The fusion advanced studies torus (FAST): A proposal for an ITER satellite facility in support of the development of fusion energy

A. Pizzuto, F. Gnesotto, M. Lontano, R. Albanese, G. Ambrosino, M.L. Apicella, M. Baruzzo, A. Bruschi, G. Calabrò, A. Cardinali, R. Cesario, F. Crisanti, V. Cocilovo, A. Coletti, R. Coletti, P. Costa, S. Briguglio, P. Frosi, F. Crescenzi, V. CoccoreseA. Cucchiaro, C. Di Troia, B. Esposito, G. Fogaccia, E. Giovannozzi, G. Granucci, G. Maddaluno, R. Maggiora, M. Marinucci, D. Marocco, P. Martin, G. Mazzitelli, F. Mirizzi, S. Nowak, R. Paccagnella, L. Panaccione, G.L. Ravera, F. Orsitto, V. Pericoli Ridolfini, G. Ramogida, C. Rita, M. Santinelli, M. Schneider, A.A. Tuccillo, R. Zagórski, M. Valisa, R. Villari, G. Vlad, F. Zonca

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Abstract

FAST is a new machine proposed to support ITER experimental exploitation as well as to anticipate DEMO relevant physics and technology. FAST is aimed at studying, under burning plasma relevant conditions, fast particle (FP) physics, plasma operations and plasma wall interaction in an integrated way. FAST has the capability to approach all the ITER scenarios significantly closer than the present day experiments using deuterium plasmas. The necessity of achieving ITER relevant performance with a moderate cost has led to conceiving a compact tokamak (R = 1.82 m, a = 0.64 m) with high toroidal field (BTup to 8.5 T) and plasma current (Ipup to 8 MA). In order to study FP behaviours under conditions similar to those of ITER, the project has been provided with a dominant ion cyclotron resonance heating system (ICRH; 30 MW on the plasma). Moreover, the experiment foresees the use of 6 MW of lower hybrid (LHCD), essentially for plasma control and for non-inductive current drive, and of electron cyclotron resonance heating (ECRH, 4 MW) for localized electron heating and plasma control. The ports have been designed to accommodate up to 10MW of negative neutral beams (NNBI) in the energy range 0.5-1 MeV. The total power input will be in the 30-40 MW range under different plasma scenarios with a wall power load comparable to that of ITER (P/R ∼ 22MWm-1). All the ITER scenarios will be studied: from the reference H mode, with plasma edge and ELMs characteristics similar to the ITER ones (Q up to ≈1.5), to a full current drive scenario, lasting around 170 s. The first wall (FW) as well as the divertor plates will be of tungsten in order to ensure reactor relevant © 2010 IAEA, Vienna.
Original languageEnglish
Article number095005
Pages (from-to)-
JournalNuclear Fusion
Volume50
Issue number9
DOIs
Publication statusPublished - Sep 2010
Externally publishedYes

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All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Condensed Matter Physics

Cite this

Pizzuto, A., Gnesotto, F., Lontano, M., Albanese, R., Ambrosino, G., Apicella, M. L., ... Zonca, F. (2010). The fusion advanced studies torus (FAST): A proposal for an ITER satellite facility in support of the development of fusion energy. Nuclear Fusion, 50(9), -. [095005]. https://doi.org/10.1088/0029-5515/50/9/095005