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The three RF additional heating systems for FAST (Articolo in rivista)
- Type
- Label
- The three RF additional heating systems for FAST (Articolo in rivista) (literal)
- Anno
- 2009-01-01T00:00:00+01:00 (literal)
- Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#doi
- 10.1016/j.fusengdes.2008.12.048 (literal)
- Alternative label
Mirizzi, Francesco[ 1 ] ; Bruschi, Alessandro[ 2 ] ; Cardinali, Alessandro[ 1 ] ; Cesario, Roberto[ 1 ] ; Granucci, Gustavo[ 2 ] ; Maggiora, Riccardo[ 3 ] ; Panaccione, Luigi[ 1 ] ; Ridolfini, Vincenzo Pericoli[ 1 ] ; Ravera, Gian Luca[ 1 ] ; Tuccillo, Angelo A.[ 1 ] (2009)
The three RF additional heating systems for FAST
in Fusion engineering and design
(literal)
- Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#autori
- Mirizzi, Francesco[ 1 ] ; Bruschi, Alessandro[ 2 ] ; Cardinali, Alessandro[ 1 ] ; Cesario, Roberto[ 1 ] ; Granucci, Gustavo[ 2 ] ; Maggiora, Riccardo[ 3 ] ; Panaccione, Luigi[ 1 ] ; Ridolfini, Vincenzo Pericoli[ 1 ] ; Ravera, Gian Luca[ 1 ] ; Tuccillo, Angelo A.[ 1 ] (literal)
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- http://www.sciencedirect.com/science/article/pii/S0920379608004821 (literal)
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- ISI Web of Science (WOS) (literal)
- Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#affiliazioni
- [ 1 ] CR Frascati, Assoc EURATOM ENEA Fus, I-00044 Frascati, Italy
[ 2 ] IFP CNR, Assoc EURATOM CNR Fus, I-20125 Milan, Italy
[ 3 ] Politecn Torino, I-10129 Turin, Italy (literal)
- Titolo
- The three RF additional heating systems for FAST (literal)
- Abstract
- FAST (Fusion Advanced Studies Torus) is a new tokamak machine proposed by the Italian Fusion Association as a Satellite Tokamak for the ITER programme. FAST will operate with deuterium plasmas to avoid the complexity deriving from the use of tritium. Therefore burning plasma conditions, where energy density of fast ions and of charged fusion products is a significant fraction of the total plasma energy density, will be achieved by accelerating plasma ions above the half-MeV range through an Ion Cyclotron Resonance Heating (ICRH) system (P=30 MW, f=60-90 MHz). For long pulse Advanced Tokamak (AT) scenarios, a Lower Hybrid Current Drive (LHCD) system (P=6 MW,f=3.7 GHz) has been envisaged to actively control the current profile, whereas an Electron Cyclotron Resonant Heating (ECRH) system (P=4 MW. f=170 GHz) will provide enough RF power for MHD control. (C) 2008 Elsevier B.V. All rights reserved. (literal)
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