Ключевые слова: ITER, central coils, quench properties, modeling, quench detection, minimum quench energy, temperature distribution
Ключевые слова: fusion magnets, LTS, Nb3Sn, central coils, coils solenoidal, coils model, quench detection, inductance, noise, measurement technique, modeling, numerical analysis
Zenobio A.D., Celentano G., Muzzi L., Marzi G.D., Corte A.D., Giannini L., Romanelli G., Zoboli L., Turtщ S., Califano F.
Libeyre P., Mayri C., Jong C., Schild T., Smith J., Sgobba S., Freudenberg K., Guinchard M., Everitt D., Santillana I.A., Gaxiola E., Frutos O.S., Bennet J., Lourenco S.S.
Ключевые слова: Tokamak, Japan, central coils, coils solenoidal, power supply, stability, test results, voltage distribution
Bruzzone P., Celentano G., Zani L., Fietz W.H., Muzzi L., Fink S., Torre A., Corato V., Corte A.D., Sedlak K., Federici G., Sarasola X., Bykovskiy N., Dematte F.
Ключевые слова: central coils, design parameters, NbTi, coils outer, HTS, REBCO, coils insert, fusion, DEMO, Europe, magnetic systems, design, coils toroidal, design parameters, react-and-wind technique, LTS, Nb3Sn
Ключевые слова: ITER, LTS, Nb3Sn, cable-in-conduit conductor, central coils, coils solenoidal, ac losses, modeling, numerical analysis
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
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: Tokamak, central coils, coils solenoidal, design, design parameters, loads, compression, mechanical properties, stress effects, modeling
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
Ключевые слова: Tokamak, central coils, coils solenoidal, coils poloidal field, quench detection, modeling, numerical analysis
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