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Novello, L.*; Cara, P.*; Coletti, A.*; Gaio, E.*; Maistrello, A.*; Matsukawa, Makoto; Philipps, G.*; Tomarchio, V.*; Yamauchi, Kunihito
IEEE Transactions on Applied Superconductivity, 26(2), p.4700507_1 - 4700507_7, 2016/03
Times Cited Count：7 Percentile：39.7(Engineering, Electrical & Electronic)Hamada, Kazuya; Nakajima, Hideo; Takano, Katsutoshi*; Kudo, Yusuke; Tsutsumi, Fumiaki*; Okuno, Kiyoshi; Jong, C.*
Fusion Engineering and Design, 75-79, p.87 - 91, 2005/11
Times Cited Count：8 Percentile：49.16(Nuclear Science & Technology)no abstracts in English
test results of a D-shaped Nb
Al CICC coil fabricated with a react-and-wind process for the National Centralized TokamakAndo, 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：10.45(Nuclear Science & Technology)no abstracts in English
Shimada, Katsuhiro; Omori, Yoshikazu; Furukawa, Hiroshi*; Terakado, Tsunehisa; Matsukawa, Makoto; Kurihara, Kenichi
Proceedings of International Conference on Electrical Engineering 2004 (ICEE 2004), p.777 - 781, 2004/00
We developed a new coil current control system for a power supply that consists of a synchronous generator and diode rectifiers. Test results are reported for the toroidal field coil power supply of JT-60, a world-class tokamak-type fusion device. This coil current control system has been designed to improve the control flexibility of the plasma discharge, and to introduce new functions. A state feedback control method is adopted to control coil current. Limit functions for the generator field current, the generator output voltage, and the toroidal field coil voltage have been added to the original coil current control system. Moreover, the abnormal state detection function of a coil is implemented for safety. The developed new intelligent control system has been tested and its performance was confirmed.
Al conductor to be applied to a fusion reactor and its application to a large superconducting coilKoizumi, Norikiyo; Okuno, Kiyoshi; Nakajima, Hideo; Ando, Toshinari*; Tsuji, Hiroshi
Teion Kogaku, 38(8), p.391 - 398, 2003/08
no abstracts in English
Al insertKoizumi, Norikiyo; Nunoya, Yoshihiko; Takayasu, Makoto*; Sugimoto, Makoto; Nabara, Yoshihiro; Oshikiri, Masayuki*; CS Model Coil Test Group
Teion Kogaku, 38(8), p.399 - 409, 2003/08
A NbAl insert was developed to demonstrate the applicability of a NbAl conductor and wind-and-react method to a TF coil of a fusion reactor by artificially applying 0.4% bending strain to the conductor after its heat treatment. The critical current test results show that the effective strains applied to the strands is almost zero. Then, the validity of the react-and-wind method was demonstrated. In addition, while an unexpected strain, which was proportional to electromagnetic force, was observed in the same scale NbSn conductor, such strain did not exist in the NbAl conductor. This shows a NbAl conductor is suitable to the application to large magnets, such as the TF coil. Furthermore, the effect of the current transfer among the strands on the critical current evaluation is studied by developing a numerical analysis code, KORO. The results figure out that the critical current of a large cable-in-conduit conductor can be easily evaluated assuming the uniform current distribution if the conductance among the strands is 10E5 S/m or less.
Al D-shaped coil fabricated by react-and-wind method for JT-60 superconducting TokamakKizu, 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 NbAl superconductor was developed for the TFC conductor material in JAERI. The NbAl 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.
Al cable-in-conduit conductorKoizumi, Norikiyo; Takahashi, Yoshikazu; Nunoya, Yoshihiko; Matsui, Kunihiro; Ando, Toshinari; Tsuji, Hiroshi; Okuno, Kiyoshi; Azuma, Katsunori*; Fuchs, A.*; Bruzzone, P.*; et al.
Cryogenics, 42(11), p.675 - 690, 2002/11
Times Cited Count：23 Percentile：64.67(Thermodynamics)In the framework of ITER-EDA, a 13T-46kA NbAl conductor with stainless steel jacket has been developed to demonstrate applicability of an NbAl conductor with react-and-wind technique to ITER-TF coils. The critical current performances of the NbAl conductors were studied to verify that the conductor achieves the expected performance and 0.4% bending strain does not originate degradation. The critical currents were measured at the background magnetic fields of 7, 9, 10 and 11 T at the temperatures from 6 to 9 K. The expected critical currents is calculated using the developed model and the calculation results indicate that the experimental results showed good agreement with the expected critical currents. Accordingly, we can conclude that the fabrication process of this conductor was appropriate and the applicability of the react-and-wind technique was demonstrated.
Hamada, Kazuya; Koizumi, Norikiyo
Purazuma, Kaku Yugo Gakkai-Shi, 78(7), p.616 - 624, 2002/07
In the Tokamak type fusion reactor design, a forced flow superconducting coil is applied from the viewpoint to high magnetic field, high withstand voltage performance and large electromagnetic force. In the forced flow magnets, it is well known that various electromagnetic phenomena are occurred by zero resistance and diamagnetic effect of superconductor and complicated structure of cable in conduit conductor (CICC). In the R&D of CICC, the study of hysteresis losses and coupling losses CICC have a lot of progress. For example, using the optimization of filament arrangement in superconducting strand and control of contact resistance of strand, ITER model coil project have a large achievement.
Sato, Satoshi; Takatsu, Hideyuki; *; Seki, Yasushi
J. Fusion Eng. Des., 30(3), p.1076 - 1080, 1996/12
no abstracts in English
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
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
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JAERI-M 7543, 37 Pages, 1978/02
no abstracts in English
