E. Kowalska-Strzęciwilk
A5015090299- Magnetic confinement fusion research
- Fusion materials and technologies
- Particle Detector Development and Performance
- Nuclear Physics and Applications
- Radiation Detection and Scintillator Technologies
- Laser-Plasma Interactions and Diagnostics
- Superconducting Materials and Applications
- Quasicrystal Structures and Properties
- Aluminum Alloy Microstructure Properties
- Plasma Diagnostics and Applications
- Nuclear reactor physics and engineering
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- X-ray Spectroscopy and Fluorescence Analysis
- Nuclear Materials and Properties
- Aluminum Alloys Composites Properties
- Intermetallics and Advanced Alloy Properties
- Atomic and Subatomic Physics Research
- Magnetic Field Sensors Techniques
- Ion-surface interactions and analysis
- Electron and X-Ray Spectroscopy Techniques
- Advanced materials and composites
- Metal and Thin Film Mechanics
- Microstructure and mechanical properties
- Diamond and Carbon-based Materials Research
Institute of Plasma Physics and Laser Microfusion
2015-2024
Royal Military Academy
2020
CEA Cadarache
2017
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2017
Czech Academy of Sciences, Institute of Plasma Physics
2015
Forschungszentrum Jülich
2003-2007
University of Silesia in Katowice
2005-2007
Institute of Physics
2005
Abstract The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with ITER-like Be/W wall. development started pure Deuterium refinement of current, and toroidal magnetic field choices succeeded solving heat load challenges arising 37 MW injected power ITER like environment, keeping radiation edge core controlled, avoiding MHD instabilities reaching high neutron rates. have re-run Tritium...
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>...
To study the impact of strong impurity radiation on energy confinement and discharge stability at JET-ILW, dedicated high-density, highly heated experiments with neon seeding have been performed. In these an increase in core especially pedestal region plus a characteristic X-point radiator inside confined observed. The increased separatrix had no confinement. Only highest puff rates heating powers () weak H-mode without back-transitions to L-mode (M-mode) could be achieved, while lower or...
Abstract We present an overview of results from a series L–H transition experiments undertaken at JET since the installation ITER-like-wall (JET-ILW), with beryllium wall tiles and tungsten divertor. Tritium, helium deuterium plasmas have been investigated. Initial in tritium show ohmic transitions low density power threshold for ( P LH ) is lower than ones densities, while we still lack contrasted data to provide scaling high densities. In there notable shift which minimum <?CDATA...
The fusion-born alpha particle heating in magnetically confined fusion machines is a high priority subject for studies. self-heating of thermonuclear plasma by particles was observed recent deuterium-tritium (D-T) experiments on the joint European torus. This observation possible conducting so-called "afterglow" where transient yield achieved with neutral beam injection as only external source, and then termination at peak performance. allowed first direct evidence electron plasmas alphas to...
Abstract The recent deuterium–tritium campaign in JET-ILW (DTE2) has provided a unique opportunity to study the isotope dependence of L-H power threshold an ITER-like wall environment (Be and W divertor). Here we present results from dedicated transition experiments at JET-ILW, documenting tritium plasmas, comparing them with matching deuterium hydrogen datasets. From earlier it is known that as plasma isotopic composition changes deuterium, through varying deuterium/hydrogen concentrations,...
Abstract The dimensionless isotope mass scaling experiment between pure Deuterium and Tritium plasmas with matched <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:msup> <mml:mi>ρ</mml:mi> <mml:mo>∗</mml:mo> </mml:msup> </mml:math> , <mml:mi>ν</mml:mi> β n q <mml:msub> <mml:mi>T</mml:mi> <mml:mi>e</mml:mi> </mml:msub> <mml:mrow> <mml:mo>/</mml:mo> </mml:mrow> <mml:mi>i</mml:mi> has been achieved in JET L-mode dominant electron heating (NBI+ohmic) conditions....
Implementing tungsten as a plasma facing material in ITER and future fusion reactors will require effective monitoring of not just its level the but also distribution. That can be successfully achieved using detectors based on Gas Electron Multiplier (GEM) technology. This work presents conceptual design detecting unit for poloidal tomography to tested at WEST project tokamak. The current stage development is discussed covering aspects which include detector's spatial dimensions, gas...
Abstract A sequence of fuel recovery methods was tested in JET, equipped with the ITER-like beryllium main chamber wall and tungsten divertor, to reduce plasma deuterium concentration less than 1% preparation for operation tritium. This also a key activity regard refining clean-up strategy be implemented at end 2nd DT campaign JET (DTE2) assess tools that are envisaged mitigate tritium inventory build-up ITER. The began 4 days baking 320 °C, followed by further which Ion Cyclotron Wall...
Abstract The two best performing pulses of the so called ITER-Baseline scenario ( I p = 3.5 MA and P in ≈ 35 MW) JET-ITER like wall, one deuterium (D) other deuterium–tritium (D–T) plasma are examined compared this study. Generally, D–T Baseline exhibit an electron density level higher than D energy is comparable by up to 20%, reaching about 12 MJ pulse studied here. In contrast with pulses, often characterised increase time radiated power mantle region (0.70 < ρ 0.95), which may lead...
Abstract The experimental and theoretical analysis were focused on experiments conducted to assess the effect of plasma isotopes, protium (H), deuterium (D), tritium (T) ion cyclotron resonance heating (ICRH) related wall interactions. Comparison L-mode discharges with N = 1 3 He H minority ICRH scenarios done for different isotopes. For selected pulses, behaviour high-Z, mid-Z low-Z intrinsic impurity radiated power was investigated based data from VUV, visible spectroscopy, bolometry...
A Gaseous Electron Multiplier (GEM)-based detector is being developed for soft X-ray diagnostics on tokamaks. Its main goal to facilitate transport studies of impurities like tungsten. Such are very relevant ITER, where the excessive accumulation in plasma core should be avoided. This contribution provides details preliminary tests at ASDEX Upgrade (AUG) with a focus most important aspects operation harsh radiation environment. It was shown that both spatially and spectrally resolved data...
This paper presents the results of energy resolution simulation for triple GEM-based detector x-ray quantum 5.9 keV . Photons this are emitted by 55Fe source, which is a standard calibration marker type detectors. The calculations were made in Garfield++ two stages. In first stage, distribution amount primary electrons generated drift volume was simulated using Heed program. Secondly, resulting quantitative treated as source electron avalanches propagated through whole detector. obtained...
The GEM based detecting system is currently being developed for poloidal tomography to be used at WEST project tokamak. It consists of two detectors planar and cylindrical geometry the vertical horizontal ports, respectively. Several laboratory tests were conducted assess performance prototype verify proposed design. For that, measurements with 55Fe source X-ray generator performed. detector's behavior was tested gas mixtures: Ar/CO2 Ar/CO2/CF4 detector amplification dependencies on high...
An increased attention to tungsten material is related a fact that it became main candidate for the plasma facing in ITER and future fusion reactor. The proposed work refers studies of W influence on performances by developing new detectors based Gas Electron Multiplier GEM) technology tomographic transport ITER-oriented tokamaks, e.g. WEST project. It presents current stage design cylindrically bent SXR GEM detector construction horizontal port implementation. Concept overcome an...
This paper presents the results of research on interactions pulsed plasma streams, as generated by PF-1000 facility, with solid targets made tungsten or carbon fibre composite. The device was equipped a modified inner electrode central insert 50 mm in diameter. experimental chamber filled pure deuterium at p0 = 1.47 hPa. At charging voltage U0 24 kV, maximum current amounted to 1.8 MA about 5.5 μs after discharge initiation. investigated were located z-axis, distance 9 cm from end. For...