Tsuchiya K., Takahashi K., Hamada K., Fukui K., Shimada K., Kawano K., Murakami H., Bonito-Oliva A., Kajitani H., Novello L., Wanner M., Davis S., Hatakeyama S., Pietro E.D., Matsunaga G., Nakamoto M., Kojima A., Onishi Y., Terakado A., Valerio T., Frello G.
Ключевые слова: Tokamak, commissioning, test results, arc, discharge characteristics, insulation, termination, joints, test results
Yoshida S., Nakamura K., Hamada K., Kobayashi T., Shimada K., Murakami H., Hatakeyama S., Sonoda S., Yuinawa K.
Ключевые слова: Tokamak, coils poloidal field, resonance effects, voltage, fluctuations, modeling
Ключевые слова: Tokamak, Japan, central coils, coils solenoidal, power supply, stability, test results, voltage distribution
Ключевые слова: Tokamak, cooling technology, cryogenic systems, modeling, thermal performance, shields, test results
Tsuchiya K., Hamada K., Fukui K., Kawano K., Abe T., Murakami H., Tomarchio V., Natsume K., Hoa C., Michel F., Wanner M., Otsu K.
Hamada K., Zani L., Fukui K., Lacroix B., Torre A., Murakami H., Nicollet S., Tomarchio V., Hoa C., Michel F., Wanner M., Davis S., Louzguiti A., Coz Q.L., Sannazzaro G.
Ключевые слова: commissioning, Tokamak, HTS, Bi2223, tapes, current leads, fabrication, design, design parameters, cooling technology, heat losses, test results
Ключевые слова: Tokamak, central coils, compression, mechanical treatment, loads, mechanical properties, strain effects, stress effects, deformation, experimental results, modeling
Mitchell N., Kim H., Hamada K., Libeyre P., Ilyin Y., Vostner A., Devred A., Baikalov A., Lim B.S., Gung C., Turck B., Dolgetta N., Simon F., Hua Q., Gaxiola E., Koczorowski S., Carl C.
Ключевые слова: ITER, coils, joints, fabrication, design parameters, fatigue behavior, test results, joint resistances, ac losses
Ключевые слова: ITER, coils toroidal, termination, design, contact characteristics, measurement technique, numerical analysis
Mitchell N., Hamada K., Domptail F., Zheng S., Surrey E., McIntosh S., Cave-Ayland K., Taylor N., Ash A.D., Holmes A.J.
Mitchell N., Hamada K., Domptail F., Foussat A., Zheng S., Surrey E., McIntosh S., Holmes A., Cave-Ayland K., Ash A., Taylor N.
Ключевые слова: ITER, magnets, fault currents, cryogenic systems, coils poloidal field, vacuum structure, safety
Mitchell N., Koizumi N., Matsui K., Hamada K., Seo K., Hemmi T., Devred A., Alekseev A., Gung C., Harrison R., Gallix R., Jong C., Foussat A., Oliva A.B., Boyer C., Nakahira M., Gandel M., Rebollo E.B., Petit P., Journeaux J.Y., Koczorowski S., Rest M.L., Martin B., Reich J., Bellesia A.
Ключевые слова: ITER, coils toroidal, magnetic systems, LTS, Nb3Sn, winding techniques, installation, cable-in-conduit conductor, coils pancake, heat treatment, impregnation, fabrication, review
Ключевые слова: ITER, central coils, jacket, mechanical properties, joints, tensile tests, fracture behavior, fatigue behavior, crack formation, test results
Ключевые слова: ITER, coils toroidal, helium liquid, cryogenic systems, numerical analysis, hydraulic performances, dynamic operation
Nunoya Y., Takahashi Y., Hamada K., Saito T., Kawano K., Oshikiri M., Teshima O., Ozeki H., Matsunami M.
Ключевые слова: ITER, central coils, jacket, fabrication, design parameters, test results, mechanical properties
Mitchell N., Hamada K., Seo K., Weiss K.-P., Savary F., Decool P., Foussat A., Sgobba S., Boyer C., Le Rest M.
Ключевые слова: ITER, coils toroidal, cryogenic systems, helium liquid, experimental devices, design
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