Nishi, Masataka; ; ; Hiyama, Tadao; Kawano, Katsumi; *;

Transactions of the American Nuclear Society, 52, p.310 - 311, 1986/00

no abstracts in English

JAEA Reports

Mechanical Study of 20MJ Superconducting Pulse Coil

*;

JAERI-M 85-147, 48 Pages, 1985/09

JAERI-M-85-147.pdf:0.93MB

no abstracts in English

Journal Articles

The experimental results of the domestic tests of the pool boiling cooled Japanese and the forced flow cooled euratom LCT coils

; ; A.Ulbricht*; P.Komarek*; H.Katheder*; F.Wuechner*; G.R.Zahn*

Teion Kogaku, 20(6), p.337 - 349, 1985/00

no abstracts in English

JAEA Reports

Design,Construction and Experiment of the Claster Test Fasility

; ; Hiyama, Tadao; ; ; ; ; ; ; ; et al.

JAERI-M 82-044, 189 Pages, 1982/06

JAERI-M-82-044.pdf:5.06MB

no abstracts in English

JAEA Reports

24 (Records 1-20 displayed on this page)