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 delta = 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 (B(T) up to 8.5 T; I(P) up to 8 MA) as well as in Advanced Tokamak operation (I(P)=3 MA), and full non inductive current scenario (I(P)=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.

FAST load assembly conceptual design

Granucci G;
2009

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 delta = 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 (B(T) up to 8.5 T; I(P) up to 8 MA) as well as in Advanced Tokamak operation (I(P)=3 MA), and full non inductive current scenario (I(P)=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.
2009
Istituto di fisica del plasma - IFP - Sede Milano
Inglese
23rd IEEE/NPSS Symposium on Fusion Engineering, 2009
23RD IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING
978-1-4244-2635-5
http://ieeexplore.ieee.org/xpl/articleDetails.jsp?arnumber=5226387&refinements%3D4281322951%2C4281396778%26sortType%3Dasc_p_Sequence%26filter%3DAND%28p_IS_Number%3A5226364%29
1-5 June 2009
San Diego, CA
____
18
none
Cucchiaro, A; Brolatti, G; Calabrò, G; Cocilovo, V; Coletti, A; Coletti, R; Costa, P; Frosi, P; Crescenzi, F; Crisanti, F; Granucci, G; Maddaluno, G; ...espandi
273
info:eu-repo/semantics/conferenceObject
04 Contributo in convegno::04.01 Contributo in Atti di convegno
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/209139
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