Ключевые слова: ITER, coils poloidal field, coils toroidal, cable-in-conduit conductor, heat transfer, nucleation
Bauer P., Liu X., Liu C., Gung C., Niu E., Han Q., Ran Q., Kun L., He X., Kaverin D., Dong Y., Shu D., Yu A.
Ключевые слова: ITER, HTS, Bi2223, current leads, fabrication, control systems, central coils, coils toroidal, coils poloidal field, design parameters, test results
Ключевые слова: fusion magnets, coils, winding techniques, winding configurations, modeling, numerical analysis, Tokamak, coils poloidal field
Ключевые слова: ITER, coils poloidal field, LTS, NbTi, cable-in-conduit conductor, quench, modeling, quench detection
Smith K., Romano G., Bonito-Oliva A., Readman P., Batista R., Valente P., Rossi D., Loizaga A., Bilbao M., Aprili P., Lopez M.M., Carvas P., Gavouyere-Lasserre P., Vizio E., Casarin V., Kostopoulos C.-2, Fachin G.
Ключевые слова: ITER, coils poloidal field, Europe, winding process, facility
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, coils toroidal, coils poloidal field, design, magnets, modeling
Ключевые слова: Tokamak, magnets, coils toroidal, coils poloidal field, protective system, current, detector, experimental results
Ключевые слова: ITER, LTS, NbTi, cable-in-conduit conductor, coils poloidal field, joints, ac losses, dynamic operation, plasma treatments, modeling, numerical analysis
Breschi M., Bauer P., Ilyin Y., Torre A., Turck B., Schild T., Gauthier F., Cavallucci L., Duchateau J.
Ключевые слова: ITER, central coils, coils solenoidal, coils poloidal field, ac losses, numerical analysis, plasma treatments, LTS, Nb3Sn, NbTi, cable-in-conduit conductor
Ключевые слова: ITER, LTS, NbTi, coils poloidal field, joints, operational performance, SULTAN, ac losses, resistance, test long-term operation, review
Ключевые слова: SULTAN, measurement setup, ITER, coils poloidal field, LTS, NbTi, cable-in-conduit conductor, joints, design, design parameters, joint resistances, current-voltage characteristics, electromagnetic forces, test results, modeling, numerical analysis, power, dissipative properties, current distribution, nonlinear effects, facility
Ключевые слова: ITER, coils poloidal field, joints, transient performance, LTS, NbTi, cable-in-conduit conductor, ac losses, resistance, modeling, numerical analysis, experimental results, comparison
Ключевые слова: ITER, coils poloidal field, heat treatment, impregnation, mechanical properties, dielectric properties, modeling, numerical analysis
Ключевые слова: ITER, coils poloidal field, impregnation, vacuum structure, pressure effect, insulation, experimental devices, test results
Zenobio A.D., Muzzi L., Corte A.D., Anemona A., Giannini L., Turtъ S., Romanelli G., Zoboli L., Vairo G.
Ключевые слова: Tokamak, coils poloidal field, design, design parameters, mechanical properties, loads, stress effects, fatigue behavior, modeling, numerical analysis
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