Zanino R., Breschi M., Bauer P., Vostner A., Martovetsky N., Bonifetto R., Cavallucci L., Zappatore A.
Ключевые слова: ITER, LTS, Nb3Sn, cable-in-conduit conductor, central coils, magnetic systems, ac losses, hysteresis, test results
Zanino R., Breschi M., Martovetsky N., Miyoshi Y., Bonifetto R., Schild T., Smith J., Hoa C., Freudenberg K., Cavallucci L., Zappatore A., Langhorn A., Rossano G., Pichel G.P., Khumthong K., Sheeron J., Ortiz E., Wooley K., Norausky N.
Ключевые слова: ITER, LTS, Nb3Sn, cable-in-conduit conductor, central coils, magnetic systems, ac losses, hysteresis, test results
Ключевые слова: magnets, fault detection, thermal-hydraulics, modeling, DEMO, coils toroidal, discharge characteristics, transport currents, voltage, hot spots, time evolution
Ключевые слова: ITER, central coils, coils solenoidal, thermal-hydraulics, ac losses, test results, modeling, comparison
Zanino R., Bonifetto R., Michel F., Roussel P., Froio A., Frattolillo A., Migliori S., Lisanti F., Angelucci M., Duri D., Iaboni A.
Ключевые слова: Tokamak, magnets, coils toroidal, divertor, cryogenic systems, cooling technology, design, thermal-hydraulics, modeling, numerical analysis
Zenobio A.D., Anemona A., Bonifetto R., Cucchiaro A., Corte A.D., Marzi G.D., Zignani C.F., Giannini L., Giorgetti F., Indrigo D., Messina G., Morici L., Muzzi L., Pizzuto A., Placido D., Polli G.M., Ramogida G., Romanelli G., Savoldi L., Turtu S., Viarengo S., Zanino R., Zappatore A., Zoboli L.
Ключевые слова: fusion, Tokamak, DEMO, magnetic systems, coils, design, cable-in-conduit conductor, plans
Zanino R., Breschi M., Bauer P., Martovetsky N., Bonifetto R., Gauthier F., Cavallucci L., Zappatore A., Khumthong K., Sheeron J., Ortiz E.
Ключевые слова: Tokamak, thermal-hydraulics, magnets, coils toroidal, plasma treatments, modeling, cryogenic systems
Ключевые слова: fusion magnets, HTS, REBCO, tapes, cable-in-conduit conductor, quench propagation, thermal-hydraulics, modeling, quench protection, hot spots, test results, SULTAN, numerical analysis
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
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, divertor, coils toroidal, thermal-hydraulics, dc performance, design, LTS, Nb3Sn, coils pancake, magnetic field distribution, heat loads, distribution, modeling, numerical analysis
Sedlak K., Anvar V.A., Bagrets N., Biancolini M.E., Bonifetto R., Bonne F., Boso D., Brighenti A., Bruzzone P., Celentano G., Chiappa A., D'Auria V., Dan M., Decool P.*10, Corte A.D., Dembkowska A.*11, Dicuonzo O., Duran I.*12, Eisterer M.*13, Ferro A., Zignani C.F., Fietz W.H., Frittitta C., Gaio E., Giannini L., Giorgetti F., Gomory F.*14, Granados X.*15, Guarino R., Heller R., Hoa C., Ivashov I.*16, Jiolat G.*10, Jirsa M.*17, Jose B.*10, Kembleton R.*18, Kumar M., Lacroix B.*10, Coz Q.L.*19, Lewandowska M.*11, Maistrello A., Misiara N.*10, Morici L., Muzzi L., Nicollet S.*10, Nijhuis A., Nunio F.*10, Portafaix C.*10, Romanelli G., Sarasola X., Savoldi L., Stepanov B., Tiseanu I.*20, Tomassetti G., Torre A.*10, Turtщ S., Uglietti D., Vallcorba R.*10, Viererbl L.*21, Vojenciak M.*14, Vorpahl C.*18, Weiss K., Wesche R., Wolf M.J., Zani L.*10, Zanino R., Zappatore A., Corato V.
Ключевые слова: fusion magnets, Tokamak, central coils, HTS, REBCO, tapes, cable-in-conduit conductor, quench propagation, modeling, thermal-hydraulics
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