Design and manufacture of the US-ITER pre prototype joint sample

Author

Gung, C.Y. ; Michael, P.C. ; Randall, R.N. ; Smith, B.A. ; Hrycaj, T. ; Minervini, J.V. ; Montgomery, D.B.

Author_Institution

Plasma Fusion Center, MIT, Cambridge, MA, USA

Volume

7

Issue

2

fYear

1997

fDate

6/1/1997 12:00:00 AM

Firstpage

469

Lastpage

472

Abstract

The US-ITER pre prototype joint sample which has been fabricated at the MIT Plasma Fusion Center is the first attempt to fabricate an optimized full size joint which can be stably operated in ITER required AC background fields at reduced coupling losses. This paper presents an overview of the joint´s construction and fabrication, highlighting some of the procedural steps that have since been incorporated into fabrication of current terminations for the inner module ITER central solenoid (CS) model coil.

Keywords

fusion reactor design; fusion reactors; superconducting coils; superconducting magnets; AC background fields; US-ITER pre prototype joint sample design; US-ITER pre prototype joint sample manufacture; current terminations; fusion reactor; inner module ITER central solenoid model coil; optimized full size joint; reduced coupling losses; Cable shielding; Conductors; Coolants; Copper; Fabrication; Manufacturing; Niobium-tin; Plasma materials processing; Prototypes; Superconducting coils;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/77.614535

Filename

614535