2005
DOI: 10.1109/tasc.2005.849145
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Experimental Results of a 70 kA High Temperature Superconductor Current Lead Demonstrator for the ITER Magnet System

Abstract: In the frame of the European Fusion Technology Programme, the Forschungszentrum Karlsruhe and the CRPP Villigen have designed and built a 70 kA current lead for the ITER TF Coils using High Temperature Superconductors (HTS). At the beginning of 2004 the HTS current lead was installed and tested in the TOSKA facility of the Forschungszentrum Karlsruhe. The scope of the experiment was to characterize the current lead in steady state conditions and to explore the operation limits as well. For this, the temperatur… Show more

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Cited by 76 publications
(22 citation statements)
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“…As in previously manufactured HTS current leads [15], [18], a mechanically robust design is obtained by soldering of the HTS stacks into the milled grooves of a stainless steel support tube. The cold end copper contact at the bottom is used to connect the 1051-8223/$26.00 © 2011 IEEE two HTS current leads with a low temperature superconductor bus bar during testing.…”
Section: Outline Design Of the Current Leadsmentioning
confidence: 99%
“…As in previously manufactured HTS current leads [15], [18], a mechanically robust design is obtained by soldering of the HTS stacks into the milled grooves of a stainless steel support tube. The cold end copper contact at the bottom is used to connect the 1051-8223/$26.00 © 2011 IEEE two HTS current leads with a low temperature superconductor bus bar during testing.…”
Section: Outline Design Of the Current Leadsmentioning
confidence: 99%
“…As reference for the 68 kA HTS CL considered in this study, we use the 70 kA HTS CL demonstrator, which was tested in many different operative conditions up to 80 kA [6].The HX in the demonstrator was of the perforated plate type, i.e., the main helium flow direction was parallel to the central Cu bar and through a series of circular perforated fins radially brazed to the central bar. In the 1-D model presented here we adopt a MF HX, which is presently the leading design for the CL HX of fusion devices under construction.…”
Section: A Reference 68 Ka Hts Current Leadmentioning
confidence: 99%
“…With the development in the properties of high temperature superconducting (HTS) conductors, the HTS magnet could be considered as potential Tokamak magnet components with the advantages of higher operation temperature and critical current density [1][2][3]. At present, the application of HTS in fusion devices mainly focuses on the design and fabrication of high temperature superconducting high current conductor [4][5][6][7][8], the design and fabrication of high temperature superconducting current lead [9,10], and the concept design and small model fabrication of HTS magnet [11,12]. It was revealed that when the TF coil system operates at the temperature range of 10 to 20 K, accordingly, the manufacturing and operating cost of the device could be reduced [13].…”
Section: Introductionmentioning
confidence: 99%