Design of superconducting tokamak magnet systems and applications to HTS

被引：9

作者：

Portone, Alfredo ^{[1
]}

Giannini, Lorenzo ^{[2
]}

Lorenzo, Jose ^{[1
]}

Cau, Francesca ^{[1
]}

机构：

[1] Fusion Energy, ITER Delivery, Josep Pl 2,Torres Diagonal Litoral B3, Barcelona 08019, Spain

[2] ENEA Frascati, Via Enr Fermi 45, I-00044 Frascati, RM, Italy

来源：

FUSION ENGINEERING AND DESIGN | 2023年 / 193卷

关键词：

Tokamak; Fusion magnets; ITER; TEMPERATURE; FIELD;

D O I：

10.1016/j.fusengdes.2023.113862

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

In this paper we illustrate a self-consistent procedure to design the superconducting Toroidal Field (TF) and Central Solenoid (CS) magnet systems starting from the basic plasma dimensioning parameters. By defining the plasma major radius and minor radii, as well as the inboard TF coil neutron shielding radial built, we proceed by sizing the TF Winding Pack (WP), its case and the CS modules. The ITER magnets design philosophy and criteria are adopted throughout the study. A key outcome of this work is to illustrate the inter-play between machine size, magnetic field and availability of inductive flux for burn. In doing so we investigate the advantages brought by high field tokamak design compared the more conventional (ITER-like) Nb3Sn based magnet design solutions.

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