FAST Load Assembly conceptual design

2009 23rd IEEE/NPSS Symposium on Fusion Engineering Pub Date : 2009-06-01 DOI:10.1109/FUSION.2009.5226387

A. Cucchiaro, G. Brolatti, G. Calabrò, V. Cocilovo, A. Coletti, R. Coletti, P. Costa, P. Frosi, F. Crescenzi, F. Crisanti, G. Granucci, G. Maddaluno, V. Pericoli-Ridolfini, A. Pizzuto, C. Rita, G. Ramogida, S. Roccella, P. Rossi

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Abstract

FAST (Fusion Advanced Studies Torus) is a proposal for a Satellite Facility which can contribute the rapid exploitation of ITER and prepare ITER and DEMO regimes of operation, as well as exploiting innovative DEMO technology. FAST is a compact (Ro = 1.82 m, a = 0.64 m, triangularity δ = 0.4) machine able to investigate non linear dynamics effects of alpha particle behaviours in burning plasmas [1][ [2][5]. The project is based on a dominant 30 MW of ICRH, 6 MW of LH and 4 MW of ECRH. FAST operates at a wide range [3][4] of parameters e.g., in high performance H-Mode (BT up to 8.5 T; IP up to 8 MA) as well as in Advanced Tokamak operation (IP=3 MA), and full non inductive current scenario (IP=2 MA). Helium gas at 30 K is used for cooling the resistive copper magnets [6]. That allows for a pulse duration up to 170 s. Tungsten (W) or Liquid Lithium (L-Li) have been chosen as the divertor plates material, and Argon or Neon as the injected impurities to mitigate the thermal loads.

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FAST负载总成概念设计

FAST(聚变高级研究环)是一个卫星设施的建议，它可以促进ITER的快速利用，并为ITER和DEMO的运行制度做准备，以及开发创新的DEMO技术。FAST是一种紧凑(Ro = 1.82 m, a = 0.64 m，三角形δ = 0.4)的机器，能够研究燃烧等离子体中α粒子行为的非线性动力学影响[1][[2][5]。该项目以30兆瓦的ICRH、6兆瓦的LH和4兆瓦的ECRH为基础。FAST可以在很宽的参数范围内工作[3][4]，例如，在高性能H-Mode (BT高达8.5 T;IP高达8 MA)，以及在高级托卡马克操作(IP=3 MA)，和全无感电流场景(IP=2 MA)。30k的氦气用于冷却电阻铜磁体[6]。这使得脉冲持续时间长达170秒。选择钨(W)或液态锂(L-Li)作为导流板材料，氩气或氖气作为注入杂质来减轻热负荷。

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2009 23rd IEEE/NPSS Symposium on Fusion Engineering

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