Overview of the RFX-mod fusion science programme

Martin, P.; Puiatti, M. E.; Agostinetti, P.; Agostini, M.; Alonso, A.; Antoni, V.; Apolloni, L.; Auriemma, F.; Avino, Fabio; Barbalace, Antonio; Barbisan, M.; Barbui, T.; Barison, S.; Barp, M.; Baruzzo, M.; Bettini, Paolo; Bigi, M.; Bilel, R.; Boldrin, M.; Bolzonella, T.; Bonfiglio, D.; Bonomo, F.; Brombin, M.; Buffa, A.; Bustreo, Chiara; Canton, A.; Cappello, S.; Carralero, D.; Carraro, L.; Cavazzana, R.; Chacòn, Luis; Chapman, B. E.; Chitarin, G.; Ciaccio, G.; Cooper, W. A.; Bello, S. Dal; Palma, M. Dalla; Delogu, R.; Lorenzi, A. De; Delzanno, Gian Luca; Masi, G.; Muri, M. De; Dong, J. Q.; Escande, Dominique; Fantini, F.; Fasoli, A.; Fassina, A.; Fellin, F.; Ferro, A.; Fiameni, S.; Finn, John M.; Finotti, Claudio; Fiorentin, A.; Fonnesu, N.; Framarin, J.; Franz, P.; Frassinetti, L.; Furno, I.; Palumbo, Maurizio Furno; Gaio, E.; Gazza, E.; Ghezzi, F.; Giudicotti, L.; Gnesotto, F.; Gobbin, M.; Gonzales, W. A.; Grando, L.; Guo, S. C.; Hanson, J.D.; Hidalgo, C.; Hirano, Y.; Hirshman, S. P.; Ide, S.; In, Y.; Innocente, P.; Jackson, G.L.; Kiyama, S.; Liu, S. F.; Liu, Y. Q.; Bruna, D. Lòpez; Lorenzini, R.; Luce, T. C.; Luchetta, A.; Maistrello, A.; Manduchi, G.; Mansfield, D.K.; Marchiori, G.; Marconato, N.; Marcuzzi, D.; Marrelli, L.; Martini, S.; Matsunaga, G.; Martines, E.; Mazzitelli, G.; McCollam, K. J.; Momo, B.; Moresco, M.; Munaretto, S.; Novello, L.; Okabayashi, M.; Olofsson, Erik; Paccagnella, R.; Pasqualotto, R.; Pavei, M.; Peruzzo, S.; Pesce, A.; Pilan, N.; Piovan, R.; Piovesan, P.; Piron, C.; Piron, L.; Pomaro, N.; Predebon, I.; Recchia, M.; Rigato, V.; Rizzolo, A.; Roquemore, A. L.; Rostagni, G.; Ruzzon, A.; Sakakita, Hajime; Sánchez, Raúl; Sarff, J. S.; Sartori, E.; Sattin, F.; Scaggion, A.; Scarin, P.; Schneider, W.; Serianni, G.; Sonato, P.; Spada, E.; Soppelsa, A.; Spagnolo, S.; Spolaore, M.; Spong, D. A.; Spizzo, G.; Takechi, M.; Taliercio, C.; Terranova, D.; Theiler, C.; Toigo, V.; Trevisan, G.L.; Valente, M.; Valisa, M.; Veltri, P.; Veranda, M.; Vianello, N.; Villone, F.; Wang, Z. R.; White, R. B.; Xu, Xiaojing; Zaccaria, P.; Zamengo, A.; Zanca, P.; Zaniol, B.; Zanotto, L.; Zilli, E.; Zollino, G.; Zuin, M.

doi:10.1088/0029-5515/53/10/104018

Cited by 18 publications

(10 citation statements)

References 64 publications

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“…In the tokamak configuration, as reported in [13], the RFXmod device demonstrated stable operation at q edge < 2, a still unexplored scenario for tokamaks. Successful (2,1) mode stabilization is obtained by either radial or poloidal sensors, provided that a proper control algorithm is implemented [14].…”

Section: Operational Scenariosmentioning

confidence: 69%

“…The RFX-mod advanced and versatile control system has been exploited to study the effect of clean external MPs on several physics issues. Previously reported was the impact on flow, reversing from counter-to co-I p direction in the presence of a non-resonant perturbation, due to an increased edge stochasticity [13,47].…”

Section: Effect Of External Mps In the Tokamak Configurationmentioning

confidence: 96%

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Overview of the RFX-mod contribution to the international Fusion Science Program

Puiatti¹,

Bello²,

Marrelli³

et al. 2015

Nucl. Fusion

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The RFX-mod device is operated both as a reversed field pinch (RFP), where advanced regimes featuring helical shape develop, and as a tokamak. Due to its flexibility, RFX-mod is contributing to the solution of key issues in the roadmap to ITER and DEMO, including MHD instability control, internal transport barriers, edge transport and turbulence, isotopic effect, high density limit and three-dimensional (3D) non-linear MHD modelling. This paper reports recent advancements in the understanding of the self-organized helical states, featuring a strong electron transport barrier, in the RFP configuration; the physical mechanism driving the residual transport at the barrier has been investigated. Following the first experiments with deuterium as the filling gas, new results concerning the isotope effect in the RFP are discussed. Studies on the high density limit show that in the RFP it is related to a toroidal particle accumulation due to the onset of a convective cell. In the tokamak configuration, q(a) regimes down to q(a) = 1.2 have been pioneered, with (2,1) tearing mode (TM) mitigated and (2,1) resistive wall mode (RWM) stabilized: the control of such modes can be obtained both by poloidal and radial sensors. Progress has been made in the avoidance of disruptions due to the (2,1) TM by applying q(a) control, and on the general issue of error field control. The effect of externally applied 3D fields on plasma flow and edge turbulence, sawtooth control and runaway electron decorrelation has been analysed. The experimental program is supported by substantial theoretical activity: 3D non-linear visco-resistive MHD and non-local transport modelling have been advanced; RWMs have been studied by a toroidal MHD kinetic hybrid stability code.

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Section: Operational Scenariosmentioning

confidence: 69%

Section: Effect Of External Mps In the Tokamak Configurationmentioning

confidence: 96%

Overview of the RFX-mod contribution to the international Fusion Science Program

Puiatti¹,

Bello²,

Marrelli³

et al. 2015

Nucl. Fusion

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“…There is no experimental evidence showing whether shaped plasmas in an RFP can bring an advantage for its performance. Recently, significant progress has been made in RFP studies both in experiments and theory [5,6]. The question of how to improve the RFP design towards an advanced fusion device is placed on the agenda.…”

Section: Introductionmentioning

confidence: 99%

Does shaping bring an advantage for reversed field pinch plasmas?

Guo

Wang

et al. 2013

Nucl. Fusion

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The MHD–kinetic hybrid toroidal stability code MARS-K (Liu et al 2008 Phys. Plasmas 15 112503) is applied to study the shaping effects on magnetohydrodynamic (MHD) stabilities in reversed field pinch (RFP) plasmas, where both elongation and triangularity are taken into account. The ideal wall β (the ratio of the gaso-kinetic to magnetic pressures) limit set by the ideal kink mode/resistive wall mode in shaped RFP is investigated first, followed by a study of the kinetic damping on the resistive wall mode. Physics understanding of the results is provided by a systematic numerical analysis. Furthermore, the stability boundary of the linear resistive tearing mode in shaped RFP plasmas is computed and compared with that of the circular case. Finally, bootstrap currents are calculated for both circular and shaped RFP plasmas. Overall, the results of these studies indicate that the current circular cross-section is an appropriate choice for RFP devices, in the sense that the plasma shaping does not bring an appreciable advantage to the RFP performance in terms of macroscopic stabilities. In order to reach a steady-state operation, future RFP fusion reactors will probably need a substantial fraction of external current drives, due to the unfavourable scaling for the plasma-generated bootstrap current in the RFP configuration.

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“…Even though the toroidal experiment has been designed to operate in reversed field pinch configuration, thanks to an easily reconfigurable winding and power supply systems and to a very flexible control system, RFX-mod operated also as a low plasma current (I p < 150 kA) Tokamak. Several experimental campaigns related to low-q (q edge < 2) operations [17], sawtoothing mitigation and runaway decorrelation through 3D applied perturbations [18,19], L-H transition in circular and D-shaped plasmas [20], have been successfully run.…”

Section: Rfx-mod2mentioning

confidence: 99%

Design of a new reflectometric system for real time plasma position control on the RFX-mod2 device

Cavazzana¹,

Abate²,

Bernardi³

et al. 2022

J. Inst.

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RFX-mod2 (R = 2.0 m, a = 0.49 m), the upgraded version of the previous RFXmod fusion device, will be equipped with a new reflectometry system specifically designed for plasma position control purposes. Featuring a high temporal and spatial resolution and being suitable for harsh fusion reactor experimental conditions (long pulses, high neutron fluxes), reflectometry has been proposed as a good candidate for this task. On RFX-mod2 the diagnostic system will consist of four bistatic ultrafast independent reflectometric units working in the frequency range (16–26.5 GHz) and installed in four different poloidal locations at the same toroidal angle: two on the equatorial plane (high field side/low field side) and two at the vertical top/bottom ports. Standard pyramidal horns will be installed in the external midplane and in the vertical ports, while parabolic hoghorn reflectors have been designed for the internal midplane. Different technical solutions for the integration in the machine, as the additive manufacturing for the antenna production, are presented. Despite the differences with respect to the application on large Tokamaks like DEMO, the RFX-mod2 plasma position reflectometer can contribute to test on a simple machine some of the issues related to the development of a reflectometry based plasma position and shape control.

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Overview of the RFX-mod fusion science programme

Cited by 18 publications

References 64 publications

Overview of the RFX-mod contribution to the international Fusion Science Program

Overview of the RFX-mod contribution to the international Fusion Science Program

Does shaping bring an advantage for reversed field pinch plasmas?

Design of a new reflectometric system for real time plasma position control on the RFX-mod2 device

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