This paper reports the highlights of the RFX-mod fusion science programme since the last 2010 IAEA Fusion Energy Conference. The RFX-mod fusion science programme focused on two main goals: exploring the fusion potential of the reversed field pinch (RFP) magnetic configuration and contributing to the solution of key science and technology problems in the roadmap to ITER. Active control of several plasma parameters has been a key tool in this endeavour. New upgrades on the system for active control of magnetohydrodynamic (MHD) stability are underway and will be presented in this paper. Unique among the existing fusion devices, RFX-mod has been operated both as an RFP and as a tokamak. The latter operation has allowed the exploration of edge safety factor q edge < 2 with active control of MHD stability and studies concerning basic energy and flow transport mechanisms. Strong interaction has continued with the stellarator community in particular on the physics of helical states and on three-dimensional codes.

Overview of the RFX-mod fusion science programme

ME Puiatti;P Agostinetti;M Agostini;V Antoni;S Barison;D Bonfiglio;F Bonomo;M Brombin;S Cappello;L Carraro;M Dalla Palma;A De Lorenzi;S Fiameni;E Gaio;F Ghezzi;M Gobbin;L Grando;P Innocente;A Luchetta;G Manduchi;G Marchiori;L Marrelli;S Martini;E Martines;R Paccagnella;R Pasqualotto;A Pesce;R Piovan;P Piovesan;N Pomaro;I Predebon;M Recchia;G Rostagni;P Scarin;G Serianni;M Spolaore;G Spizzo;C Taliercio;D Terranova;V Toigo;M Valisa;N Vianello;P Zaccaria;M Zuin
2013

Abstract

This paper reports the highlights of the RFX-mod fusion science programme since the last 2010 IAEA Fusion Energy Conference. The RFX-mod fusion science programme focused on two main goals: exploring the fusion potential of the reversed field pinch (RFP) magnetic configuration and contributing to the solution of key science and technology problems in the roadmap to ITER. Active control of several plasma parameters has been a key tool in this endeavour. New upgrades on the system for active control of magnetohydrodynamic (MHD) stability are underway and will be presented in this paper. Unique among the existing fusion devices, RFX-mod has been operated both as an RFP and as a tokamak. The latter operation has allowed the exploration of edge safety factor q edge < 2 with active control of MHD stability and studies concerning basic energy and flow transport mechanisms. Strong interaction has continued with the stellarator community in particular on the physics of helical states and on three-dimensional codes.
2013
Istituto di Chimica della Materia Condensata e di Tecnologie per l'Energia - ICMATE
Istituto di fisica del plasma - IFP - Sede Milano
Istituto gas ionizzati - IGI - Sede Padova
Flow transport
Fusion devices
IAEA Fusion Energy Conference
Magnetic configuration
Plasma param
Reversed field pinch
Science and Technology
Strong interaction
Plasma devices
Safety factor
Magnetohydrodynamics
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/211263
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