FAST: Feasibility Analysis for a Completely Superconducting Magnet System
FAST: Feasibility Analysis for a Completely Superconducting Magnet System
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DOI：
10.1109/tasc.2010.2089406
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发表时间：
2011-06
影响因子：
1.8
通讯作者：
A. Di Zenobio;A. della Corte;L. Muzzi;G. Polli;L. Reccia;S. Turtu;F. Crisanti;A. Cucchiaro;A. Pizzuto;R. Villari
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文献类型：
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作者：
A. Di Zenobio;A. della Corte;L. Muzzi;G. Polli;L. Reccia;S. Turtu;F. Crisanti;A. Cucchiaro;A. Pizzuto;R. Villari
FAST（Fusion Advanced Studies Torus）是意大利提出的ITER欧洲卫星设施方案，是一个紧凑型托卡马克装置（R 0 = 1.82 m，a= 0.64 m，三角形δ = 0.4），能够研究燃烧等离子体中α粒子行为的非线性动力学效应，并测试与ITER和DEMO直接相关的第一壁/偏滤器的技术解决方案（例如：全钨壁偏滤器和先进液态金属偏滤器）。该机器的设计与氘等离子体的无量纲参数范围接近的ITER和访问先进的托卡马克制度与长脉冲持续时间相对于当前的扩散时间。预测了等离子体轴上的最大磁场为8.5 T，最大等离子体电流为8 MA。在目前的设计阶段，ENEA正在研究超导解决方案的可行性。它由18个环形场、6个极向场和6个中心螺线管模块线圈组成，所有线圈均由Nb 3Sn和NbTi电缆导管导体缠绕。驱动磁铁的设计，从机械到中子和热分析的所有主要方面，在这里提出和讨论。
FAST (Fusion Advanced Studies Torus), the Italian proposal for a European 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 alpha-particle behavior in burning plasmas and to test technical solutions for the first wall/divertor directly relevant for ITER and DEMO (e.g.: full-tungsten wall and divertor and advanced liquid metal divertor). The machine is designed to operate with Deuterium plasmas in a dimensionless parameter range close to that of ITER and to access advanced tokamak regimes with long pulse duration with respect to the current diffusion time. It foresees a maximum magnetic field on plasma axis of 8.5 T and a maximum plasma current of 8 MA. In the present design phase, the feasibility of a superconducting solution for the magnet system is being investigated by ENEA. It consists of 18 Toroidal Field, 6 Poloidal Field and 6 Central Solenoid module coils, all of which wound by Nb3Sn and NbTi Cable-In-Conduit Conductors. All the main aspects driving the magnets' design, from mechanical to neutronic and thermal analyses, are here presented and discussed.