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: ITER, coils toroidal, control systems, fabrication
Ключевые слова: ITER, LTS, Nb3Sn, strands, composites, modeling, thermal properties, mechanical properties, elastic behavior, stress distribution, numerical analysis
Ключевые слова: ITER, LTS, Nb3Sn, cable-in-conduit conductor, central coils, coils solenoidal, ac losses, modeling, numerical analysis
Zanino R., Breschi M., Bauer P., Martovetsky N., Bonifetto R., Gauthier F., Cavallucci L., Zappatore A., Khumthong K., Sheeron J., Ortiz E.
Ключевые слова: ITER, coils poloidal field, central coils, LTS, Nb3Sn, NbTi, cable-in-conduit conductor, design parameters, ac losses, experimental results, review
Ключевые слова: ITER, coils toroidal, LTS, Nb3Sn, cable-in-conduit conductor, bronze process, internal tin method, ac losses, measurement technique, SULTAN
Ключевые слова: ITER, magnetic systems, feeder, bus bar conductor, joints, quality control, joint resistances, pressure drop, stability, test results
Mitchell N., Martovetsky N., Miyoshi Y., Decool P., Jong C., Schild T., Smith J., Freudenberg K., Gauthier F., Liao M., Everitt D., Cormany C., Hughes D., Rossano G., Potts R., Stephens A., Bruton A., Mariani A., Vandergriff D., Dao C.N.
Ключевые слова: Tokamak, ITER, central coils, coils solenoidal, installation, compression, joints, joint resistances, bus bar conductor, fabrication
Formisano A., Portone A., Bellesia B., Harrison R., Bonito-Oliva A., Jimenez M., Viladiu E., Bue A.L., Kostopoulos C., Aprili P., Pellicer N., Pompa E., Pallas G., Pozuelo E., Ferrater M.
Ключевые слова: ITER, Tokamak, coils toroidal, fabrication, control systems, test results
Ключевые слова: ITER, Japan, coils toroidal, fabrication, LTS, Nb3Sn, impregnation, cooling technology, winding techniques
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: ITER, coils toroidal, LTS, Nb3Sn, degradation studies, critical temperature, loads, quench, discharge characteristics, test results
Ключевые слова: ITER, coils toroidal, current leads, prototype, design parameters, fabrication, HTS, Bi2223/AgAu, tapes, cooling technology, test results
Ключевые слова: ITER, current leads, surface, stainless steel, fabrication, processing apparatus
Ключевые слова: fusion magnets, ITER, DEMO, cryogenic systems, helium supercritical, heat loads, dynamic operation, cryogenic pumps, design, design parameters, modeling, numerical analysis, review
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