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Journal Articles

Design of the superconducting coil system in JT-60SA

Tsuchiya, Katsuhiko; Kizu, Kaname; Ando, Toshinari*; Tamai, Hiroshi; Matsukawa, Makoto

Fusion Engineering and Design, 82(5-14), p.1519 - 1525, 2007/10

 Times Cited Count:4 Percentile:65.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation of bending strain dependence of critical current of Nb$$_{3}$$Al conductor for coils with react-and-wind method

Kizu, Kaname; Tsuchiya, Katsuhiko; Shimada, Katsuhiro; Ando, Toshinari*; Hishinuma, Yoshimitsu*; Koizumi, Norikiyo; Matsukawa, Makoto; Miura, Yushi*; Nishimura, Arata*; Okuno, Kiyoshi; et al.

Fusion Engineering and Design, 82(5-14), p.1493 - 1499, 2007/10

 Times Cited Count:3 Percentile:72.14(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Conceptual design of magnet system for JT-60 super advanced (JT-60SA)

Kizu, Kaname; Tsuchiya, Katsuhiko; Ando, Toshinari*; Sborchia, C.*; Masaki, Kei; Sakurai, Shinji; Sukegawa, Atsuhiko; Tamai, Hiroshi; Fujita, Takaaki; Matsukawa, Makoto; et al.

IEEE Transactions on Applied Superconductivity, 17(2), p.1348 - 1352, 2007/06

 Times Cited Count:4 Percentile:68.55(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Stress analyses of the support structure and winding pack of the superconducting TF coil in National Centralized Tokamak

Tsuchiya, Katsuhiko; Kizu, Kaname; Takahashi, Hiroyuki*; Ando, Toshinari*; Matsukawa, Makoto; Tamai, Hiroshi

IEEE Transactions on Applied Superconductivity, 16(2), p.922 - 925, 2006/06

 Times Cited Count:1 Percentile:87.26(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Effects of tensile and compressive strain on critical currents of Nb$$_{3}$$Al strand and cable-in-conduit conductor

Kizu, Kaname; Tsuchiya, Katsuhiko; Shimada, Katsuhiro; Ando, Toshinari*; Hishinuma, Yoshimitsu*; Koizumi, Norikiyo; Matsukawa, Makoto; Miura, Yushi*; Nishimura, Arata*; Okuno, Kiyoshi; et al.

IEEE Transactions on Applied Superconductivity, 16(2), p.872 - 875, 2006/06

 Times Cited Count:1 Percentile:87.26(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Poloidal field coil configuration and plasma shaping capability in NCT

Matsukawa, Makoto; Tamai, Hiroshi; Fujita, Takaaki; Kizu, Kaname; Sakurai, Shinji; Tsuchiya, Katsuhiko; Kurita, Genichi; Morioka, Atsuhiko; Ando, Toshinari; Miura, Yushi

IEEE Transactions on Applied Superconductivity, 16(2), p.914 - 917, 2006/06

 Times Cited Count:4 Percentile:68.89(Engineering, Electrical & Electronic)

no abstracts in English

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:81.1(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

Effective bending strain estimated from $$I$$$$_{c}$$ test results of a D-shaped Nb$$_{3}$$Al CICC coil fabricated with a react-and-wind process for the National Centralized Tokamak

Ando, Toshinari*; Kizu, Kaname; Miura, Yushi*; Tsuchiya, Katsuhiko; Matsukawa, Makoto; Tamai, Hiroshi; Ishida, Shinichi; Koizumi, Norikiyo; Okuno, Kiyoshi

Fusion Engineering and Design, 75-79, p.99 - 103, 2005/11

 Times Cited Count:1 Percentile:88.49(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of advanced superconducting coil technologies for the National Centralized Tokamak

Kizu, Kaname; Miura, Yushi*; Tsuchiya, Katsuhiko; Ando, Toshinari*; Koizumi, Norikiyo; Matsui, Kunihiro*; Sakasai, Akira; Tamai, Hiroshi; Matsukawa, Makoto; Ishida, Shinichi; et al.

Nuclear Fusion, 45(11), p.1302 - 1308, 2005/11

 Times Cited Count:4 Percentile:84.35(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Design and stress analysis of support structure of toroidal field coil for the JT-60SC

Tsuchiya, Katsuhiko; Kizu, Kaname; Miura, Yushi; Ando, Toshinari*; Sakasai, Akira; Matsukawa, Makoto; Tamai, Hiroshi; Ishida, Shinichi

IEEE Transactions on Applied Superconductivity, 14(2), p.1427 - 1430, 2004/06

 Times Cited Count:1 Percentile:87.82(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Design of the high-T$$_{c}$$ superconducting TF coil for the tight aspect ratio Tokamak power reactor (VECTOR)

Ando, Toshinari*; Nishio, Satoshi; Yoshimura, Hideto*

IEEE Transactions on Applied Superconductivity, 14(2), p.1481 - 1484, 2004/06

 Times Cited Count:8 Percentile:54.91(Engineering, Electrical & Electronic)

no abstracts in English

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:87.82(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Development and test results of a 60kA HTS current lead for fusion application

Isono, Takaaki; Hamada, Kazuya; Kawano, Katsumi; Abe, Kanako*; Nunoya, Yoshihiko; Sugimoto, Makoto; Ando, Toshinari*; Okuno, Kiyoshi; Bono, Takaaki*; Tomioka, Akira*; et al.

Teion Kogaku, 39(3), p.122 - 129, 2004/03

JAERI has been developing a large-capacity high-temperature superconductor (HTS) current lead for fusion application, and succeeded in fabricating and testing a 60kA HTS current lead satisfying ITER requirements. Targets of performance are 1/10 heat leak and 1/3 electric power consumption of cryogenic system compared with a conventional lead. To achieve the target, selection of sheath material of HTS, optimizing the Cu part, reduction of joule heat at joint between HTS and Cu parts, improve of heat transfer between HTS and stainless steel tube. Developed 60kA HTS current lead satisfied the design condition and almost achieved the targets. Adoption of the HTS current lead can reduce 13% electric power consumption of cryogenic system for ITER.

Journal Articles

Development of a 30 m long Nb$$_{3}$$Al superconducting conductor jacketed with a round-in-square type stainless steel conduit for the toroidal field coils in JT-60SC

Tsuchiya, Katsuhiko; Kizu, Kaname; Miura, Yushi; Ando, Toshinari*; Nakajima, Hideo; Matsukawa, Makoto; Sakasai, Akira; Ishida, Shinichi

Fusion Engineering and Design, 70(2), p.131 - 140, 2004/02

 Times Cited Count:3 Percentile:74.43(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Advanced fusion technologies developed for JT-60 superconducting Tokamak

Sakasai, Akira; Ishida, Shinichi; Matsukawa, Makoto; Akino, Noboru; Ando, Toshinari*; Arai, Takashi; Ezato, Koichiro; Hamada, Kazuya; Ichige, Hisashi; Isono, Takaaki; et al.

Nuclear Fusion, 44(2), p.329 - 334, 2004/02

no abstracts in English

Journal Articles

Advanced fusion technologies developed for JT-60 superconducting Tokamak

Sakasai, Akira; Ishida, Shinichi; Matsukawa, Makoto; Akino, Noboru; Ando, Toshinari*; Arai, Takashi; Ezato, Koichiro; Hamada, Kazuya; Ichige, Hisashi; Isono, Takaaki; et al.

Nuclear Fusion, 44(2), p.329 - 334, 2004/02

 Times Cited Count:7 Percentile:74.35(Physics, Fluids & Plasmas)

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:83.36(Thermodynamics)

no abstracts in English

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 a Nb$$_{3}$$Al conductor for toroidal field coils

Koizumi, Norikiyo; Ando, Toshinari*; Nakajima, Hideo; Matsui, Kunihiro; Sugimoto, Makoto; Takahashi, Yoshikazu; Okuno, Kiyoshi; Kizu, Kaname; Miura, Yushi; Tsuchiya, Katsuhiko; et al.

Proceedings of 20th IEEE/NPSS Symposium on Fusion Engineering (SOFE 2003), p.419 - 422, 2003/10

Nb$$_{3}$$Sn cConductors have already been developed for the TF coils operating at 13 T. However, the critical current of Nb$$_{3}$$Sn degrades due to a strain, and the amount of degradation becomes larger when the magnetic field increases, which set a limit of the Nb$$_{3}$$Sn application to a large coil at around 13 T. Nb$$_{3}$$Al is considered, therefore, to be a next generation superconductor, since the critical current of Nb$$_{3}$$Al is superior to that of Nb3Sn and less sensitive against strains. JAERI has been developing Nb$$_{3}$$Al conductor since 80s. As the first step, mass production technique of Nb3Al strands was established. In the second step, coil fabrication technique was developed and could successfully be charged to the nominal point of 13 T and 46 kA. From these advantages, JAERI is also promoting R&D activities to develop Nb$$_{3}$$Al TF coils for JT-60SC. The prototype Nb$$_{3}$$Al conductor has already been made. A D-shaped coil was fabricated and successfully tested. These activities constitute the basic approaches to develop TF coils whose operating field is expected to be around 16 T.

Journal Articles

Superconducting coil with pure copper wires for thermal protection outside cable-in-conduit conductors

Ando, Toshinari*; Kikuchi, Mitsuru

Fusion Engineering and Design, 66-68, p.1097 - 1102, 2003/09

 Times Cited Count:0 Percentile:100

In order to realize a low cost TF superconducting coil system for tokamak fusion reactors, the design of TF superconducting coil with a copper coil in place of pure copper wires within cable-in-conduit conductors is considered, which are needed for the thermal protection. This consideration is carried out under the condition that hot spot temperature of conductor is less than 250 K and a plasma-confinement vacuum vessel has no damage during the TF coil fast discharge in the ITER TF coil design. As the result, it is found that the conductor area is reduced by 35 % and the copper coil is installed into the original coil case together with a TF coil winding. An external resister system is reduced by around 40 % of the original system because 40 % of magnetic energy (40 GJ) stored in the ITER TF coil is dissipated into the copper coil during the fast discharge.

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