R. Zagórski
A5045838403- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- Nuclear reactor physics and engineering
- Phase Equilibria and Thermodynamics
- Material Dynamics and Properties
- Materials Engineering and Processing
- Additive Manufacturing and 3D Printing Technologies
- Dust and Plasma Wave Phenomena
- Nuclear Materials and Properties
- Aluminum Alloys Composites Properties
- nanoparticles nucleation surface interactions
- Solar and Space Plasma Dynamics
- Nuclear Physics and Applications
- Advanced Thermodynamics and Statistical Mechanics
- High-Energy Particle Collisions Research
- Granular flow and fluidized beds
- Theoretical and Computational Physics
- Laser-induced spectroscopy and plasma
- Catalysis and Oxidation Reactions
- Innovations in Concrete and Construction Materials
Institute of Plasma Physics and Laser Microfusion
2013-2025
National Centre for Nuclear Research
2020-2024
Max Planck Institute for Plasma Physics
2024
National Agency for New Technologies, Energy and Sustainable Economic Development
1994-2023
University of Padua
2021-2022
Royal Military Academy
2020
Culham Science Centre
2007-2019
Culham Centre for Fusion Energy
2007-2019
Ghent University
2014
Silesian University of Technology
2001-2013
With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossi et al 2014 Fusion Eng. Des. 89 907–12), the Tore Supra facility and team expertise (Dumont Plasma Phys. Control. 56 075020) is used to pave way towards ITER divertor procurement operation. It consists implementing a configuration installing ITER-like actively cooled tungsten monoblocks tokamak, taking full benefit of its unique long-pulse capability. user platform, open all partners. This paper describes physics basis WEST:...
Abstract The negative-ion based neutral beam injector for heating and current drive of the ITER plasma (ITER HNB) is under development, at present focusing on optimization full-scale source in SPIDER test stand. production H − or D ions ion low work function surfaces obtained by caesium evaporation. This paper describes conditioning procedure corresponding performances during first operation with caesium. Technical solutions to overcome limitations stand are described. influence parameters...
Plasma exhaust has been identified as a major challenge towards the realisation of magnetic confinement fusion. To mitigate risk that single null divertor (SND) with high radiation fraction in scrape-of-layer (SOL) adopted for ITER will not extrapolate to DEMO reactor, EUROfusion consortium is assessing potential benefits and engineering challenges alternative configurations. Alternative configurations could be readily design include X (XD), Super-X (SXD), Snowflake (SFD) double (DND). The...
FAST is a new machine proposed to support ITER experimental exploitation as well anticipate DEMO relevant physics and technology. aimed at studying, under burning plasma conditions, fast particle (FP) physics, operations wall interaction in an integrated way. has the capability approach all scenarios significantly closer than present day experiments using deuterium plasmas. The necessity of achieving performance with moderate cost led conceiving compact tokamak (R = 1.82m, 0.64m) high...
Heat and particle loads on the plasma facing components are among most challenging issues to be solved for a reactor design. Alternative magnetic configurations may enable tokamak operation with lower peak heat load than standard single null (SN) divertor. This papers reports creation control of one such alternatives: two-null nearby divertor configuration. An important element this study is that was produced large superconducting as an experimental advanced tokamak. A preliminary experiment...
Scenario modelling for the demonstration fusion reactor (DEMO) has been carried out using a variety of simulation codes.Two DEMO concepts have analysed: pulsed tokamak, characterised by rather conventional physics and technology assumptions (DEMO1) steady-state with moderately advanced (DEMO2).Sensitivity to impurity concentrations, radiation, heat transport models investigated.For DEMO2, impact current driven non-inductively Neutral Beams studied full MonteCarlo simulations fast ion...
An overview of the recent operations and main results cesium injection in Source for Production Ions Deuterium Extracted from Rf plasma (SPIDER) negative ion source are described this contribution. In experiments without injection, all SPIDER plants were tested to verify basic expectations on operational parameters (e.g., electron cooling effectiveness magnetic filter field) determine its region. For beam properties, it was shown that current density varies across vertical direction....
The reduction in divertor target power load due to radiation of sputtered and externally seeded impurities tokamak fusion reactors is investigated. approach based on integrated numerical modelling DEMO discharges using the COREDIV code, which self-consistently solves 1D radial transport equations plasma core region 2D multifluid SOL. Calculations are performed for inductive scenarios steady-state configurations with tungsten walls Ar or Ne seeding. For all considered significant can be...
Liquid lithium as a plasma-facing material was tested for the first time on high field medium size tokamak, FTU. A liquid Li reservoir supplies mesh of capillaries that is movable from shot to in scrape-off layer (SOL) plasma act secondary limiter. An almost complete lithization vacuum vessel walls obtained about three discharges. Plasmas cleaner than boronization and titanization, with lower radiation losses smaller impurity content are produced. The SOL electron temperature increases, ΔTe...
The ITER Scenario Modelling Working Group (ISM WG) is organized within the European Task Force on Integrated Tokamak (ITM-TF). main responsibility of WG to advance a pan-European approach integrated predictive modelling plasmas with emphasis urgent issues, identified during Design Review. Three major topics are discussed, which considered as and where has best possible expertize. These current profile control, density control impurity in (the last two involve both core SOL plasma). Different...
Abstract Results of numerical studies the plasma parameters in SPIDER sources are presented. Analysis done by means code FSFS2D which gives self-consistent 2D description source, including neutral gas flow, chemistry, RF coupling driver and transport through magnetic filter. Different particle species described separate continuity equations electron temperature is governed energy equation whereas potential Poisson equation.
The has been used for investigations the
SPIDER...
One of the most severe problems for fusion reactors is power load on plasma facing components. The challenge to develop operation scenarios, which combine sufficient energy confinement with benign heat loads radiative type-III ELMy H-mode seems a possible solution such an integrated ITER scenario. Nitrogen seeded H-modes standard inductive scenario and high beta stationary hybrid are investigated respect their transient steady-state fluxes divertor, properties, edge operational space, core...
FTU plasma discharges with an extremely high amount of Li injection have been performed using a poloidal liquid lithium limiter acting as the principal source in shadow main TZN toroidal limiter. Very peculiar these is formation ‘virtual’ that redistributes energy flux to tokamak vessel first wall by radiative processes and therefore decreases heat load onto Mo These experiments contribute investigation more complex scenario will possibly be faced project divertor additional power (or on targets).
Abstract In this paper we present integrated numerical modelling for the first time applied to ASDEX Upgrade nitrogen seeded discharges with full tungsten wall using COREDIV code. It has been found that code is able reproduce experimental data majority of considered shots. particular, satisfactory agreement global core parameters like P div , rad Z eff W mhd τE and Γ puff N found. However, shows significantly larger concentrations (factor 3‐10) than in experiment reason discrepancy not...
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...
The behaviour of the scrape-off plasma European tokamak DEMO (DEMOnstration economical feasibility fusion power) is analysed by means 2D edge code TECXY when either lithium or tin are used as liquid target materials in single null configuration. targets modelled a thin metal layer superimposed on tungsten substrate that faces plasma, while its bottom kept at fixed temperature. top temperature calculated from heat transport equation. evaporation rate so derived and sputtering give total...
The two-dimensional multifluid code TECXY has been used to model the biasing (with respect first wall) of toroidal belt limiter ALT-II on tokamak TEXTOR-94 and new pump being installed Tore Supra in framework CIEL project. It is well known that edge flow pattern can be influenced by poloidal electric drifts from imposing radial fields. modelling with introduces imprinted bias currents scrape-off layer (SOL) for case negative (limiter) biasing, potentials positive biasing. This allowed us...
Abstract In this paper we present results of numerical simulations nitrogen seeded JET discharges. particular, have benchmarked the code against type III ELMy pulses. addition to recovering main discharge parameters, interplay between and intrinsic carbon is also reproduced. Predictions for discharges with higher plasma current I p = 3.5 MA different input powers (14 < P aux 23 MW) demonstrate that it possible achieve high radiation fractions (> 80%) simultaneously reduce both...