Title of article
A thermo-hydraulic analysis of the superconducting proposal for the TF magnet system of FAST
Author/Authors
Polli، نويسنده , , G.M. and Corte، نويسنده , , A. della and Di Zenobio، نويسنده , , A. and Muzzi، نويسنده , , L. and Reccia، نويسنده , , L. and Turtù، نويسنده , , S. and Brolatti، نويسنده , , G. and Crisanti، نويسنده , , F. and Cucchiaro، نويسنده , , A. and Pizzuto، نويسنده , , A. and Villari، نويسنده , , R.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2011
Pages
4
From page
1454
To page
1457
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.
Keywords
SIMULATION , thermal-hydraulics , ITER , FAST Tokamak , Fusion reactors , Superconducting coils
Journal title
Fusion Engineering and Design
Serial Year
2011
Journal title
Fusion Engineering and Design
Record number
2358301
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