Ключевые слова: DEMO, status, fusion magnets, Tokamak, magnetic systems, neutron irradiation, modeling, coils poloidal field, design parameters, design, divertor
Jiang B., Song Y., Wang C., Sborchia C., Smith K., Wu W., Zhang Z., Wu H., Lu K., Shen G., Wei J., Readman P., Valente P., Vercelli G., Bilbao M., Penate J.C.
Gaio E., Lampasi A., Zito P., Starace F., Costa P., Maffia G., Minucci S., Toigo V., Zanotto L., Ciattaglia S.
Ключевые слова: power supply, divertor, torque, test results, coils poloidal field, coils toroidal, modeling, numerical analysis, torque
Ключевые слова: ITER, coils poloidal field, current, magnetization, numerical analysis
Anashkin I.O., Khvostenko P.P., Bondarchuk E.N., Belyakov V.A., Injutinc N.V., Romannikov A.N., Solopeko A.V.
Ключевые слова: Tokamak, magnetic systems, design parameters, fabrication, coils toroidal, coils poloidal field, coils solenoidal
Ключевые слова: ITER, DEMO, Japan, Europe, Tokamak, status, design parameters, coils toroidal, coils poloidal field, central coils, HTS, current leads, shields, thermal performance, cryostat, divertor, cryogenic systems, power supply, review
Vysotsky V.S., Lelekhov S.A., Potanina L.V., Fetisov S.S., Shutov K.A., Patrikeev V.M., Taran A.V., Kaverin D.S., Kochetov M.V., Chensky I.F., Tronza V.I.
Ключевые слова: ITER, coils poloidal field, coils toroidal, Russia, review, cable-in-conduit conductor, cables, fabrication, jacketing, twist-pitch, microstructure, crack formation, LTS, NbTi, Nb3Sn, RRR parameter, hydraulic performances
Eisterer M., Potanina L., Abdyukhanov I., Pantsyrny V., Lukyanov P.A., Lelekhov S., Polikarpova M., Karasev Y., Baumgartner T., Malchenkov A.V., Konovalov Y., Weber W.
Vysotsky V.S., Lelekhov S.A., Potanina L.V., Fetisov S.S., Shutov K.A., Patrikeev V.M., Taran A.V., Kaverin D.S., Kochetov M.V., Chensky I.F., Tronza V.I.
Ключевые слова: ITER, coils poloidal field, coils toroidal, Russia, review, cable-in-conduit conductor, cables, fabrication, jacketing, twist-pitch, microstructure, crack formation, LTS, NbTi, Nb3Sn, RRR parameter, hydraulic performances
Ключевые слова: Tokamak, coils poloidal field, power supply, test results, current waveforms
Ключевые слова: ITER, coils poloidal field, joints, stability, heat transfer, RRR parameter
Ключевые слова: HTS, magnets, design, induction heating, dc performance, cryogenic systems, GdBCO, coated conductors, design parameters, insulating medium, stainless steel, magnetic field distribution, numerical analysis, fabrication, coils poloidal field, discharge characteristics, critical caracteristics, current-voltage characteristics, flux density, test results
Ключевые слова: DEMO, coils toroidal, design parameters, react-and-wind technique, central coils, coils solenoidal, coils poloidal field, winding techniques, cable-in-conduit conductor, LTS, Nb3Sn, degradation studies, mechanical properties, stress effects, magnetic field distribution, stress distribution, critical caracteristics, Jc/B curves, HTS, comparison
Rodin I., Bursikov A., Belyakov V., Pugachev A., Mednikov A., Klimchenko Y., Marushin E., Nasluzov S., Stepanov D., Ustinov A.
Ключевые слова: coils poloidal field, magnets double pancake, winding techniques, ITER, facility
Ключевые слова: quench detection, Tokamak, coils poloidal field, modeling, numerical analysis
Ключевые слова: Tokamak, LTS, Nb3Sn, central coils, coils equilibrium field, fabrication, coils poloidal field
Ключевые слова: SULTAN, test results, comparison, ITER, magnetic systems, coils toroidal, coils poloidal field, central coils, LTS, Nb3Sn, NbTi, cable-in-conduit conductor, facility
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