E. Pawelec
A5072365454- Magnetic confinement fusion research
- Fusion materials and technologies
- Lubricants and Their Additives
- Plasma Diagnostics and Applications
- Technical Engine Diagnostics and Monitoring
- Superconducting Materials and Applications
- Tribology and Wear Analysis
- Laser-induced spectroscopy and plasma
- Laser-Plasma Interactions and Diagnostics
- Vacuum and Plasma Arcs
- Particle accelerators and beam dynamics
- Surface Treatment and Coatings
- Metal and Thin Film Mechanics
- Biodiesel Production and Applications
- Ionosphere and magnetosphere dynamics
- Nuclear reactor physics and engineering
- Advancements in Materials Engineering
- Nuclear Materials and Properties
- Welding Techniques and Residual Stresses
- Gas Dynamics and Kinetic Theory
- Tribology and Lubrication Engineering
- Plasma and Flow Control in Aerodynamics
- Spectroscopy and Laser Applications
- Atomic and Molecular Physics
- Plasma Applications and Diagnostics
University of Opole
2011-2024
Institute of Physics
2006-2024
Czech Academy of Sciences, Institute of Physics
2023-2024
Culham Science Centre
2022
United Kingdom Atomic Energy Authority
2022
Łukasiewicz Research Network
2020
Royal Military Academy
2020
Łukasiewicz - Institute for Sustainable Technologies
2004-2018
National Centre for Nuclear Research
2006
Centre National de la Recherche Scientifique
2006
The erosion of tungsten (W), induced by the bombardment plasma and impurity particles, determines lifetime plasma-facing components as well impacting on performance influx W into confined region. screening divertor transport in largely content core, but source strength itself has a vital impact this process. JET tokamak experiment provides access to large set erosion-determining parameters permits detailed description closest ITER one: (i) effective sputtering yields fluxes function energy...
Abstract After the second Deuterium–Tritium Campaign (DTE2) in JET tokamak with ITER-Like Wall (ILW) and full tritium campaigns that preceded followed after DTE2, a sequence of fuel recovery methods was applied to promote removal from wall components. The started several days baking main chamber walls at 240 °C 320 °C. Subsequently, superimposed Ion-Cyclotron Conditioning (ICWC) Glow Discharge (GDC) cleaning cycles deuterium. Diverted plasma operation deuterium different strike point...
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...
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 This paper reports the first experiment carried out in deuterium–tritium addressing integration of a radiative divertor for heat-load control with good confinement. Neon seeding was time D–T plasma as part second campaign JET its Be/W wall environment. The technical difficulties linked to re-ionisation heat load are reported T and D–T. compares impact neon on plasmas their D counterpart detachment, localisation radiation, scrape-off profiles, pedestal structure, edge localised modes global
Abstract Deuterium (D) and beryllium (Be) fluxes are obtained in JET Low-confinement (L-mode) plasmas at the outer limiters of first wall using calibrated visible cameras. They inferred from measured radiances spectroscopic S/XB method. From fluxes, effective gross erosion yield Yeff limiter surface is estimated. After discussing uncertainties proposed methodology, we show dependence deduced particle recent L-mode on: separatrix-limiter clearance, magnetic field plasma current, NBI ICR...
Using spectroscopic and electric measurements, vibrational rotational molecular gas temperatures as well free electron temperature concentration were determined in different regions of a time-periodical like, atmospheric pressure non-equilibrium lοw current gliding arc.It was shown that this discharge includes an initial quasi-equilibrium zone, with the quasi--equilibrium 4 to 6 kK, zone about 10 3 translational from 1 1.5 kK.The transition between two mentioned zones coincides phenomenon...
During the 2015-2016 JET campaigns many efforts have been devoted to exploration of high-performance plasma scenarios envisaged for DT operation in JET.In this paper we review various key recent hybrid discharges and model combined ICRF+NBI heating.These deuterium with beams had ICRF antenna frequency tuned match cyclotron minority H at centre tokamak coinciding second harmonic resonance D. The modelling takes into account synergy between NBI heating through D beam ions which allows us...
We present here the results of spectroscopic analysis high-resolution visible spectra beryllium hydride and its isotopologues (BeH, BeD, BeT), produced during plasma–surface interactions limiter divertor JET-ILW (ITER-like Wall) pulses. The production, being an important part wall erosion via chemical-assisted physical sputtering, shows dependence on plasma conditions, also isotope content plasma. This work that this is true for molecular energy distributions, parameterized by rotational...
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 required heating power, <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>P</mml:mi> <mml:mi>LH</mml:mi> </mml:mrow> </mml:msub> </mml:math> , to access the high confinement regime (H-mode) in tritium containing plasmas is investigated JET with ITER-like wall at a toroidal magnetic field of <mml:mi>B</mml:mi> <mml:mi>t</mml:mi> <mml:mo>=</mml:mo> <mml:mn>1.8</mml:mn> T and plasma current <mml:mi>I</mml:mi>...
The flow properties of Xe atoms were investigated in the 1 kW class PPS100-ML Hall effect thruster by means Doppler-shifted laser-induced fluorescence spectroscopy near infrared. Fluorescence spectra resonant level and metastable have been acquired inside outside channel under several operating conditions. Analytical treatment modelling measured lineshapes indicate atom axial velocity increases to a value well above sound speed before decreasing quickly near-field plume. Numerical...
Ammonia formation was studied in a series of dedicated nitrogen seeded H-mode discharges at ASDEX Upgrade.The evolution ammonia investigated with reference phase before the seeding, and long, stable flat-top nitrogen-seeded phase.It monitored divertor spectroscopy analysis exhaust gas.The amount detected increased continuously over course five same seeding rate.The trend observed density core plasma, as measured by charge exchange recombination other signals, linked to effects seeding.The...
Measurements of the ion currents to and plasma conditions at low-field side (LFS) divertor target plate in low-confinement mode plasmas JET ITER-like wall materials configuration show that core density required detach LFS is independent hydrogenic species protium, deuterium tritium, a 40 %/60 % deuterium–tritium mixture. This observation applies with strike line connected horizontal part chosen because its superior diagnostic coverage. The finding operational status cryogenic pump. electron...
The pre-fusion power operation (PFPO) phase of ITER, as described in the ITER research plan with Staged Approach2, includes both hydrogen (H) and helium (He) plasma operations. In preparation for PFPO, WEST JET ran He campaigns to study plasma-wall interactions a tungsten environment. included back-and-forth transition between H or deuterium (D) allowing assessment achievable content well accessible wall reservoirs respective species. changeovers tokamak pulses fixed divertor configuration....
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...
Abstract The heating power to access the high confinement mode (H-mode), P LH , scales approximately inversely with isotope mass of main ion plasma species as found in (protonic) hydrogen, deuterium and tritium plasmas many fusion facilities over last decades. In first dedicated L–H transition experiments at Joint European Torus (JET) tokamak facility ITER-like wall (ILW), threshold, was studied systematically pure hydrogen–tritium mixtures a magnetic field 1.8 T current 1.7 MA order assess...
We present a study of the power threshold for L–H transitions (PLH) in almost pure helium plasmas, obtained recent experiments at JET with an ITER-like wall (Be and W divertor). The most notable new result is that density which PLH minimum, , considerably higher than deuterium hydrogen plasmas. discuss possible implications ITER its pre-fusion operating phase.
Several thin layers of an arc plasma column were observed side-on at different distances from the cathode. The was operated in argon atmospheric pressure with current equal to 200 A. As basic diagnostic method we used Olsen - Richter diagrams. For determination temperature Larenz Fowler Milne and Boltzmann plot methods applied. Electron density measured Stark width ArII line continuum intensity.
Intra-ELM tungsten sources, which dominate the total W source, are quantified in inner and outer divertor of JET-ILW. The amount sputtered atoms for individual ELMs demonstrates a clear dependence on ELM frequency. It decreases when pedestal temperature is lower and, correspondingly, frequency higher. Nevertheless, entire gross erosion source (the number eroded per second due to ELMs) increases initially with reaches its maximum at fELM ≈ 50–55 Hz followed by reduction high range. in/out...
Abstract The isotope effect, hydrogen (H) versus deuterium (D), on the gross beryllium (Be) erosion yield has been measured in ohmic limiter plasmas JET tokamak by spectroscopic means. A simplified method to extract effective sputtering from quotient of radiances D α or γ and Be II lines at 527 nm was applied. clear effect found, being about a factor 2 larger compared H whole explored plasma density range. This is agreement with physical data obtained + ion beams also material surface...
This paper explores the plasma parameters of helium and hydrogen Ion Cyclotron Wall Conditioning (ICWC) discharges performed in JET as part a He/H fuelling changeover experiment. The conducted study shows that with higher density is formed than hydrogen. A distinct glow ion cyclotron resonance zone observed throughout discharge He. In H-ICWC discharges, lower radio-frequency coupling efficiency coupled power was He-ICWC discharges. While concentration decreased number pulses same for...
Abstract High resolution <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:msubsup> <mml:mrow> <mml:mtext>D</mml:mtext> </mml:mrow> <mml:mn>2</mml:mn> <mml:mo>∗</mml:mo> </mml:msubsup> </mml:math> Fulcher band spectroscopy was used in the MAST-U divertors during Super-X and (shorter-legged) elongated divertor density ramps with <mml:msub> </mml:msub> fuelling from mid-plane high-field side. In case, upper showed ground state rotational temperatures of molecules...
A tracer-encapsulated solid pellet (TESPEL) injection system for the TJ-II stellarator was recently developed. In order to reduce time and cost development, we combined a TESPEL injector provided by National Institute Fusion Science with an existing cryogenic system. Consequently, into plasma successfully achieved, which confirmed several diagnostics including normal-incidence spectrometer monitoring tracer impurity behavior.