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View article: Upgrade of the Diagnostic Neutral Beam Injector for the RFX-mod2 experiment
Upgrade of the Diagnostic Neutral Beam Injector for the RFX-mod2 experiment Open
Diagnostic Neutral Beam Injectors (DNBI), through the combined use of Charge Exchange Recombination Spectroscopy (CHERS) and Motional Stark effect diagnostics (MSE), are a well-known tool to access important information about magnetically …
View article: Upgrade of the Diagnostic Neutral Beam Injector for the RFX-mod2 experiment
Upgrade of the Diagnostic Neutral Beam Injector for the RFX-mod2 experiment Open
Diagnostic Neutral Beam Injectors (DNBI), through the combined use of Charge Exchange Recombination Spectroscopy (CHERS) and Motional Stark effect diagnostics (MSE), are a well-known tool to access important information about magnetically …
View article: Runaway electron mitigation by 3D fields application in ASDEX Upgrade, COMPASS, and RFX-mod
Runaway electron mitigation by 3D fields application in ASDEX Upgrade, COMPASS, and RFX-mod Open
Disruption-generated runaway electron (RE) beams represent a potentially severe threat for tokamak plasma-facing components. Application of properly designed 3D fields can act as a mitigation mechanism, as recently investigated in ASDEX Up…
View article: RFX-mod2 diagnostic capability enhancements for the exploration of multi-magnetic-configurations
RFX-mod2 diagnostic capability enhancements for the exploration of multi-magnetic-configurations Open
The RFX-mod2 device, the upgraded version of the previous RFX-mod with a modified magnetic boundary, is presently under realization and will start to be operated in 2025. Significant upgrades of the diagnostic capabilities have been propos…
View article: RFX-mod2 as a flexible device for reversed-field-pinch and low-field tokamak research
RFX-mod2 as a flexible device for reversed-field-pinch and low-field tokamak research Open
The RFX-mod2 installation is planned to be completed by 2024 and the start of operations is expected in 2025. The high flexibility of the machine (already tested in the previous RFX-mod experiment) allows operation in Reversed Field Pinch …
View article: Dynamics of ultralow-q plasmas in the RFX-mod device
Dynamics of ultralow-q plasmas in the RFX-mod device Open
The results are presented of an experimental activity performed in the RFX-mod device aimed at characterizing plasma dynamics in the so-called Ultralow-q (ULq) magnetic configuration, which corresponds to edge safety factor values below 1.…
View article: Interaction of Tearing Modes With Passive Structures in a Tokamak
Interaction of Tearing Modes With Passive Structures in a Tokamak Open
In this work a surface current plasma model is coupled to a Volume Integral Formulation for studying the interaction between tokamak tearing modes and the machine metallic structures surrounding the plasma. By evaluating the passive respon…
View article: Turbulent filament properties in L and H-mode regime in the RFX-mod operating as a tokamak
Turbulent filament properties in L and H-mode regime in the RFX-mod operating as a tokamak Open
The dynamics of turbulent filaments in L and ELM-free H-mode in the RFX-mod device operating as a tokamak is discussed in the present work. L-H transition and sustained H-mode have been achieved in the RFX-mod with the aid of an external e…
View article: Three-dimensional simulations of plasma turbulence in the RFX-mod scrape-off layer and comparison with experimental measurements
Three-dimensional simulations of plasma turbulence in the RFX-mod scrape-off layer and comparison with experimental measurements Open
The tokamak scrape-off layer (SOL) plasma dynamics is investigated in a circular limiter configuration with a low edge safety factor. Focusing on the experimental parameters of two ohmic tokamak inner-wall limited plasma discharges in RFX-…
View article: H-mode achievement and edge features in RFX-mod tokamak operation
H-mode achievement and edge features in RFX-mod tokamak operation Open
The RFX-mod experiment is a fusion device designed to operate as a reversed field pinch (RFP), with a major radius R = 2 m and a minor radius a = 0.459 m. Its high versatility recently allowed operating it also as an ohmic tokamak, allowin…
View article: Overview of the RFX-mod fusion science activity
Overview of the RFX-mod fusion science activity Open
This paper reports the main recent results of the RFX-mod fusion science activity. The RFX-mod device is characterized by a unique flexibility in terms of accessible magnetic configurations. Axisymmetric and helically shaped reversed-field…
View article: Role of a continuous MHD dynamo in the formation of 3D equilibria in fusion plasmas
Role of a continuous MHD dynamo in the formation of 3D equilibria in fusion plasmas Open
International audience; Stationary 3D equilibria can form in fusion plasmas via saturation of magnetohydrodynamic (MHD) instabilities or stimulated by external 3D fields. In these cases the current profile is anomalously broad due to magne…
View article: Integration of the state observer RAPTOR in the real-time MARTe framework at RFX-mod
Integration of the state observer RAPTOR in the real-time MARTe framework at RFX-mod Open
The RAPTOR - RApid Plasma Transport simulatOR code is a model-based control-oriented code that predicts Tokamak plasma profile evolution in real-time. One of its key applications is in a state observer, where the real-time predictions are …
View article: Avoidance of tearing mode locking with electro-magnetic torque introduced by feedback-based mode rotation control in DIII-D and RFX-mod
Avoidance of tearing mode locking with electro-magnetic torque introduced by feedback-based mode rotation control in DIII-D and RFX-mod Open
Disruptions caused by tearing modes (TMs) are considered to be one of the most critical roadblocks to achieving reliable, steady-state operation of tokamak fusion reactors. We have demonstrated a promising scheme to avoid mode locking by u…
View article: Impact of ideal MHD stability limits on high-beta hybrid operation
Impact of ideal MHD stability limits on high-beta hybrid operation Open
The hybrid scenario is a candidate for stationary high-fusion gain tokamak operation in ITER and DEMO. To obtain such performance, the energy confinement and the normalized pressure βN must be maximized, which requires operating near or ab…
View article: Runaway electron mitigation by applied magnetic perturbations in RFX-mod tokamak plasmas
Runaway electron mitigation by applied magnetic perturbations in RFX-mod tokamak plasmas Open
Thanks to its advanced system for the control of magnetohydrodynamic modes, the RFX-mod device run as a tokamak is particularly suited to the study of the possible impact on runaway electron (RE) de-confinement in response to applied magne…
View article: Real time measurement of plasma macroscopic parameters on RFX-mod using a limited set of sensors
Real time measurement of plasma macroscopic parameters on RFX-mod using a limited set of sensors Open
A method to estimate the plasma boundary and global parameters such as βp+li/2 and the edge safety factor q95 is described. The method is based on poloidal flux extrapolation in the vacuum region between the plasma and the magnetic measure…
View article: Overview of the RFX-mod contribution to the international Fusion Science Program
Overview of the RFX-mod contribution to the international Fusion Science Program Open
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 …
View article: Turbulent electromagnetic filaments in actively modulated toroidal plasma edge
Turbulent electromagnetic filaments in actively modulated toroidal plasma edge Open
Filament or blob structures have been observed in all magnetic configurations with very similar features despite the difference in the magnetic geometry, and are believed to play an important role in convecting particles and energy towards…
View article: Density limit studies in the tokamak and the reversed-field pinch
Density limit studies in the tokamak and the reversed-field pinch Open
The ITER scenarios and the project of DEMO involve stable operation above the Greenwald density, which justifies efforts to understand and overcome the density limit, this last observed as a disruptive termination of tokamak discharges and…
View article: Beta limit and plasma response to n=1 perturbations in ASDEX Upgrade
Beta limit and plasma response to n=1 perturbations in ASDEX Upgrade Open
V. Igochine, P. Lauber, P. Piovesan, M. Schneller, E. Strumberger, W. Suttrop, D.Yadykin, P.Bettini, A. Bogomolov, T. Bolzonella, I.G.J. Classen, M. Dunne, A. Gude, M. Maraschek, L. Marrelli, R. McDermott, M. Reich, G. Tardini, the EUROfus…
View article: Real-time simulation of internal profiles in the presence of sawteeth using the RAPTOR code and applications to ASDEX Upgrade and RFX-mod
Real-time simulation of internal profiles in the presence of sawteeth using the RAPTOR code and applications to ASDEX Upgrade and RFX-mod Open
the RAPTOR code and applications to ASDEX Upgrade and RFX-mod C. Piron 1 , F. Felici 2 , D. Kim 3 , C.J. Rapson 4 , M. Reich 4 , O. Sauter 3 , W. Treutterer 4 , H. van den Brand 5 , and the ASDEX Upgrade Team, C. Finotti 1 , G. Manduchi 1 …