Analysis of heat load, current margin and current non-uniformity in ITER PF coil joints

G. Rolando, E.P.A. van Lanen, J. van Nugteren, Wietse Offringa, Y. Ilyin, B. Lim, F. Simon, Arend Nijhuis

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The poloidal field (PF) magnet system of the International Thermonuclear Experimental Reactor (ITER) consists of six pulsed coils. Each coil comprises independent modules connected to each other through “shaking hands” joints. In the paper the results of the analysis of the electro-magnetic and thermal performance of the joints during the ITER 15 MA plasma scenario are presented. Of special concern is the radial magnetic field component that is particularly high close to the upper and lower edges of the coils. Moreover, the orientation of the joints in the PF coils is such as to give scope to large current loops between the two cables, which could potentially reduce the temperature and current margins to critical levels. The study has been carried out with the code JackPot-AC, which has been recently upgraded to allow a strand-level detailed analysis of lap-type joints.
Original languageEnglish
Article number4201405
JournalIEEE transactions on applied superconductivity
Issue number3
Publication statusPublished - 2013


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