A5019951298- 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
- Gas Dynamics and Kinetic Theory
- Rocket and propulsion systems research
- Nuclear reactor physics and engineering
- Computational Fluid Dynamics and Aerodynamics
- Solar and Space Plasma Dynamics
- High-pressure geophysics and materials
- Laser-induced spectroscopy and plasma
- Atomic and Molecular Physics
- Nuclear Materials and Properties
Max Planck Institute for Plasma Physics
2017-2025
Institut de Recherche sur la Fusion par Confinement Magnétique
2024
CEA Cadarache
2024
Culham Science Centre
2024
Culham Centre for Fusion Energy
2024
Max Planck Society
2017-2021
Aix-Marseille Université
2020
Centre National de la Recherche Scientifique
2020
Polytechnic University of Turin
2017
Fusion whole device modeling simulations require comprehensive models that are simultaneously physically accurate, fast, robust, and predictive. In this paper we describe the development of two neural-network (NN) based as a means to perform snon-linear multivariate regression theory-based for core turbulent transport fluxes, pedestal structure. Specifically, find NN-based approach can be used consistently reproduce results TGLF EPED1 over broad range plasma regimes, with computational...
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 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>...
Over previous campaigns, an intense experimental program on advanced tokamak (AT) scenarios, has been carried out at the ASDEX Upgrade with full-tungsten wall. These discharges have executed shortly after boronization of first wall to reduce density and impurity influx. The confinement level such AT was found vary considerably, even when similar, if not identical, engineering parameters were out. This work investigates causes variations. Among all plasma quantities analyzed, quality...
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 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...
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 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...
An accurate description of turbulence up to the transport time scale is essential for predicting core plasma profiles and enabling reliable calculations designing advanced scenarios future devices. Here, we exploit gap separation between scales couple global gyrokinetic code GENE transport-solver Tango, including kinetic electrons, collisions, realistic geometries, toroidal rotation electromagnetic effects first time. This approach overcomes codes' limitations enables high-fidelity profile...
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"...
Abstract The successful validation of theory-based models transport, magnetohydrodynamic stability, heating and current drive, with tokamak measurements over the last 20 years, has laid foundation for a new era where these can be routinely used in ‘predict first’ approach to design predict outcomes experiments on tokamaks today. capability plasma confinement core profiles quantified uncertainty, based multi-machine, international, database experience, will provide confidence that proposed...
Abstract A model for the pedestal density prediction based on neutral penetration combined with transport is presented. The tested against a database of JET-ILW Type I ELMy H-modes showing good agreement over wide range parameters both in standalone modelling (using experimental temperature profile) and full Europed that predicts pedestals simultaneously. further ASDEX Upgrade MAST-U are found to agree same as JET-ILW. experiment where isotope main ion varied D/T scan at constant gas rate...
Plasma density is one of the key quantities that need to be controlled in real-time as it scales directly with fusion power and, if left uncontrolled, limits can reached leading a disruption. On ASDEX Upgrade (AUG), measurements are line-integrated density, measured by interferometers, and average derived from bremsstrahlung spectroscopy. For control, these used reconstruct radial profile using an extended Kalman filter (EKF). However, discharges where ion cyclotron resonance heating (ICRH)...
Abstract Self-healing liquid metal divertors (LMDs) based on the Capillary Porous Structure (CPS) concept are currently being considered among possible solutions to power exhaust problem in future fusion reactors. Indeed, passive replenishment of plasma-facing surface by capillary forces and self-shielding target via vapor emission can potentially improve divertor lifetime its resilience transient loads. On other hand, LMD erosion be significant due evaporation thermal sputtering, top...
Abstract The common way to predict energy confinement in future devices such as ITER is use scaling laws, based on parameters regression of large cross-machine databases. However, this approach limited: the variables are not purely engineering parameters, physics quantities plasma density n e also input; power regressions fail capture important regime transitions; profile effects T i / or reverse magnetic shear retained. As a consequence, scatter large, but even some dependences known be...
Abstract A new approach to infer the momentum transport in tokamak core plasmas via perturbation experiments is presented. For first time, analysis self-consistently includes all components and their time dependencies, which are essential separate fluxes closely match experiment. The quantitative agreement between experimentally inferred coefficients gyrokinetic predictions provides an unprecedented validation. This work shows that methodology can now be utilized on route physics-based...
Abstract In present-day fusion devices, central wave heating is crucial to avoid core tungsten (W) accumulation. this work, we present an integrated modelling framework that reproduces the reduction of W peaking in ASDEX Upgrade experiments when multiple transport channels are self-consistently evolved, emphasizing effects on turbulent and neoclassical transport. Predictions for ITER 15 MA baseline then provided. We show a reactor different regime as compared tokamaks. The challenges...
Abstract We use an integrated modeling workflow with the transport code ASTRA coupled quasi-linear model TGLF-SAT2, neoclassical NCLASS, FACIT for impurity and IMEP routines pedestal calculations, in order to predict evolution of plasma profiles Divertor Tokamak Test facility (DTT) tokamak main scenarios. The simulations cover whole confined radius, up separatrix, time including early phase limiter configuration, current ramp-up L-mode divertor L–H transition part stationary H-mode phase....
Abstract Combining the analysis of multiple diagnostics and well-chosen prior information in framework Bayesian probability theory, Integrated Data Analysis code (IDA Fischer et al 2010 Fusion Sci. Technol. 58 675–84) can provide density temperature radial profiles fusion plasmas. These IDA-fitted measurements are then used for further analysis, such as discharge simulations other experimental data analysis. Since IDA considers measurement data, which is frequently fragmentary, with...
Abstract In this work, a very fast integrated transport model involving every region that interacts directly with the plasma of tokamak, has been developed. The confined is modeled in 1.5D, while scrape-off layer 0D structure. For core region, physics-based analytical regression based on set simulations TGLF [Staebler 2005 Phys. Plasmas 12 102508] produced. H-mode regime, an average edge-localized-modes applied pedestal region. two-point for electron temperature (exhaust) and particle...
Electron cyclotron resonance heating (ECRH) can drive large current densities through electron (ECCD). ECCD is expected to be crucial for high-performance plasmas in future fusion reactors like ITER and DEMO, making the efficiency of a critical design parameter reactors. In present-day devices, good agreement between measured predicted has been found. However, ensure reliability machines, direct validation momentum distribution function needed.