作者: L Zani , H Cloez , M Tena , A Della Corte , L Muzzi
DOI: 10.1088/0953-2048/18/12/028
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摘要: In the framework of International Thermonuclear Experimental Reactor (ITER) R&D programme part concerning Nb3Sn cable-in-conduit conductor Toroidal Field coils, a dedicated action was launched within European Fusion Technology Programme, designed to improve investigation impact bending strain on recently developed industrially advanced strands. order ensure that ITER TF coils experience relevant mechanical conditions, strands were jacketed inside 0.2 mm thick stainless steel tube, simulating influence jacket cable this paper we will describe in detail four candidate methods investigated for imposing pure controlled A common feature these is they study reaction strand heat treatment mandrel and transfer it onto test with different diameter. practice, imposed limited 0.5%. Two solutions are considered: reduction or an increase diameter mandrel. Also, two options possible removal at ends connection current leads: before after treatment. The tested provide area as large possible. Specific support together tool design manufacture be presented. general comparison all regards specified criteria also carried out precisely define process application method developed. We find finally best approach which radius increased removed