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Journal Articles

Design study of superconducting coils for the fusion DEMO plant at JAERI

Isono, Takaaki; Koizumi, Norikiyo; Okuno, Kiyoshi; Kurihara, Ryoichi; Nishio, Satoshi; Tobita, Kenji

Fusion Engineering and Design, 81(8-14), p.1257 - 1261, 2006/02

 Times Cited Count:5 Percentile:37.94(Nuclear Science & Technology)

In order to realize an economically competitive power generation system, generation of a higher field is required. Toroidal Field (TF) coils of fusion DEMO plant at JAERI are required to generate magnetic field of 16 to 20 T. To realize this high field, advanced superconducting materials, such as Nb$$_3$$Al and high temperature superconductor (HTS), are considered. HTS has enough performance in a 20-T field at 4 K, and a forced-cooled type HTS conductor using a silver alloy sheathed Bi-2212 round wire has been proposed. Required areas of superconductor, structure, stabilizer, coolant and insulator in the cross section of coil winding have been calculated. However, there are many technical issues to be solved, such as accurate temperature control during heat treatment in an atmosphere of oxygen. On the other hand, a large coil using Nb$$_3$$Al has been developed by JAERI, and major technology to fabricate a 16-T Nb$$_3$$Al coil was developed. Validity and issues of grading the winding area are discussed, and there is a possibility to increase a field up to around 17 T using the method.

Journal Articles

Test results of 60-kA HTS current lead for fusion application

Isono, Takaaki; Kawano, Katsumi; Hamada, Kazuya; Matsui, Kunihiro; Nunoya, Yoshihiko; Hara, Eiji*; Kato, Takashi; Ando, Toshinari*; Okuno, Kiyoshi; Bono, Takaaki*; et al.

Physica C, 392-396(Part2), p.1219 - 1224, 2003/10

A 60-kA high-temperature-superconductor (HTS) current lead has been fabricated and tested for aiming at the application to a fusion magnet system, providing a low heat leak current lead. The design of HTS current leads is optimized not only to reduce the heat leak but also to perform safe operation even in fault conditions. The HTS current lead consists of a forced flow cooled copper part and a conduction cooled HTS part. The HTS part is composed of 288 Ag-10at.%Au sheathed Bi-2223 tapes and they are cylindrically arrayed on a stainless steel tube. The diameter and the length of the HTS part are 146 mm and 300 mm, respectively. Operation of a 60 kA current, which is the world record, was successfully achieved at coolant of 20 K, 3.2 g/s for the copper part, and a low heat leak of 5.5 W at 4.2 K was demonstrated. This result shows that the electric power of a refrigerator to cool the current lead can be reduced by 1/3 of that in a conventional current lead. In conclusion, technology of a large HTS current lead for fusion application is established.

Journal Articles

Development of 10kA Bi2212 conductor for fusion application

Isono, Takaaki; Nunoya, Yoshihiko; Ando, Toshinari*; Okuno, Kiyoshi; Ono, Michitaka*; Ozaki, Akira*; Koizumi, Tsutomu*; Otani, Nozomu*; Hasegawa, Takayo*

IEEE Transactions on Applied Superconductivity, 13(2), p.1512 - 1515, 2003/06

 Times Cited Count:20 Percentile:67.52(Engineering, Electrical & Electronic)

Japan Atomic Energy Research Institute has started development work on a large current conductor using high Tc superconductor (HTS) aiming at a fusion power reactor after the International Thermonuclear Experimental Reactor (ITER). HTS has a capability to produce a magnetic field of higher than 16 T, which is required in such a fusion power reactor. A trial fabrication of a 10-kA 12-T conductor was started using round Ag-alloy sheathed Bi-2212 strands, which has best performance at 4.2K, 16T at present. The conductor has about 34-mm diameter, and is composed of 729 HTS strands. Operating temperature is designed at not only 4 K but also 20K. The conductor sample is indirectly cooled and is solder-coated on the surface to use specific heat of the lead as much as possible, which at 20 K is almost comparable with specific heat of SHe at 4.5K, 0.6MPa. From the tests of the conductor, the fabrication of large HTS conductor and 10kA operation at 12 T and about 12.5 K were successfully performed and the possibility of HTS to use fusion application was demonstrated.

JAEA Reports

Non-uniform current distribution in a force-cooled superconductor under changing magnetic field

Koizumi, Norikiyo

JAERI-Research 99-076, p.198 - 0, 2000/02

JAERI-Research-99-076.pdf:13.19MB

no abstracts in English

Journal Articles

Development of the central solenoid model coil for the ITER using Nb$$_{3}$$Sn superconductors

Ando, Toshinari

Denki Gakkai Genshiryoku Gijutsu Kenkyukai Shiryo NE-99-5, p.23 - 28, 1999/00

no abstracts in English

Journal Articles

Development of the toroidal field coil conductor using Nb$$_{3}$$Al superconductor

Koizumi, Norikiyo

Denki Gakkai Genshiryoku Gijutsu Kenkyukai Shiryo NE-99-6, p.29 - 34, 1999/00

no abstracts in English

Journal Articles

Charging test results of the DPC-TJ, a high-current-density large superconducting coil for fusion machines

*; Wachi, Y.*; Shimada, M.*; *; *; Hamajima, Takataro*; Fujioka, T.*; Nishi, Masataka; Tsuji, Hiroshi; Ando, Toshinari; et al.

IEEE Transactions on Applied Superconductivity, 3(1), p.480 - 483, 1993/03

 Times Cited Count:4 Percentile:45.98(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Fabrication of superconductor for the DPC-TJ coil

Aoki, Nobuo*; *; *; *; Shimada, M.*; Hamajima, Takataro*; *; Fujioka, T.*; Takahashi, Yoshikazu; Ando, Toshinari; et al.

Cryogenics, 33(6), p.581 - 585, 1993/00

 Times Cited Count:2 Percentile:18.34(Thermodynamics)

no abstracts in English

Journal Articles

The DPC-TJ program; Development of a high-current-density large superconducting coil for fusion machines

Nishi, Masataka; Ando, Toshinari; Tsuji, Hiroshi; *; Hamajima, Takataro*; Fujioka, T.*

Teion Kogaku, 27(3), p.207 - 216, 1992/00

no abstracts in English

Journal Articles

Fabrication of the superconductor for the DPC-TJ coil

Aoki, Nobuo*; *; *; *; Shimada, M.*; Hamajima, Takataro*; *; Fujioka, T.*; Takahashi, Yoshikazu; Ando, Toshinari; et al.

Teion Kogaku, 27(3), p.221 - 225, 1992/00

no abstracts in English

Journal Articles

Development of the proto-type conductors and design of the test coil for the fusion experimental reactor

Nishi, Masataka; Takahashi, Yoshikazu; Isono, Takaaki; *; Yoshida, Kiyoshi; Koizumi, Koichi; Tada, Eisuke; Tsuji, Hiroshi; Okuno, Kiyoshi; Ando, Toshinari; et al.

Proc. of IEEE 13th Symp. on Fusion Engineering,Vol. 1, p.780 - 783, 1990/00

no abstracts in English

Journal Articles

Results of verification tests and coil test of DPC-TJ

Nishi, Masataka; Tsuji, Hiroshi; Takahashi, Yoshikazu; Nakajima, Hideo; Isono, Takaaki; Ando, Toshinari; Shimamoto, Susumi; *; Hamajima, Takataro*; *; et al.

Proc. of the 11th Int. Conf. on Magnet Technology,Vol. 2, p.856 - 861, 1990/00

no abstracts in English

Journal Articles

Large area ion source

Okumura, Yoshikazu

Kino Zairyo, 0(7), p.42 - 53, 1989/07

no abstracts in English

14 (Records 1-14 displayed on this page)
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