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Addressing the Technical Challenges for the Construction of the ITER Central Solenoid
By: Lyraud, C.; Rodriguez-Mateos, F.; Jong, C.; Jewell, M.; Bessette, D.; Libeyre, P.; Sgobba, S.; Reed, R.; Dalder, E.; Myatt, L.; Freudenberg, K.; Litherland, S.; Hussung, R.; Rey, C.; Martovetsky, N.; Reiersen, W.; Hamada, K.;
2012 / IEEE
This item was taken from the IEEE Periodical ' Addressing the Technical Challenges for the Construction of the ITER Central Solenoid ' The Central Solenoid (CS) of the ITER Magnet system is split into six independently powered coils enclosed inside an external structure which provides vertical precompression thus preventing separation of the coils and acting as a support to net resulting loads. The analyses include an assessment of the mechanical behavior of the different components of the CS, under the normal and fault conditions, aiming at demonstrating the ability of the CS to achieve 30 000 cycles of plasma operation at nominal current (15 MA). A comprehensive material testing program is developed for the conductor jacket, the impregnated glass-epoxy insulation and the structure. The paper describes the architecture of the analysis and qualification programs and provides an overview of the results obtained so far.
Impregnated Glass-epoxy Insulation
Iter Magnet System
Iter Central Solenoid
Current 15 Ma
Engineered Materials, Dielectrics And Plasmas
Fields, Waves And Electromagnetics