N. Bonanomi
A5033471033- Magnetic confinement fusion research
- Fusion materials and technologies
- Ionosphere and magnetosphere dynamics
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Nuclear reactor physics and engineering
- Solar and Space Plasma Dynamics
- Fluid Dynamics and Turbulent Flows
- High-pressure geophysics and materials
- Nuclear Materials and Properties
- High-Energy Particle Collisions Research
- Computational Fluid Dynamics and Aerodynamics
- Semiconductor materials and devices
- Fault Detection and Control Systems
- Atomic and Subatomic Physics Research
- Anomaly Detection Techniques and Applications
- Silicon and Solar Cell Technologies
- Meteorological Phenomena and Simulations
- GNSS positioning and interference
- Electrostatic Discharge in Electronics
Max Planck Institute for Plasma Physics
2018-2025
University of Rome Tor Vergata
2024
Culham Science Centre
2017-2024
Culham Centre for Fusion Energy
2017-2024
Max Planck Society
2018-2021
National Centre for Nuclear Research
2021
Royal Military Academy
2020
University of Milano-Bicocca
2017-2019
Institute of Plasma Physics
2017-2018
Abstract In 2021 JET exploited its unique capabilities to operate with T and D–T fuel an ITER-like Be/W wall (JET-ILW). This second major campaign (DTE2), after DTE1 in 1997, represented the culmination of a series enhancements—new fusion diagnostics, new injection capabilities, refurbishment plant, increased auxiliary heating, in-vessel calibration 14 MeV neutron yield monitors—as well as significant advances plasma theory modelling community. DTE2 was complemented by sequence isotope...
Abstract The most efficient and promising operational regime for the International Thermonuclear Experimental Reactor tokamak is high-confinement mode. In this regime, however, periodic relaxations of plasma edge can occur. These edge-localized modes pose a threat to integrity fusion device. Here we reveal strong impact energetic ions on spatio-temporal structure in tokamaks using nonlinear hybrid kinetic–magnetohydrodynamic simulations. A resonant interaction between fast at electromagnetic...
Abstract An overview is presented of the progress since 2021 in construction and scientific programme preparation Divertor Tokamak Test (DTT) facility. Licensing for building has been granted at end 2021. Cat. A radiologic source also 2022. The toroidal field magnet system progressing. prototype 170 GHz gyrotron produced it now under test on FALCON design vacuum vessel, poloidal coils civil infrastructures completed. shape first DTT divertor agreed with EUROfusion to different plasma exhaust...
Quasilinear turbulent transport models are a successful tool for prediction of core tokamak plasma profiles in many regimes. Their success hinges on the reproduction local nonlinear gyrokinetic fluxes. We focus significant progress quasilinear model QuaLiKiz [C. Bourdelle et al. 2016 Plasma Phys. Control. Fusion 58 014036], which employs an approximated solution mode structures to significantly speed up computation time compared full linear solvers. Optimization dispersion relation algorithm...
The design of future fusion reactors and their operational scenarios requires an accurate prediction the plasma confinement. We have developed a new model that integrates different elements describing main physics phenomena which determine In particular, we are coupling pedestal transport model, based on empirical observations, to ASTRA code, which, together with TGLF turbulent NCLASS neoclassical allows us describe from magnetic axis separatrix. also coupled simple scrape-off layer ASTRA,...
Abstract The findings of an investigation into the properties three dimensional (3D) saturated fluctuation intensity electric potential in gyrokinetic turbulence simulations is presented. Scans flux surface elongation and Shafranov shift are used to isolate tokamak geometric dependencies. required order compute exact fluxes by a quasilinear method determined using linear eigenmodes computed with code. A model this non-linear constructed eigenmode geometry shape functions obtained from 3D...
Abstract As part the DTE2 campaign in JET tokamak, we conducted a parameter scan T and D-T complementing existing pulses H D. For different main ion masses, type-I ELMy H-modes at fixed plasma current magnetic field can have pedestal pressure varying by factor of 4 total changing from <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:msub> <mml:mi>β</mml:mi> <mml:mrow> <mml:mi mathvariant="normal">N</mml:mi> </mml:mrow> </mml:msub> <mml:mo>=</mml:mo>...
Abstract The research program of the TCV tokamak ranges from conventional to advanced-tokamak scenarios and alternative divertor configurations, exploratory plasmas driven by theoretical insight, exploiting device’s unique shaping capabilities. Disruption avoidance real-time locked mode prevention or unlocking with electron-cyclotron resonance heating (ECRH) was thoroughly documented, using magnetic radiation triggers. Runaway generation high- Z noble-gas injection runaway dissipation...
Abstract The nature of the turbulent transport in edge region ASDEX Upgrade and JET-ILW deuterium (D) hydrogen (H) L-mode plasmas is studied using local gyro-kinetic simulations. For both devices turbulence found to be dominated by an electron drift-wave destabilized high collisionality plasma strongly related kinetic dynamics. isotope ion mass have important impact on turbulence. In linear simulations, wider eigenfunctions electrostatic potential with a lower translate threshold normalized...
Abstract The properties of L-mode confinement have been investigated with a set dedicated experiments in ASDEX Upgrade and related modelling activity the transport code ASTRA quasi-linear turbulent model TGLF–SAT2, boundary conditions at separatrix. values by two-point for electron temperature, ion temperature proportional to constant factor, density fraction volume averaged density. influx neutrals has through feedback procedure which ensures that simulation same particle content as...
Abstract Experiments on ASDEX Upgrade (AUG) in 2021 and 2022 have addressed a number of critical issues for ITER EU DEMO. A major objective the AUG programme is to shed light underlying physics confinement, stability, plasma exhaust order allow reliable extrapolation results obtained present day machines these reactor-grade devices. Concerning pedestal physics, mitigation edge localised modes (ELMs) using resonant magnetic perturbations (RMPs) was found be consistent with reduction linear...
The Alfvén instability nonlinearly excited the energetic-particle-driven geodesic acoustic mode on ASDEX-Upgrade tokamak, as demonstrated experimentally. mechanism of excitation and nonlinear evolution is not yet fully understood. In present work, a first-principles simulation using MEGA code investigated properties in both linear growth saturated phases. Here we show that successfully reproduced coexistence these two modes, agreed with experimental results well. Conclusive evidence showed...
Abstract This paper presents a study on the dependence of ion temperature stiffness plasma main isotope mass in JET ITER-like wall and C discharges. To this aim, database H, D T shots is analyzed, including new dedicated shots, comparing experiments with lower higher power injected by NBI system. In order to characterize turbulence mass, three these discharges (two one D) same external heating scheme are studied detail interpreted gyrokinetic linear nonlinear simulations. The analysis...
Abstract On the basis of several recent breakthroughs in fusion research, many activities have been launched around world to develop power plants on fastest possible time scale. In this context, high-fidelity simulations plasma behavior large supercomputers provide one main pathways accelerating progress by guiding crucial design decisions. When it comes determining energy confinement a magnetic device, which is key quantity interest, gyrokinetic turbulence are considered approach choice –...
Abstract Previous studies with first-principle-based integrated modelling suggested that electron temperature gradient (ETG) turbulence may lead to an anti-gyroBohm isotope scaling in JET high-performance hybrid H-mode scenarios. A dedicated comparison study against higher-fidelity invalidates this claim. Ion-scale magnetic field perturbations included, can match the power balance fluxes within error margins. Multiscale gyrokinetic simulations from two distinct codes produce no significant...
Abstract The dependence of the confinement a tokamak plasma in L-mode on magnetic field is explored with set dedicated experiments ASDEX Upgrade and theory-based full-radius modelling approach, based ASTRA transport code TGLF-SAT2 model only using engineering parameters input, like those adopted scaling laws for time. experimental results confirm weak global field, consistent plasmas agreement predictions. approach then extended to numerically investigate current size. at constant size shown...
Fusion performance in tokamaks depends on the core and edge regions as well their nonlinear feedbacks.The achievable degree of confinement under constraints power handling presence a metallic wall is still an open question.Therefore, any improvement temperature density peaking crucial for achieving target performance.This has motivated further progress understanding turbulent transport mechanisms, to help scenario development present devices improve predictive tools ITER operations.In last...
The isotope dependence of plasma transport will have a significant impact on the performance future D-T experiments in JET and ITER eventually fusion gain economics reactors. In preparation for operation JET, dedicated comprehensive analyses were performed H, D H-D mixed plasmas. analysis data has demonstrated an unexpectedly strong favourable global confinement energy, momentum particles ELMy H-mode plasmas atomic mass main ion species, energy time scaling as ${\tau _E}\sim {A^{0.5}}$...
Abstract An overview of recent results obtained at the tokamak ASDEX Upgrade (AUG) is given. A work flow for predictive profile modelling AUG discharges was established which able to reproduce experimental H-mode plasma profiles based on engineering parameters only. In center, theoretical predictions current redistribution by a dynamo effect were confirmed experimentally. For core transport, stabilizing fast ion distributions turbulent transport shown be important explain isotope and...
Abstract In this work we present the extensive validation of a refined version integrated model based on engineering parameters (IMEP) introduced in reference (Luda et al 2020 Nucl . Fusion 60 036023). The modeling workflow is now fully automated, computationally faster thanks to reduced radial resolution TGLF calculation, and it includes toroidal rotation, which was still taken from experimental measurements our previous work. updated maintains same accuracy as its when tested cases...
Abstract This paper presents an overview of results from L–H transition experiments that were performed at ASDEX Upgrade (AUG) with the aim identifying underlying mechanisms leading to H-mode confinement. With a broad variety and new diagnostic techniques, as well modeling efforts, AUG has contributed substantially improving our understanding over past years. In this review, important roles ion heat channel edge radial electric field ( E r ) in physics are brought into context known...
Abstract This paper is dealing with the physics basis used for design of Divertor Tokamak Test facility (DTT), under construction in Frascati (DTT 2019 DTT interim report (2019)) Italy, and description main target plasma scenarios device. The goal will be study power exhaust, intended as a fully integrated core-edge problem, eventually to propose an optimized divertor European DEMO plant. approach described their features are reported, by using simulations performed state-of-the-art codes...
Experimental observations in JET tokamak plasmas and gyrokinetic simulations point to an important role, for electron heat transport, of electron-scale instabilities their interaction with ion-scale instabilities. Since these effects are maximized strong heating modes close marginal stability, findings high relevance ITER plasmas, featuring both conditions. Gyrokinetic quasi-linear transport models accounting multi-scale assessed against experimental results.
Abstract Kinetic profile predictions of ITER PFPO-1 plasmas require high accuracy in the central electron temperatures to be applied calculation third harmonic cyclotron absorption. Correctly predicting transition from L-mode H-mode further requires precise estimates ion heat flux periphery plasma. Recent versions quasi-linear transport models TGLF and QuaLiKiz were tested against an extensive set experimental results ASDEX Upgrade (AUG) JET-ILW, where focus was put on AUG heated by ECRH....
Abstract The recently developed integrated model based on engineering parameters (IMEP) (Luda et al 2020 Nucl. Fusion 61 126048; Luda 2021 60 036023), so far validated ASDEX Upgrade, has been tested a database of 3 Alcator C-Mod and 55 JET-ILW ELMy (type I) H-mode stationary phases. empirical pedestal transport included in IMEP, consisting now imposing fixed value <?CDATA $R \lt\nabla T_\mathrm{e}\gt/T_\mathrm{e,top} = - 82.5$?> <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"...