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., Zanino R., Turtu S., Muzzi L., Marzi G.D., Polli G.M., Corte A.D., Zignani C.F., Messina G., Cucchiaro A., Bonifetto R., Pizzuto A., Morici L., Anemona A., Savoldi L., Ramogida G., Giorgetti F., Zappatore A., Giannini L., Romanelli G., Zoboli L., Placido D., Viarengo S., Indrigo D.
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: magnets, heat losses, cryogenic systems, cooling technology, ITER, central coils, modeling, numerical analysis
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
Ключевые слова: DEMO, magnets, coils toroidal, magnetic systems, safety, modeling, ITER, comparison
Ключевые слова: ITER, central coils, modeling, ac losses, numerical analysis, LTS, Nb3Sn, cable-in-conduit conductor, thermal-hydraulics, experimental results
Turtu S., Muzzi L., Corato V., Corte A.D., Zignani C.F., Messina G., Affinito L., Bonifetto R., Morici L., Anemona A., Savoldi L., Zappatore A., Righetti R., Giannini L., Romanelli G., Zoboli L., Zanino A.Z.
Ключевые слова: HTS, coated conductors, cable-in-conduit conductor, quench propagation, modeling, thermal performance, thermal-hydraulics
Ключевые слова: Tokamak, central coils, thermal-hydraulics, numerical analysis, operational performance, modeling, temperature distribution
Zenobio A.D., Zanino R., Bruzzone P., Turtu S., Corato V., Bonifetto R., Sedlak K., Savoldi L., Zappatore A.
Ключевые слова: DEMO, LTS, NbTi, coils poloidal field, thermal-hydraulics, numerical analysis, design, magnetic field distribution, modeling
Ключевые слова: DEMO, coils toroidal, mechanical properties, numerical analysis, coils wind-and-react, modeling, design, stress distribution
Zanino R., Breschi M., Ribani P.L., Devred A., Martovetsky N., Bonifetto R., Bianchi M., Carli S., Savoldi L., Takaaki I.
Ключевые слова: ITER, central coils, quench propagation, thermal-hydraulics, experimental results, hot spots, numerical analysis, comparison
Ключевые слова: ITER, central coils, coils insert, stability, test results, thermal-hydraulics, design, design parameters, minimum quench energy, LTS, cable-in-conduit conductor, Nb3Sn
Ключевые слова: DEMO, coils toroidal, quench propagation, fusion magnets, Europe, design parameters, modeling, numerical analysis, hot spots, temperature distribution
Zanino R., Bruzzone P., Breschi M., Isono T., Zani L., Devred A., Martovetsky N., Nabara Y., Bessette D., Bonifetto R., Savoldi L.
Ключевые слова: ITER, central coils, LTS, Nb3Sn, strands, test results, SULTAN, mechanical properties, strain effects
Ключевые слова: DEMO, coils toroidal, winding configurations, design, thermal-hydraulics, numerical analysis, LTS, Nb3Sn, strands, geometry effects, cable-in-conduit conductor
Ключевые слова: central coils, coils model, LTS, Nb3Sn, cable-in-conduit conductor, comparison, thermal-hydraulics, test long-term operation, experimental results, ITER
Zanino R., Bruzzone P., Mitchell N., Breschi M., Nunoya Y., Okuno K., Takahashi Y., Isono T., Ciazynski D., Zani L., Saito T., Smirnov A., Kawano K., Devred A., Martovetsky N., Torre A., Nabara Y., Bessette D., Nicollet S., Duchateau J.-L., Bonifetto R., Suwa T., Reiersen W., Gauthier F., Ozeki H., Savoldi L., Khodak A., Louzguiti A., Rodin I.*10, Tronza V.*11
Ключевые слова: ITER, central coils, coils insert, test results, degradation studies, ac losses, mechanical properties, strain effects, quench propagation, stability, heating rates
Ключевые слова: coils toroidal, DEMO, thermal-hydraulics, modeling, Europe, design, cooling technology
Zanino R., Bruzzone P., Celentano G., Augieri A., Muzzi L., Marzi G.D., Corte A.D., Bonifetto R., Carli S., Savoldi L., Piras V.
Ключевые слова: HTS, cable-in-conduit conductor, fusion magnets, thermal-hydraulics, modeling, DEMO, coated conductors, twisting, stacked blocks, Al, cores, REBCO, EDIPO, test results, pressure drop, thickness dependence
Wesche R., Eisterer M., Bruzzone P., Stepanov B., Turtu S., Ciazynski D., Zani L., Nijhuis A., Muzzi L., Lacroix B., Torre A., Hertout P., Prokopec R., Bonifetto R., Nunio F., Hoa C., Vallcorba R., Sedlak K., Savoldi L., Brutti C., Biancolini M.E., Giorgetti F., Panin A., Bayer C.M.*12, Coleman M.*18, Duran I.*17, Fietz W.H.*12, Gade P.V.*12, Gaio E.*10, Goldacker W.*12, Gomory F.*13, Granados X.*16, Heller R.*12, Kario A.*12, Lewandowska M.*11, Maistrello A.*10, Petrisor T.*15, Poncet J., Cardona M.S., Schlachter S.I.*12, Tiseanu I.*14, Vojenciak M.*13, Weiss K.-P.*12, Yagotintsev K., Zanino. R.
Ключевые слова: DEMO, magnetic systems, review, status, design, LTS, Nb3Sn, thermal-hydraulics, coils toroidal, HTS, Roebel conductors, CORC cables
Ключевые слова: Tokamak, magnets, thermal-hydraulics, modeling, ac losses
Ключевые слова: Tokamak, coils toroidal, central coils, ITER, cryogenic systems, helium liquid, heat loads, modeling, numerical analysis, neural networks
Ключевые слова: ITER, coils toroidal, cryogenic systems, hydraulic performances, modeling, helium supercritical
Ключевые слова: ITER, coils toroidal, heat loads, fusion magnets, high field magnets
Ключевые слова: modeling, heat loads, pulsed operation, ITER, central coils, design parameters
Ключевые слова: Tokamak, central coils, thermal-hydraulics, numerical analysis, modeling computational, high field magnets
Ключевые слова: ITER, coils toroidal, thermal-hydraulics, irradiation effects, modeling, cooling technology
Ключевые слова: ITER, coils toroidal, modeling computational, cooling technology, cryogenic systems, thermal-hydraulics, modeling, design parameters, LTS
Ключевые слова: ITER, coils toroidal, discharge characteristics, modeling, hot spots, quench, coils pancake, temperature distribution
Ключевые слова: ITER, coils toroidal, coils model, thermal-hydraulics, discharge characteristics, numerical analysis, safety
Ключевые слова: ITER, coils poloidal field, LTS, NbTi, quench propagation, test results, numerical analysis
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