DocumentCode
783323
Title
Mechanical design and analysis of joints for the ITER PF coils
Author
Libeyre, P. ; Decool, P.
Author_Institution
CEA/CADARACHE, St. Paul-Lez-Durance, France
Volume
12
Issue
1
fYear
2002
fDate
3/1/2002 12:00:00 AM
Firstpage
586
Lastpage
590
Abstract
The Poloidal Field (PF) coils of the International Thermonuclear Experimental Reactor (ITER) are designed with NbTi cable-in-conduit conductors (CICCs) wound in double pancakes which are connected in series by joints. These joints have to operate in the poloidal magnetic field which generate large varying forces. The conceptual design of the joints is based on the overlap concept with twin-boxes and includes a tie-bar to carry the tensile load and a clamping support to resist the radial and vertical loads. The mechanical analysis is performed with several finite-element models of the joint area. It is shown that the design allows to keep both the tensile stress in the conductor and the shear stress in the insulation within acceptable limits.
Keywords
Tokamak devices; cable jointing; cables (electric); finite element analysis; fusion reactor design; mechanical strength; niobium compounds; shear strength; stress-strain relations; superconducting coils; ITER PF coils; International Thermonuclear Experimental Reactor; NbTi; cable-in-conduit conductors; clamping support; double pancakes; finite-element models; joints; mechanical design; poloidal field coils; poloidal magnetic field; shear stress; tensile load; tie-bar; twin-boxes; Clamps; Coils; Conductors; Inductors; Magnetic analysis; Magnetic fields; Niobium compounds; Tensile stress; Titanium compounds; Wounds;
fLanguage
English
Journal_Title
Applied Superconductivity, IEEE Transactions on
Publisher
ieee
ISSN
1051-8223
Type
jour
DOI
10.1109/TASC.2002.1018472
Filename
1018472
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