A5090817830- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Gyrotron and Vacuum Electronics Research
- Ionosphere and magnetosphere dynamics
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Electromagnetic Launch and Propulsion Technology
- Nuclear Materials and Properties
- Nuclear Physics and Applications
- Electrostatic Discharge in Electronics
- Muon and positron interactions and applications
- Physics of Superconductivity and Magnetism
- High-Energy Particle Collisions Research
- Particle Detector Development and Performance
- Solar and Space Plasma Dynamics
- Neutrino Physics Research
- Particle physics theoretical and experimental studies
- Pulsed Power Technology Applications
- Model Reduction and Neural Networks
- Metal and Thin Film Mechanics
- Nuclear and radioactivity studies
- Innovative Microfluidic and Catalytic Techniques Innovation
Istituto Nazionale di Fisica Nucleare, Sezione di Padova
2024
Istituto Nazionale di Fisica Nucleare, Sezione di Milano Bicocca
2023
Fusion for Energy
2012-2021
Royal Military Academy
2020
's Heeren Loo
2018
Japan External Trade Organization
2015
Culham Science Centre
2008-2013
École Polytechnique Fédérale de Lausanne
2005-2013
Karlsruhe Institute of Technology
2011-2013
Fondazione IRCCS Istituto Nazionale dei Tumori
2012
The understanding and predictive capability of transport physics plasma confinement is reviewed from the perspective achieving reactor-scale burning plasmas in ITER tokamak, for both core edge regions. Very considerable progress has been made understanding, controlling predicting tokamak across a wide variety conditions regimes since publication Physics Basis (IPB) document (1999 Nucl. Fusion 39 2137–2664). Major areas considered here follow. (1) Substantial improvement content, reliability...
Analysis of Type I ELMs from ongoing experiments shows that ELM energy losses are correlated with the density and temperature pedestal plasma before crash. The loss normalized to is found correlate across collisionality (ν*ped), decreasing increasing ν*ped. Other parameters affect size, such as edge magnetic shear, etc, which influence volume affected by ELMs. particle influenced this weakly dependent on other parameters. In JET DIII-D, under some conditions, can be observed (`minimum'...
Progress in the definition of requirements for edge localized mode (ELM) control and application ELM methods both high fusion performance DT operation non-active low-current ITER is described. Evaluation power fluxes low plasma current H-modes shows that uncontrolled ELMs will not lead to damage tungsten (W) divertor target, unlike high-current which by expected. Despite lack at lower currents, found be required under these conditions prevent an excessive contamination W, could eventually...
The scaling of the energy confinement in H mode plasmas with different hydrogenic isotopes (hydrogen, deuterium, DT and tritium) is investigated JET. For ELM-free modes thermal time τth found to decrease weakly isotope mass (τth ∼M-0.25±0.22), whilst ELMy shows practically no dependence ∼M0.03±0.1). Detailed local transport analysis reveals that edge region increases strongly mass, whereas core decreases (τthcore ∝ M-0.16), approximate agreement theoretical models gyro-Bohm type (τgB ∼M-0.2).
The experimental characteristics of divertor detachment in the JET tokamak with Mark I pumped are presented for ohmic, L mode and ELMy H experiments main emphasis on discharges deuterium fuelling only. range over which is observed various regimes, as well influence configuration, direction toroidal field, target material active pumping detachment, will be described. characteristics, such existence a considerable electron pressure drop along field lines scrape-off layer (SOL), compatibility...
As part of the ITER Design Review and in response to issues identified by Science Technology Advisory Committee, physics requirements were reviewed as appropriate updated. The focus this paper will be on recent work affecting design with special emphasis topics near-term procurement arrangements. This describe results on: sensitivity studies, poloidal field coil requirements, vertical stability, effect toroidal ripple thermal confinement, material choice heat load for plasma-facing...
The pressure at the top of edge transport barrier (or ‘pedestal height’) strongly impacts fusion performance, while large localized modes (ELMs), driven by free energy in pedestal region, can constrain material lifetimes. Accurately predicting height and ELM behavior ITER is an essential element prediction optimization performance. Investigation intermediate wavelength MHD ‘peeling–ballooning’ modes) has led to improved understanding important constraints on mechanism for ELMs. combination...
Operating ITER in the reference inductive scenario at design values of Ip = 15 MA and QDT 10 requires achievement good H-mode confinement that relies on presence an edge transport barrier whose pedestal pressure height is key to plasma performance. Strong gradients occur such conditions can drive magnetohydrodynamic instabilities resulting localized modes (ELMs), which produce a rapid energy loss from region facing components (PFC). Without appropriate control, heat loads PFCs during ELMs...
Results are presented from a series of dedicated experiments carried out on JET in tritium, DT, deuterium and hydrogen plasmas to determine the dependence H mode power threshold plasma isotopic mass. The Pthr ∝ Aeff-1 scaling is established over whole range. This result makes it possible for fusion reactor with 50:50 DT mixture access regime about 20% less than that needed DD mixture. first systematic measurements necessary transition type I ELM regime, which occurs after mode, also...
Recent experiments on the Type I ELMy H-mode regime performed at JET with improved diagnostics have expanded range of parameters for study ELM energy and particle losses. Deviations from standard behaviour such losses in some areas operating space revealed that are correlated (density temperature) pedestal plasma before crash, while other global characteristics (such as frequency) a consequence ELM-driven flux in-between confinement. The relative loss (to energy) is found to correlate well...
Results are presented of experiments carried out in JET with the Mark II divertor to study ELMy H modes at high density. In these effective ion mass plasma (pure hydrogen, deuterium and tritium), input power, current edge triangularity were varied. The variation density was achieved by gas fuelling. focus is on two main issues: global energy confinement scaling mode pedestal. It found that dependence ITER97-P(y) not confirmed experiment when limit approached. For regime a independent...
New experimental results on transient loads during ELMs and disruptions in present divertor tokamaks are described used to carry out a extrapolation ITER reference conditions draw consequences for its operation. In particular, the achievement of low energy/convective type I edge localized modes (ELMs) ITER-like plasma seems only way obtain which may be compatible with an acceptable erosion lifetime facing components (PFCs) ITER. Power disruptions, contrary, seem lead most cases because...
We present the results of experiments in JET to study effect plasma shape on high density ELMy H-modes, with geometry magnetic boundary similar that envisaged for standard Q = 10 operation ITER. The described are single lower null plasmas, q profile, neutral beam heating and gas fuelling, average triangularity δ calculated at separatrix ~0.45-0.5 elongation κ~1.75. In agreement previous obtained other divertor Tokamaks, thermal energy confinement time maximum achievable steady state a given...
The ITER electron cyclotron (EC) upper port antenna (or launcher) is nearing completion of the detailed design stage and final build-to-print will soon start. main objective this launcher to drive current locally stabilize neoclassical tearing modes (NTMs) (depositing ECCD inside island that forms on either q = 3/2 or 2 rational magnetic flux surfaces) control sawtooth instability (deposit near 1 surface). should be capable steering focused beam deposition location resonant surface over...
Views Icon Article contents Figures & tables Video Audio Supplementary Data Peer Review Share Twitter Facebook Reddit LinkedIn Tools Reprints and Permissions Cite Search Site Citation M. N. A. Beurskens, T. H. Osborne, P. Schneider, E. Wolfrum, L. Frassinetti, R. Groebner, Lomas, I. Nunes, S. Saarelma, Scannell, B. Snyder, D. Zarzoso, Balboa, Bray, Brix, J. Flanagan, C. Giroud, Giovannozzi, Kempenaars, Loarte, de la Luna, G. Maddison, F. Maggi, McDonald, Pasqualotto, Saibene, Sartori, Emilia...
In-vessel, non-axisymmetric, control coils have proven to be an important option for mitigating and suppressing edge-localized modes (ELMs) in high performance operating regimes on a growing number of tokamaks. Additionally, in-vessel non-axisymmetric ELM coil is being considered the ITER baseline design. In preparing initial operation this set, comprehensive study was carried out characterize linear superposition 3D vacuum magnetic field, produced by coil, series equilibria representing...
A 24 MW Electron Cyclotron (EC) system operating at 170 GHz and 3600 s pulse length is to be installed on ITER. The EC plant shall deliver 20 of this power the plasma for Heating Current Drive (H&CD) applications. designed initiation, central heating, current drive, profile tailoring, Magneto-hydrodynamic control (in particular, sawteeth Neo-classical Tearing Mode) in flat-top phase plasma. preliminary design review was performed 2012, which identified a need extended application...
This paper presents the experimental characterization of pedestal parameters, edge localized mode (ELM) energy, and particle losses from main plasma corresponding ELM energy fluxes on facing components for a series dedicated experiments in Joint European Torus (JET). From these experiments, it is demonstrated that simple hypothesis relating peeling-ballooning linear instability to not valid. Contrary previous observations at lower triangularities, small low collisionality have been obtained...
Several small/no ELM regimes such as EDA, grassy ELM, HRS, QH-mode, type II and V ELMs with good confinement properties have been obtained in Alcator C-Mod, ASDEX-Upgrade, DIII-D, JET, JFT-2M, JT-60U NSTX. All these show considerable reduction of instantaneous heat load onto divertor target plates contrast to conventional I energy losses are evaluated less than 5% the pedestal stored energy. These summarized widely categorized by their conditions terms operational space non-dimensional...
The main objective of this paper is investigation methods for reduction divertor heat loads in order to increase the lifetime tiles future fusion reactors.Special emphasis given studies transient due edge localized modes (ELMs).Two are compared: argon seeded type-I ELMy H-modes and nitrogen type-III H-modes.In both scenarios, impurity seeding leads a pedestal energy hence released by ELM.This consequentially reduces power load targets.At high radiative fractions H-modes, part that ELM (small...
A number of possible designs external and in-vessel coils generating resonant magnetic perturbations (RMPs) for Type I edge localized modes (ELMs) control in ITER are analysed the reference scenarios (H-mode, Hybrid Steady-State) taking into account physical, technical spatial constraints. The level stochasticity (Chirikov parameter ∼1 at ψ 1/2 ∼ 0.95) generated by I-coils DIII-D experiments on ELMs suppression was taken as a reference. Designs with toroidal symmetry n = 3 were considered to...