Conceptual design of the ITER TF model coil

Author

Libeyre, P. ; Bertrand, B. ; Decool, P. ; Turck, B. ; Komarek, P. ; Maurer, W. ; Ulbricht, A. ; Zahn, G. ; Spadoni, M. ; Salpietro, E.

Author_Institution

CEA, Centre d´´Etudes Nucleaires de Cadarache, France

Volume

32

Issue

4

fYear

1996

fDate

7/1/1996 12:00:00 AM

Firstpage

2260

Lastpage

2263

Abstract

The aims of the toroidal field (TF) model coil are to test the manufacturing feasibility of the ITER TF magnet concepts, to assess the reliability of the fully integrated system by dedicated testing and to qualify the quality assurance and the testing methods. The 3.8 m long racetrack shaped TFMC will be tested in the TOSKA facility at Karlsruhe in a configuration using the Euratom LCT Coil to provide in-plane and out-of-plane loads, relevant to the ITER coils

Keywords

design engineering; fusion reactor materials; fusion reactors; quality control; superconducting coils; superconducting device testing; superconducting magnets; test facilities; ITER superconducting coils; conceptual design; manufacturing feasibility; quality assurance; reliability; testing methods; toroidal field model coil; Coils; Conductors; Electronic design automation and methodology; Erbium; Insulation testing; Plasma materials processing; System testing; Temperature; Toroidal magnetic fields; Virtual manufacturing;

fLanguage

English

Journal_Title

Magnetics, IEEE Transactions on

Publisher

ieee

ISSN

0018-9464

Type

jour

DOI

10.1109/20.508616

Filename

508616