Ключевые слова: ITER, central coils, quench properties, modeling, quench detection, minimum quench energy, temperature distribution
Ключевые слова: ITER, LTS, NbTi, cable-in-conduit conductor, coils poloidal field, joints, ac losses, dynamic operation, plasma treatments, modeling, numerical analysis
Ключевые слова: ITER, magnets, coils toroidal, LTS, Nb3Sn, cable-in-conduit conductor, ac losses, 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, central coils, coils solenoidal, thermal-hydraulics, ac losses, test results, modeling, comparison
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: Tokamak, divertor, heat loads, ITER, DEMO, vacuum structure, cryogenic systems, status, plans
Ключевые слова: ITER, coils poloidal field, impregnation, vacuum structure, pressure effect, insulation, experimental devices, test results
Koizumi N., Matsui K., Chikaraishi H., Takahata K., Imagawa S., Obana T., Hamaguchi S., Kajitani H., Takada S., Onodera Y.
Libeyre P., Mayri C., Jong C., Schild T., Smith J., Sgobba S., Freudenberg K., Guinchard M., Everitt D., Santillana I.A., Gaxiola E., Frutos O.S., Bennet J., Lourenco S.S.
Ключевые слова: ITER, Japan, LTS, Nb3Sn, coils toroidal, coils pancake, heat treatment, experimental results
Ключевые слова: ITER, magnets, experimental results, quality control, fusion magnets, bus bar conductor, defects, safety
Lopez M.M., Bonito-Oliva A., Valente P., Boutboul T., Carvas P., Loizaga A., Romano G., Calchi G., Aprili P., Harrison R., Gavouyere-Lasserre P., Vizio E., Rossi D., Batista R., Casarin V., Jimenez M., Readman P., Sborchia C., Guang S., Paiva V., Martins V., Conceincao P., Magouri N., Lim B.S., Gaxiola E., Bersier J.L., Ilyin Y., Baikalov A., Min L., Mitchell N., Penco R., Pesenti P., Cavanna E., Pizzigoni G., Amaduzzi A., Berrino M., Mussinato A., Lucas J.
Ключевые слова: ITER, coils poloidal field, fabrication, delivery system, test results, facility
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