Pre-Compression Requirements for the ITER Central Solenoid

Author

Fu, Y. ; Jong, C. ; Michael, P. ; Mitchell, N.

Author_Institution

ITER, Ibaraki

Volume

16

Issue

2

fYear

2006

fDate

6/1/2006 12:00:00 AM

Firstpage

791

Lastpage

794

Abstract

The ITER CS contains 6 identical but electrically independent modules. ITER plasma shaping requirements yield a wide range of radial (or hoop) loads and a wide range of vertical loads on each CS module. Pre-compression is used to maintain contact between the modules during all stages of plasma operation, to minimize primary tensile stresses in the coil insulation, and to prevent toroidal ratcheting of the modules during repeat operation. The preload requirements for the ITER Central Solenoid (CS) are the subject of this paper. Axial pre-compression of CS stack is carefully analyzed using finite element (FE) models. Conflicting requirements on the pre-compression structure (namely, the generation of large axial pre-compression with minimal use of radial space outside the modules) are balanced to support the desired plasma shapes

Keywords

finite element analysis; fusion reactor design; plasma diagnostics; superconducting magnets; C5 stack; ITER central solenoid; ITER plasma shaping; axial precompression requirements; coil insulation; finite element models; plasma operation; preload requirements; radial loads; toroidal ratcheting; vertical loads; Coils; Conductors; Finite element methods; Glass; Insulation; Material properties; Plasma temperature; Solenoids; Tensile stress; Thermal stresses; CS coil; ITER; pre-compression;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/TASC.2006.873257

Filename

1642966