Mitchell N., Libeyre P., Martovetsky N., Decool P., Jong C., Schild T., Smith J., Freudenberg K., Everitt D., Cormany C., Gaxiola E., Reagan T., Pallisa J., Rossano G., Mullins, Potts R., Stephens A., Brun C., Bruton A., Mariani A., Vandergriff D.
Ключевые слова: presentation, ITER, LTS, Nb3Sn, Rutherford cables, central coils, fabrication, design, review, photo, compression, joints
Mitchell N., Kim H., Vostner A., Devred A., Clayton N., Torre A., Gung C., Laurenti A., Decool P., Doshi K., Boyer C., Huygen S., Martin B., Piccin R., Peluso B., Bale Y., Bayetti P., Bremond S., Brilleman T., Cerignat S., Dumoulin O., Fontaine A., Journeaux J., Kazuya H., Laquiere J., Michelier P., Nicolas L., Pignoly E., Tena P.
Ключевые слова: ITER, magnetic systems, review, high voltage process, insulation, discharge characteristics, feeder, bus bar conductor
Mitchell N., Libeyre P., Martovetsky N., Walsh R.P., Jong C., Lyraud C., Dolgetta N., Hatfield D., Smith J., Sgobba S., Evans D., McRae D.M., Reiersen W., Freudenberg K., Everitt D., Cormany C., Langeslag S., Gaxiola E., Journeaux J., Pearce R., Aviles I., Chae T., Hughes D., Reagan T., Litherl S.
Ключевые слова: ITER, central coils, fabrication, LTS, Nb3Sn, design parameters, winding configurations, joints, cryogenic systems
Mitchell N., Kim H., Hamada K., Libeyre P., Ilyin Y., Vostner A., Devred A., Baikalov A., Lim B.S., Gung C., Turck B., Dolgetta N., Simon F., Hua Q., Gaxiola E., Koczorowski S., Carl C.
Ключевые слова: ITER, coils, joints, fabrication, design parameters, fatigue behavior, test results, joint resistances, ac losses
Oliva A.B., Aprili P., Soto E.B., Batista R., Bellesia B., Robello E.B., Caballero J., Lino M.C., Cornelis M., Damone M., Harrison R., Cornella J., Kostopoulos C., Jimenez M., Libens K., Malpica O., Moreno A., Pellicer N., Poncet L., Tarrago S., Viladu E., Dormicchi O., Valle N., Lucas J., Felipe A., Francone R., Barbero P., Ribeiro J.S., Thyssen E., Devred A., Koczorowski S., Mitchell N.
Ключевые слова: ITER, coils toroidal, winding configurations, fabrication, test results, Europe, LTS, Nb3Sn, measurement technique, review
Ключевые слова: presentation, ITER, magnets, fabrication, coils toroidal, central coils, status, LTS, Nb3Sn, cable-in-conduit conductor, degradation studies, insulation, high voltage process, cryogenic systems, review
Mitchell N., Vostner A., Devred A., Romano G., Bessette D., Pong I., Bevillard G., Zhou C., Jewell M., Sullivan N.
Mitchell N., Wang L., Wang L., Libeyre P., Ilyin Y., Liu L., Li C., Dong X., Dolgetta N., Simon F., Wei J., Yu X., Sgobba S., Evans D., Niu E., Langeslag S.A., Fang C., Zheng W., Cormany C., Gaxiola E., Xin J.
Ключевые слова: ITER, correction coils, fabrication, winding techniques, insulation, joints, LTS, NbTi, cable-in-conduit conductor
Mitchell N., Alekseev A., Bessette D., Shatil N., Serio L., Belyakov V., Gornikel I., Sytchevsky S., Vasiliev V., Kalinin V., Kaparkova M., Arslanova D.
Ключевые слова: ITER, cryogenic systems, heat loads, pulsed operation, control systems, thermal-hydraulics, numerical analysis
Ключевые слова: ITER, magnetic systems, design, fabrication, status, review
Mitchell N., Hamada K., Domptail F., Zheng S., Surrey E., McIntosh S., Cave-Ayland K., Taylor N., Ash A.D., Holmes A.J.
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: ITER, coils poloidal field, joints, stability, heat transfer, RRR parameter
Mitchell N., Kim H., Ilyin Y., Chen L., Chen Y., Devred A., Clayton N., Gung C., Ding K., Lu K., Beemsterboer C., Farek J., Wen X., Man S., Naoyuki S.
Ключевые слова: bus bar conductor, ITER, joints, design, test results, feeder, heat loads, pressure drop
Mitchell N., Hamada K., Domptail F., Foussat A., Zheng S., Surrey E., McIntosh S., Holmes A., Cave-Ayland K., Ash A., Taylor N.
Ключевые слова: ITER, magnets, fault currents, cryogenic systems, coils poloidal field, vacuum structure, safety
Mitchell N., Libeyre P., Martovetsky N., Jong C., Lyraud C., Dolgetta N., Vollmann T., Hatfield D., Smith J., Sgobba S., Evans D., Reiersen W., Litherland S., Freudenberg K., Myatt L., Everitt D., Cormany C., Rosenblad P., Langeslag S., Gaxiola E., Journeaux J.Y., Brazelton C., Abbott R., Daubert J., Rackers K., Nentwich T.
Ключевые слова: ITER, central coils, fabrication, design, design parameters, mechanical properties, stress effects
Mitchell N., Koizumi N., Matsui K., Hamada K., Seo K., Hemmi T., Devred A., Alekseev A., Gung C., Harrison R., Gallix R., Jong C., Foussat A., Oliva A.B., Boyer C., Nakahira M., Gandel M., Rebollo E.B., Petit P., Journeaux J.Y., Koczorowski S., Rest M.L., Martin B., Reich J., Bellesia A.
Ключевые слова: ITER, coils toroidal, magnetic systems, LTS, Nb3Sn, winding techniques, installation, cable-in-conduit conductor, coils pancake, heat treatment, impregnation, fabrication, review
Mitchell N., Ilyin Y., Lim B.S., Smith K., Beemsterboer C., Simon F., Valente P., Hua Q., Sabadi N.P., Oustinov A.
Ключевые слова: ITER, coils poloidal field, fabrication, LTS, NbTi
Ключевые слова: ITER, quench protection, magnets, high voltage process, current limiting characteristics, design, resistor
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