Zenobio A.D., Muzzi L., Corte A.D., Anemona A., Giannini L., Turtъ S., Romanelli G., Zoboli L., Vairo G.
Ключевые слова: Tokamak, coils poloidal field, design, design parameters, mechanical properties, loads, stress effects, fatigue behavior, modeling, numerical analysis
Ключевые слова: Tokamak, magnets, coils toroidal, LTS, Nb3Sn, cable-in-conduit conductor, design, design parameters, mechanical properties, strain effects, loads, twist-pitch, modeling, numerical analysis
Zani L., Torre A., Hertout P., Nunio F., Hoa C., Coz Q.L., Bonne F., Varin S., Bourcier C., Wambeke C.V., Petit V., Dejoie F., Lacroix C.H.
Ключевые слова: Tokamak, magnetic systems, coils toroidal, design, design parameters, LTS, NbTi, cryogenic systems, helium superfluid, quench state, neutron irradiation, gamma irradiation, thermal-hydraulics, electrical field, modeling, minimum quench energy, quench properties, heat transfer, hot spots
Tanna V.L., Khan Z., George S., Paravastu Y., Raval D.C., Panchal P., Garg A., Gupta V., Gangradey R., Mukherjee S.S., Mishra J.S., Nayak P.A., Srikanth L., Dewasi A., Verma S.K., Duttaa R., Agravat H.
Ключевые слова: Tokamak, cryogenic pumps, cooling technology, nitrogen liquid , design, fabrication, photo, pressure dependence, temperature dependence, nitrogen gas, test results
Ключевые слова: Tokamak, coils toroidal, HTS, REBCO, tapes, stacked blocks, cable-in-conduit conductor, mechanical properties, stress effects, design
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
Ключевые слова: Tokamak, coils toroidal, LTS, Nb3Sn, cable-in-conduit conductor, joints superconducting , resistance, coatings, fabrication, test results
Ключевые слова: Tokamak, coils toroidal, jacket, eddy currents, defects, surface, ex-situ process
Ключевые слова: Tokamak, magnets, LTS, cable-in-conduit conductor, jacket, jacketing, joints, fabrication
Ключевые слова: Tokamak, cooling technology, cryogenic systems, modeling, thermal performance, shields, test results
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
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
Tsuchiya K., Hamada K., Fukui K., Kawano K., Abe T., Murakami H., Tomarchio V., Natsume K., Hoa C., Michel F., Wanner M., Otsu K.
Ключевые слова: Tokamak, central coils, coils solenoidal, coils poloidal field, quench detection, modeling, numerical analysis
Ключевые слова: Tokamak, divertor, magnetic systems, LTS, NbTi, cable-in-conduit conductor, feeder, design parameters, thermal performance, thermal-hydraulics, modeling, numerical analysis, facility
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