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

doi:10.1109/TASC.2012.2236131

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

Research output: Contribution to journal › Article › Academic › peer-review

5 Citations (Scopus)

Abstract

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 language	English
Article number	4201405
Journal	IEEE transactions on applied superconductivity
Volume	23
Issue number	3
DOIs	https://doi.org/10.1109/TASC.2012.2236131
Publication status	Published - 2013

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10.1109/TASC.2012.2236131

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

abstract = "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.",

author = "G. Rolando and {van Lanen}, E.P.A. and {van Nugteren}, J. and Wietse Offringa and Y. Ilyin and B. Lim and F. Simon and Arend Nijhuis",

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doi = "10.1109/TASC.2012.2236131",

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T1 - Analysis of heat load, current margin and current non-uniformity in ITER PF coil joints

AU - Rolando, G.

AU - van Lanen, E.P.A.

AU - van Nugteren, J.

AU - Offringa, Wietse

AU - Ilyin, Y.

AU - Lim, B.

AU - Simon, F.

AU - Nijhuis, Arend

PY - 2013

Y1 - 2013

N2 - 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.

AB - 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.

U2 - 10.1109/TASC.2012.2236131

DO - 10.1109/TASC.2012.2236131

M3 - Article

VL - 23

JO - IEEE transactions on applied superconductivity

JF - IEEE transactions on applied superconductivity

SN - 1051-8223

IS - 3

M1 - 4201405

ER -

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

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