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Journal Articles

Proposals for the final design of the ITER central solenoid

Yoshida, Kiyoshi; Takahashi, Yoshikazu; Mitchell, N.*; Bessette, D.*; Kubo, Hiroatsu*; Sugimoto, Makoto; Nunoya, Yoshihiko; Okuno, Kiyoshi

IEEE Transactions on Applied Superconductivity, 14(2), p.1405 - 1409, 2004/06

 Times Cited Count:16 Percentile:37.74(Engineering, Electrical & Electronic)

The ITER Central Solenoid (CS) is 12m high and 4m in diameter. The CS consists of a stack of 6electrically independent modules to allow control of plasma shape. The modules are compressed vertically by a pre-compression structure to maintain contact between modules. The CS conductor is CIC conductor with Nb$$_{3}$$Sn strands and a steel conduit. The CS model coil and insert coil test results have shown that the conductor design must be modified to achieve an operation margin. This required either to increase the cable diameter or to use strand with a higher current capability. A bronze-process (NbTi)$$_{3}$$Sn strand is proposed to achieve a higher critical magnetic field. A square conduit with a high Mn stainless steel is proposed as it can satisfy fatigue requirements. The inlets are in the high stress region and any stress intensification there must be minimized. The pre-compression structure is composed of 9tie plates to reduce the stress on the cooling pipes. These design proposals satisfy all ITER operational requirements.

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:87.89(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Acoustic emission and disturbances in central solenoid model coil for international thermonuclear experimental reactor

Arai, K.*; Ninomiya, Akira*; Ishigooka, Takeshi*; Takano, Katsutoshi*; Nakajima, Hideo; Michael, P.*; Vieira, R.*; Martovetsky, N.*; Sborchia, C.*; Alekseev, A.*; et al.

Cryogenics, 44(1), p.15 - 27, 2004/01

 Times Cited Count:3 Percentile:83.49(Thermodynamics)

no abstracts in English

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.

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

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

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:60.62(Thermodynamics)

no abstracts in English

Journal Articles

Experimental results of CS model coil; Mechanical performance

Sugimoto, Makoto; Nakajima, Hideo; Tsuchiya, Yoshinori; Kubo, Hiroatsu*; CS Model Coil Test Group

Teion Kogaku, 36(6), p.336 - 343, 2001/06

no abstracts in English

Journal Articles

Progress of the ITER central solenoid model coil programme

Tsuji, Hiroshi; Okuno, Kiyoshi*; Thome, R.*; Salpietro, E.*; Egorov, S. A.*; Martovetsky, N.*; Ricci, M.*; Zanino, R.*; Zahn, G.*; Martinez, A.*; et al.

Nuclear Fusion, 41(5), p.645 - 651, 2001/05

 Times Cited Count:53 Percentile:15.76(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Fabrication of ITER central solenoid model coil-outer module

Ando, Toshinari; Hiyama, Tadao; Takahashi, Yoshikazu; Nakajima, Hideo; Kato, Takashi; Sugimoto, Makoto; Isono, Takaaki; Kawano, Katsumi; Koizumi, Norikiyo; Hamada, Kazuya; et al.

IEEE Transactions on Applied Superconductivity, 9(2), p.628 - 631, 1999/06

 Times Cited Count:7 Percentile:50.38(Engineering, Electrical & Electronic)

no abstracts in English

JAEA Reports

Design of correction coil for ITER

Kubo, Hiroatsu*; Omine, T.*; Yoshida, Kiyoshi

JAERI-Tech 98-050, 69 Pages, 1998/11

JAERI-Tech-98-050.pdf:1.88MB

no abstracts in English

11 (Records 1-11 displayed on this page)
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