Numerical Analysis of the ITER TF Conductor Samples in SULTAN With the THELMA Code

Author

Bellina, Fabrizio ; Bessette, Denis ; Breschi, Marco ; Zenobio, Aldo Di ; Ribani, Pier Luigi ; Richard, Laura Savoldi ; Zanino, Roberto

Author_Institution

Dipt. di Ing. Elettr., Univ. di Udine, Udine, Italy

Volume

19

Issue

3

fYear

2009

fDate

6/1/2009 12:00:00 AM

Firstpage

1457

Lastpage

1461

Abstract

The paper presents the results of a numerical analysis campaign which studies the steady-state behavior and the typical tests (current-sharing temperature and critical current measurements) foreseen for the SULTAN samples of the ITER TF reference conductor, with special emphasis to the current and electric field distribution among and along the sub-cables. In this analysis, the sample geometrical parameters (twist pitch, joint/termination length) and some electrical parameters (joint, termination and inter-bundle resistance) are supposed to range in their design or their measured boundaries, in order to understand their individual effect on the conductor performances and the test conditions.

Keywords

Tokamak devices; fusion reactor design; fusion reactor materials; fusion reactor theory; niobium alloys; numerical analysis; plasma toroidal confinement; superconducting cables; superconducting magnets; tin alloys; CICC; ITER design; Nb₃Sn; THELMA Code; cable in conduit conductor; critical current measurements; current-sharing temperature; electric field distribution; electrical parameters; geometrical parameters; numerical analysis; superconducting magnets; toroidal field conductor; CICC; ITER; Nb3Sn; SULTAN samples; modeling; superconducting magnets;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/TASC.2009.2018763

Filename

5067102