Toroidal high temperature superconducting coils for ISTTOK

被引：0

作者：

Fernandes, H. ^{[1
]}

Goemoery, F. ^{[3
]}

della Corte, A. ^{[2
]}

Celentano, G. ^{[2
]}

Souc, J. ^{[3
]}

Silva, C. ^{[1
]}

Carvalho, I. ^{[1
]}

Gomes, R. ^{[1
]}

Di Zenobio, A. ^{[2
]}

Messina, G. ^{[2
]}

机构：

[1] Inst Super Tecn, Lab Associado, Inst Plasmas & Fusao Nucl, Assoc Euratom IST, P-1049001 Lisbon, Portugal

[2] ENEA CR Frascati, I-00044 Frascati, RM, Italy

[3] Slovak Acad Sci, Inst Elect Engn, Bratislava 84104, Slovakia

来源：

FUSION ENGINEERING AND DESIGN | 2011年 / 86卷 / 6-8期

关键词：

HTS; Tokamak; Nuclear fusion; Toroidal field; Steady-state operation;

D O I：

10.1016/j.fusengdes.2011.03.089

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：

High temperature superconductors (HTS) are very attractive to be used in fusion devices mainly due to lower operations costs. The HTS technology has reached a point where the construction of toroidal field coils for a tokamak is possible. The feasibility of a tokamak operating with HTS is extremely relevant and ISTTOK is the ideal candidate for a meaningful test due to its small size (and consequently lower cost) and the possibility to operate in a steady-state inductive regime. In this paper, a conceptual study of the ISTTOK upgrade to a superconducting device is presented, along with the relevant boundary conditions to achieve a permanent toroidal field with HTS. It is shown that the actual state of the art in HTS allows the design of a toroidal field coil capable of generating the appropriate field on plasma axis while respecting the structural specification of the machine. (C) 2011 Elsevier B.V. All rights reserved.

引用

页码：1458 / 1461

页数：4

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