Paolo Bettini
A5044606197- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Electromagnetic Simulation and Numerical Methods
- Fusion materials and technologies
- Electromagnetic Scattering and Analysis
- Plasma Diagnostics and Applications
- Laser-Plasma Interactions and Diagnostics
- Vacuum and Plasma Arcs
- Magnetic Field Sensors Techniques
- High voltage insulation and dielectric phenomena
- Electrostatic Discharge in Electronics
- Non-Destructive Testing Techniques
- Advanced Numerical Methods in Computational Mathematics
- Numerical methods in engineering
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Lightning and Electromagnetic Phenomena
- Numerical methods for differential equations
- Geophysical and Geoelectrical Methods
- Particle Accelerators and Free-Electron Lasers
- Model Reduction and Neural Networks
- Geophysical Methods and Applications
- Electromagnetic Compatibility and Measurements
National Agency for New Technologies, Energy and Sustainable Economic Development
2013-2024
University of Padua
2015-2024
University of Udine
2003-2024
University of Florence
2020
University of Brescia
2020
University of Milan
2013
The ITER project requires additional heating by two neutral beam injectors, each accelerating to 1 MV a 40 A of negative deuterium ions, deliver the plasma power about 17 MW for one hour. As these requirements have never been experimentally met, it was recognized as necessary setup test facility, PRIMA (Padova Research on Megavolt Accelerator), in Italy, including full-size ion source, SPIDER, and prototype whole injector, MITICA, aiming develop injectors be installed ITER. This realization...
The development of technologies for the additive manufacturing, in particular metallic materials, is offering possibility producing parts with complex geometries. This opens up to using topological optimization methods design electromagnetic devices. Hence, a wide variety approaches, originally developed solid mechanics, have recently become attractive also field electromagnetics. general distinction between gradient-based and gradient-free drives structure paper, latter becoming...
The spacers for the gas insulated transmission line ITER neutral beam injector will be designed to withstand operating voltage of 1 MV dc. Electric charging processes spacer surface are then expected play an important role in final electric field distribution. Aim paper is investigate effects different conductivity properties SF6-Spacer insulating structures on charge set-up, and identify a procedure minimize this charge. Based most updated literature, presents discusses results two newly...
Abstract In magnetic fusion devices, error field (EF) sources, spurious perturbations, need to be identified and corrected for safe stable (disruption-free) tokamak operation. Within Work Package Tokamak Exploitation RT04, a series of studies have been carried out test the portability novel non-disruptive method, designed tested in DIII-D (Paz-Soldan et al 2022 Nucl. Fusion 62 126007), perform an assessment model-based EF control strategies towards their applicability ITER. this paper,...
RFX-mod is a Reversed Field Pinch device that allowed performing experiments in regimes with plasma current up to 2 MA, thanks its MHD active control system. Experiments have shown improved performances are obtained when the resonant part of m = 1 spectrum one dominant tearing mode much higher than other secondary ones (quasi single helicity states). Tearing modes play crucial role determining energy and particle transport. Based on present understanding interplay between passive conductive...
Abstract Niobium (Nb) is a transition metal commonly used as an alloying element for increasing strength, toughness, corrosion resistance, and other properties of steel superalloys. Pure Nb, however, very interesting its excellent superconductivity. This makes it suitable producing superconducting magnets devices particle acceleration systems physics research (e.g., resonant cavities). In this work, the production Nb by Laser-Based Powder Bed Fusion (PBF-LB/M, also known Laser or LPBF)...
Within the EUROfusion MST1 work package, a series of experiments has been conducted on AUG and TCV devices to disentangle role plasma fueling shape for onset small ELM regimes. On both devices, regimes with high confinement are achieved if only two conditions fulfilled at same time. Firstly, density separatrix must be large enough (), leading pressure profile flattening separatrix, which stabilizes type-I ELMs. Secondly, magnetic configuration close double null (DN), reduction shear in...
Integrating the plasma core performance with an edge and scrape-off layer (SOL) that leads to tolerable heat particle loads on wall is a major challenge. The new European medium size tokamak task force (EU-MST) coordinates research ASDEX Upgrade (AUG), MAST TCV. This multi-machine approach within EU-MST, covering wide parameter range, instrumental progress in field, as ITER DEMO core/pedestal SOL parameters are not achievable simultaneously present day devices. A two prong adopted. On one...
Low-rank approximation techniques are useful approaches to reduce the computational effort required by integral equations methods. Here, two different libraries based on hierarchical-matrices and hierarchically semi-separable matrices applied partial element equivalent circuit method for study of high-frequency electromagnetic problems. The academic case a dielectric sphere complex device used in thermonuclear fusion science considered order compare performances libraries.
RFX-mod is a reversed field pinch (RFP) experiment equipped with system that actively controls the magnetic boundary. In this paper we describe results of new control algorithm, clean mode (CMC), in which aliasing sideband harmonics generated by discrete saddle coils corrected real time. CMC operation leads to smoother (i.e. more axisymmetric) Tearing modes rotate (up 100 Hz) and partially unlock. Plasma–wall interaction diminishes due decrease non-axisymmetric shift plasma column. With...
With the exploration of MA plasma current regime in up to 0.5 s long discharges, RFX-mod has opened new and very promising perspectives for reversed field pinch (RFP) magnetic configuration, made significant progress understanding improving confinement controlling stability. A big leap with respect previous knowledge expectations on RFP physics performance been by since last 2006 IAEA Fusion Energy Conference. self-organized helical equilibrium experimentally achieved (the Single Helical...
Optimization of machine operation, including plasma position control, density control and especially feedback on multiple magnetohydrodynamic modes, has led RFX-mod to operate reliably at 1.5 MA, the highest current ever achieved a reversed field pinch (RFP). At high low magnetic topology spontaneously self-organizes in an Ohmical helical symmetry, with new axis helically twisting around geometrical torus. The separatrix island disappears leaving wide symmetric thermal structure large...
This paper reports the main recent results of RFX-mod fusion science activity.The device is characterized by a unique flexibility in terms accessible magnetic configurations.Axisymmetric and helically shaped Reversed-field pinch equilibria have been studied, along with tokamak plasmas wide range q(a) regimes (spanning from 4 down to 1.2 values).The full configurations between two, so-called ultra low-q ones, has explored, aim studying specific physical issues common all equilibria, such as,...
We present an effective technique to solve eddy current problems in thin conductors of arbitrary topology by a boundary element method based on stream function. By considering mesh the conductor, which we assume be surface (i.e., orientable combinatorial two-manifold embedded R <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sup> , aim this paper is introduce novel render function single valued when conductor not topologically trivial. In...
The modified RFX is a very flexible device used for variety of control schemes MHD instabilities and advanced reverse field pinch scenarios. Relative to the previous machine, RFX-mod has thin Cu shell with vertical penetration time τS, lowered from 450 50 ms shell/plasma proximity b/a = 1.24–1.1. Toroidal equilibrium feedback-controlled new power supplies provide better B control. Newly designed graphite tiles protect vessel localized deposition. A mesh 192 external saddle coils, supervised...
This paper summarizes the main achievements of RFX fusion science program in period between 2008 and 2010 IAEA Fusion Energy Conferences. RFX-mod is largest reversed field pinch world, equipped with a system 192 coils for active control MHD stability. The discovery understanding helical states electron internal transport barriers core temperature >1.5 keV significantly advances perspectives configuration. Optimized experiments plasma current up to 1.8 MA have been realized, confirming...
This paper presents a volume integral formulation to solve eddy current problems on general polyhedral meshes. The required topological preprocessing is efficiently addressed in linear worst case complexity by using the idea of lazy cohomology generators.
A novel partial element equivalent circuit (PEEC) formulation for solving full-Maxwell's equations, with piecewise homogeneous and linear conductive, dielectric, magnetic media, is presented. It based on the cell method which by using integral variables as problem unknowns naturally suited developing circuit-like approaches such PEEC. Volume meshing allows complex 3-D geometries, electric materials, to be discretized. Electromagnetic couplings in air domain are modeled equations.
The JT-60SA tokamak, being built under the Broader Approach agreement jointly by Europe and Japan, is due to start operation in 2020 expected give substantial contributions both ITER DEMO scenario optimisation. A broad set of preparation activities for an efficient experiments on carried out, involving elaboration Research Plan, advanced modelling various domains, feasibility conception studies diagnostics other sub-systems connection with priorities scientific programme, development...
Abstract Tokamak plasmas can amplify very small resonant components of error fields (EFs) when operating close to the ideal magneto-hydrodynamic (MHD) limits. Such EFs are well diagnosed in ASDEX Upgrade tokamak (Igochine V et al 2017 Nucl. Fusion 57 116027, Maraschek M 40th EPS Conf. on Plasma Physics 2013 P4.127), which allows model EF as correction required for optimal compensation. Experiments show that considering plasma effect, it is foreseen ITER, necessary even case EF. improves...