A thermo-hydraulic analysis of the superconducting proposal for the TF magnet system of FAST

G.M. Polli, A. Della Corte, A. Di Zenobio, L. Muzzi, L. Reccia, S. Turtù, G. Brolatti, F. Crisanti, A. Cucchiaro, A. Pizzuto, R. Villari

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Abstract

FAST (Fusion Advanced Studies Torus), the Italian proposal of a satellite facility to ITER, is a compact tokamak (R0= 1.82 m, a = 0.64 m, triangularity δ = 0.4) able to investigate non linear dynamics effects of α-particle behavior in burning plasmas and to test technical solutions for the first wall/divertor directly relevant for ITER and DEMO. Currently, ENEA is investigating the feasibility of a superconducting solution for the magnet system. This paper focuses on the analysis of the TF magnets thermal behavior. In particular, utilizing only the room available in the resistive design and referring to one of the most severe scenario envisaged for FAST, the minimum temperature margin in the coil has been calculated for a thermal load distribution on winding and cable jacket due to nuclear heating only. © 2011 EURATOM. Published by Elsevier B.V. All rights reserved.
Original languageEnglish
Pages (from-to)1454 - 1457
Number of pages4
JournalFusion Engineering and Design
Volume86
Issue number6-8
DOIs
Publication statusPublished - Oct 2011
Externally publishedYes

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All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Civil and Structural Engineering
  • Mechanical Engineering

Cite this

Polli, G. M., Corte, A. D., Di Zenobio, A., Muzzi, L., Reccia, L., Turtù, S., ... Villari, R. (2011). A thermo-hydraulic analysis of the superconducting proposal for the TF magnet system of FAST. Fusion Engineering and Design, 86(6-8), 1454 - 1457. https://doi.org/10.1016/j.fusengdes.2011.01.107