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
Mitchell N., Wang L., Shen G., Dolgetta N., Simon F., Oliva A.B., Lim B., Ilin Y., Liao M., Lopez M., Reich J.
Ключевые слова: ITER, coils poloidal field, fabrication, installation, photo, review
Ключевые слова: presentation, Tokamak, Japan, design, design parameters, coils toroidal, coils poloidal field, central coils, LTS, NbTi, Nb3Sn, fabrication, cooling technology, joint resistances, test results
Ключевые слова: ITER, coils poloidal field, central coils, LTS, Nb3Sn, NbTi, cable-in-conduit conductor, design parameters, ac losses, experimental results, review
Ключевые слова: Tokamak, central coils, coils solenoidal, coils poloidal field, quench detection, modeling, numerical analysis
Ключевые слова: Tokamak, divertor, central coils, coils solenoidal, coils poloidal field, modeling, numerical analysis, breakdown characteristics
Boutboul T., Romano G., Harrison R., Martinez M., Bonito-Oliva A., Readman P., Batista R., Jimenez M., Valente P., Rossi D., Loizaga A., Aprili P., Ferrater M., Carvas P., Calchi G., Vizio E., Casarin V., Paiva V., Magouri N., Cuevas C., Jimenez A., Pallаs G., Gavouyere-Lassere P.
Ключевые слова: ITER, coils poloidal field, magnets, coils pancake, LTS, NbTi, cable-in-conduit conductor, winding process, impregnation, winding configurations, current, numerical analysis
Ilyin Y., Luongo C., Boutboul T., Bellesia B., Romano G., Harrison R., Martinez M., Oliva A.B., Boter E., Batista R., Jimenez M., Valente P., Rossi D., Bue A.L., Casas M., Loizaga A., Koczorowski S., Aprili P., Pellicer N., Pompa E., Hernandez A., Pozuelo E., Ferrater M., Carvas P., Calchi G., Gavouyere-Lasserre P., Casarin V., Paiva V., Martins V., Viladiu E.*1Vizio E., Charalampos K., Su L.B.
Ключевые слова: Europe, ITER, coils toroidal, Nb3Sn, coils poloidal field, LTS, NbTi, cable-in-conduit conductor, fabrication, status
Ключевые слова: DEMO, magnets, Nb3Sn, feeder, LTS, NbTi, cables, coils toroidal, coils poloidal field, central coils, design, design parameters, joints, bus bar conductor, HTS, REBCO, coated conductors, current leads, design, modeling
Ключевые слова: Tokamak, spheres, magnetic systems, coils toroidal, coils poloidal field, design, HTS, modeling, power plants, facility
Ключевые слова: fusion magnets, central coils, Bi2212/Ag, tapes, design, HTS, coils poloidal field, design parameters, mechanical properties, stress distribution, facility
Srinivasan R., Tanna V.L., Prasad U., Roy S., Nimavat H., Kumar N., Kanabar D., Dodiya C., Ghate M., Purwar G., Garg A., Singh Y., Parmesh M., Pal U.K., Raju D.
Ключевые слова: Tokamak, coils poloidal field, Cu-based conductors, current leads, insulating medium, fabrication, test results
Ключевые слова: Tokamak, design parameters, magnetic systems, coils toroidal, coils poloidal field, central coils, commissioning
Rodin I.Y., Zapretilina E.R., Bondarchuk E.N., Kavin A.A., Kitaev B.A., Kozhukhovskaya N.M., Tanchuk V.N., Kovalchuk O.A., Krasilnikov A.V., Labusov A.N., Voronova A.A., Trofimov V.A., Konovalov S.V., Grigoryev S.A., Mineeva I.I., Muratova V.P., Cherdakov A.K., Chernenok V.V.
Ключевые слова: Tokamak, reactor, hybrid systems, HTS, coils toroidal, coils poloidal field, central coils, correction coils, comparison, fusion, design parameters, review
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