Design of the ITER PF Coil Joints

Author

Simon, F. ; Boyer, C. ; Ilyin, Y. ; Beemsterboer, C. ; Byung Su Lim

Author_Institution

ITER Organ., St. Paul-lez-Durance, France

Volume

22

Issue

3

fYear

2012

fDate

6/1/2012 12:00:00 AM

Firstpage

4804104

Lastpage

4804104

Abstract

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.

Keywords

finite element analysis; superconducting coils; superconducting magnets; 2 T magnetic ήeld; ITER PF coil joints; ITER poloidal field magnet system; current 55 kA; current sharing; electrical model; electromagnetic forces; finite-element structural analyses; manufacturability procedure; repair procedure; size 8 m to 24 m; superconductors; twin-box concept; Coils; Conductors; Copper; Insulation; Joints; Stress; Welding; ITER; PF coil; joint; twin box;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/TASC.2011.2174562

Filename

6086589