Mitchell N., Wang L., Shen G., Dolgetta N., Simon F., Oliva A.B., Lim B., Ilin Y., Liao M., Lopez M., Reich J.
Ключевые слова: ITER, coils poloidal field, fabrication, installation, photo, review
Ключевые слова: Tokamak, coils toroidal, LTS, Nb3Sn, cable-in-conduit conductor, joints superconducting , resistance, coatings, fabrication, test results
Ключевые слова: Tokamak, LTS, Nb3Sn, strands, coils toroidal, design, joints, design, fabrication, NbTi, cable-in-conduit conductor, bus bar conductor, test results
Ключевые слова: LTS, Nb3Sn, coils toroidal, annealing process, joints, heat treatment, safety, modeling, numerical analysis
Xie Y., Song Y., Wang C., Sborchia C., Smith K., Wu W., Wu H., Lu K., Shen G., Wei J., Readman P., Valente P., Hu X.Y.
Ключевые слова: ITER, coils poloidal field, coils pancake, design, cryogenic systems, cycling, thermal performance, fabrication, test results, measurement setup
Ключевые слова: presentation, Tokamak, China, design parameters, design parameters, coils toroidal, magnetic systems, prototype, LTS, Nb3Sn, hybrid systems, comparison, ITER, magnetic field distribution, stability, mechanical properties, stress distribution, cooling technology, deformation, winding configurations, central coils, experimental results
Xie Y., Han H., Song Y., Sborchia C., Smith K., Wu W., Zhang Z., Wu H., Zhang M., Lu K., Shen G., Wei J., Readman P., Valente P., Bilbao M., Wen W., Jiang K.
Ключевые слова: ITER, coils poloidal field, welding, termination, deformation, mechanical properties, cycling, experimental results
Ключевые слова: ITER, coils pancake, coils poloidal field, winding configurations, fabrication, LTS, NbTi
Song Y., Sborchia C., Smith K., Wu W., Zhang Z., Wu H., Lu K., Shen G., Wei J., Du S., Readman P., Valente P., Penate J.
Ключевые слова: ITER, coils poloidal field, cryogenic systems, mechanical properties, fatigue behavior, test results
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.
Ключевые слова: ITER, coils toroidal, joints, design, LTS, NbTi, cryogenic systems, mechanical properties, stress distribution
Mitchell N., Chen Y., Devred A., Song Y., Huang X., Clayton N., Liu C., Gung C., Cheng Y., Ding K., Lu K., Shen G., Feng H., Yu X., Sato N., Niu E., Pierre B.
Ключевые слова: ITER, feeder, China, review, status, HTS, current leads, joints, thermal properties, shields
Ключевые слова: ITER, current leads, fabrication, HTS, Bi2223
Mitchell N., Bi Y., Bauer P., Zhou T., Devred A., Song Y., Huang X., Liu C., Gung C., Ding K., Shen G., Feng H., Ni Q.
Ключевые слова: ITER, current leads, HTS, Bi2223, stacked blocks, model small-scale, critical caracteristics, critical current, joints, quench properties, voltage drops, design, test results
Mitchell N., Yang Y., Bi Y., Bauer P., Taylor T., Zhou T., Devred A., Song Y., Ballarino A., Ding K., Shen G., Foussat A.
Ключевые слова: ITER, current leads, design, HTS, Bi2223, design parameters, stacked blocks, heat exchanger
Mitchell N., Bi Y., Bauer P., Wang Z., Chen Y., Zhou T., Devred A., Song Y., Huang X., Gung C., Cheng Y., Ding K., Lu K., Shen G., Sahu A., Jong C., Dolgetta N., Ilin Y.
Ключевые слова: feeder, ITER, design, fabrication, termination, vacuum structure, cryostat
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