Design of the ITER PF Coil Joints

• Published in: IEEE transactions on applied superconductivity Vol. 22; no. 3; p. 4804104
• Main Authors: Simon, F., Boyer, C., Ilyin, Y., Beemsterboer, C., Byung Su Lim
• Format: Journal Article Conference Proceeding
• Language: English
• Published: New York, NY IEEE 01.06.2012; Institute of Electrical and Electronics Engineers; The Institute of Electrical and Electronics Engineers, Inc. (IEEE)
• Subjects: Applied sciences; Coiling; Coils; Conductors; Copper; Design engineering; Electrical engineering. Electrical power engineering; Electromagnets; Exact sciences and technology; Insulation; ITER; joint; Joints; Modules; PF coil; Stress; Superconductivity; twin box; Various equipment and components; Welding; ITER tokamak; joint; Magnet; Electromagnetic force; twin box; Electrical model; PF coil; Finite element method; Nuclear fusion reactor; Poloidal field; Layout; Current distribution; Feasibility; ITER; Magnetic field; Alternating current
• ISSN: 1051-8223; 1558-2515
• DOI: 10.1109/TASC.2011.2174562

The ITER poloidal field magnet system consists of 6 pulsed coils with a diameter ranging from 8 m to 24 m and a weight of up to 400 t. The coils are made of independent modules connected to each other by joints. This paper summarizes the design constraints, including manufacturability and repair procedure, and the layout of the joints based on the "twin-box" concept. It particularly focuses on the structure of the joint and its support since the joints will operate at the maximum current of 55 kA in a 2 T magnetic field, and there- fore should be able to withstand high electromagnetic forces. In this article, we present the main results of the finite-element structural analyses of the joint. Finally, we summarize the main results of the electrical model developed to determine the losses (AC and transport current) and current sharing in the joint.