Zanino R., Martovetsky N.N., Bonifetto R., Schild T., Gauthier F., Zappatore A., Khumthong K., Schaubel K.M., Sheeron J., Langhorn A.R.
Ключевые слова: ITER, central coils, thermal-hydraulics, cable-in-conduit conductor, pressure drop, test results, modeling
Ключевые слова: fusion magnets, HTS, REBCO, tapes, stacked blocks, coils toroidal, central coils, CORC cables, new, design, critical caracteristics, Jc/B curves, cable-in-conduit conductor, review
Ключевые слова: fusion magnets, central coils, Bi2212/Ag, tapes, design, HTS, coils poloidal field, design parameters, mechanical properties, stress distribution, facility
Ключевые слова: ITER, cable-in-conduit conductor, LTS, NbTi, strands, coils toroidal, central coils, ac losses, modeling, numerical analysis, experimental results, SULTAN, comparison
Zanino R., Breschi M., Bauer P., Ribani P.L., Martovetsky N., Bonifetto R., Gauthier F., Cavallucci L., Zappatore A.
Ключевые слова: ITER, LTS, Nb3Sn, cable-in-conduit conductor, central coils, measurement setup, ac losses, calorimetric method, transport currents, damping, test results, SULTAN, modeling, comparison
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
Ключевые слова: Tokamak, reactor, hybrid systems, HTS, tapes, REBCO, comparison, stacked blocks, twisting, CORC cables, critical current, current density, magnetic field dependence, coils toroidal, angular dependence, central coils, review
Ключевые слова: HTS, REBCO, coated conductors, stacked blocks, twisting, cable-in-conduit conductor, quench properties, modeling, thermal-hydraulics, contact characteristics, resistance, DEMO, central coils, coils solenoidal, magnetic field distribution, critical caracteristics, critical current distribution, temperature distribution, interstrand contact resistances, normal zone propagation, hot spots, numerical analysis
Ключевые слова: presentation, China, large-scale applications, review, wires, HTS, YBCO, fabrication, coated conductors, pnictides, tapes, Bi2212, cable-in-conduit conductor, FCL, cables, power transmission lines, liquid natural gas, generators, high field magnets, coils insert, MRI magnets, LTS, NbTi, coils toroidal, central coils, Nb3Sn, coils model, Maglev system, evacuated tube, critical caracteristics, test results
Ключевые слова: Tokamak, central coils, compression, mechanical treatment, loads, mechanical properties, strain effects, stress effects, deformation, experimental results, modeling
Mitchell N., Libeyre P., Martovetsky N., Decool P., Jong C., Schild T., Smith J., Freudenberg K., Everitt D., Cormany C., Gaxiola E., Reagan T., Pallisa J., Rossano G., Potts R., Stephens A., Brun C., Bruton A., Mariani A., Vandergriff D., Mullins D., Nguyen C.
Ключевые слова: ITER, central coils, coils solenoidal, fabrication, LTS, Nb3Sn, design, compression
Ключевые слова: ITER, design parameters, LTS, Nb3Sn, fabrication, degradation studies, history, cables, central coils, coils toroidal, critical temperature, cycling, crack formation, tensile tests, training effect
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