Conductors of the ITER magnets

Author

Bessette, D. ; Mitchell, N. ; Zapretilina, E. ; Takigami, H.

Author_Institution

ITER Naka-JCT, Ibaraki, Japan

Volume

11

Issue

1

fYear

2001

fDate

3/1/2001 12:00:00 AM

Firstpage

1550

Lastpage

1553

Abstract

Nb₃Sn and NbTi cable in conduit conductors (CICCs) cooled by a supercritical helium forced flow are considered in the ITER magnets. The design of the various CICCs relies on consideration of cost and manufacture as well as on the R&D performed on conductors for the ITER Model Coils. The amount of superconducting strand is optimized to satisfy operational requirements such as a minimum temperature margin, a heat power balance for stability (Stekly parameter), and a maximum hot spot temperature in case of quench. The conductor design and the main results of the conductor thermohydraulic analysis are discussed including consideration of nonuniform current distribution among superconducting strands

Keywords

cooling; current distribution; fusion reactor design; liquid helium; multifilamentary superconductors; niobium alloys; superconducting cables; superconducting magnets; tin alloys; titanium alloys; ITER Model Coils; ITER magnets; Nb₃Sn; Nb₃Sn cable in conduit conductors; NbTi; NbTi cable in conduit conductors; Stekly parameter; conductor thermohydraulic analysis; cooling; heat power balance; maximum hot spot temperature; minimum temperature margin; nonuniform current distribution; operational requirements; stability; superconducting strand; superconducting strands; supercritical helium forced flow; Conductors; Helium; Niobium compounds; Power cables; Superconducting cables; Superconducting coils; Superconducting magnets; Temperature; Tin; Titanium compounds;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/77.920072

Filename

920072