A5016140254- Magnetic confinement fusion research
- Fusion materials and technologies
- Nuclear Materials and Properties
- Plasma Diagnostics and Applications
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Metal and Thin Film Mechanics
- Laser-induced spectroscopy and plasma
- Atomic and Molecular Physics
- Ion-surface interactions and analysis
- Nuclear Physics and Applications
- Ionosphere and magnetosphere dynamics
- Diamond and Carbon-based Materials Research
- Metallurgical Processes and Thermodynamics
- Particle accelerators and beam dynamics
- Semiconductor materials and devices
- Organic and Molecular Conductors Research
- Advanced materials and composites
- Advanced Power Generation Technologies
- Surface and Thin Film Phenomena
- High-Energy Particle Collisions Research
- Electrochemical Analysis and Applications
- Advanced Chemical Physics Studies
- Coal and Coke Industries Research
Forschungszentrum Jülich
2014-2024
Culham Centre for Fusion Energy
2022-2024
Lipetsk State Technical University
2023
Culham Science Centre
2014-2022
Royal Military Academy
2020
VTT Technical Research Centre of Finland
2011-2013
Oak Ridge National Laboratory
2013
University of Lisbon
2013
University College Ghent
2011
Omsk State Technical University
2007-2009
The provision of a particle and power exhaust solution which is compatible with first-wall components edge-plasma conditions key area present-day fusion research mandatory for successful operation ITER DEMO. work package plasma-facing (WP PFC) within the European programme complements laboratory experiments, i.e. in linear plasma devices, electron ion beam loading facilities, studies performed toroidally confined magnetic such as JET, ASDEX Upgrade, WEST etc. connection both groups done via...
JET is used as a test bed for ITER, to investigate beryllium migration which connects the lifetime of first-wall components under erosion with tokamak safety, in relation long-term fuel retention. The (i) limiter and (ii) divertor configurations have been studied JET-ILW (JET Be first wall W divertor), compared those former JET-C carbon-based plasma-facing (PFCs)). For configuration, gross at contact point was determined situ by spectroscopy between 4% (Ein = 35 eV) more than 100%, caused...
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 We present recent highlights from the most operation phases of Wendelstein 7-X, advanced stellarator in world. Stable detachment with good particle exhaust, low impurity content, and energy confinement times exceeding 100 ms, have been maintained for tens seconds. Pellet fueling allows plasma reduced ion-temperature-gradient turbulence, during such phases, overall is so (energy often 200 ms) that attained density temperature profiles would not possible less optimized devices, since...
ITER will use beryllium as a plasma-facing material in the main chamber, covering total surface area of about 620 m2. Given importance erosion and co-deposition for tritium retention ITER, significant efforts have been made to understand behaviour under fusion-relevant conditions with high particle heat loads. This paper provides comprehensive report on state knowledge conditions: mechanisms their consequences, migration JET, fuel dust generation. The reviews basic laboratory studies,...
The effective sputtering yield of Be (Y tot ) was determined in-situ by emission spectroscopy low ionising as function the deuteron impact energy (E in = 25 -175eV and surface temperature (T surf 200 • C -520 C) limiter discharges carried out JET tokamak.Be self dominates erosion at high energies > 150eV causes Y far beyond 1.The drops to values, below 4.5%, accessible lowest ≃ 25eV achievable configuration.At medium energies, E 75eV , two contributors measured 9% were identified: third...
The recently developed Monte-Carlo code ERO2.0 is applied to the modelling of limited and diverted discharges at JET with ITER-like wall (ILW). global beryllium (Be) erosion deposition simulated compared experimental results from passive spectroscopy. For limiter configuration, it demonstrated that Be self-sputtering an important contributor (at least 35%) erosion. Taking this contribution into account, confirms previous evidence high deuterium (D) surface concentrations up ∼ 50% atomic...
Wall conditioning is essential in tokamak and stellarator research to achieve plasma performance reproducibility. This paper presents an overview of recent results, both from experiments present devices modelling, view with superconducting coils, focus on W7-X, JT-60SA ITER. In these devices, the coils stay energised throughout experimental day or week which demands for new techniques that work presence nominal field, addition proven methods such as baking, glow discharge (GDC) low-Z wall...
Abstract The paper provides an overview of recent modelling global material erosion and deposition in the fusion devices Wendelstein 7-X (W7-X), JET ITER using Monte-Carlo code ERO2.0. For validating tool a three-dimensional environment, W7-X simulations are performed to describe carbon from graphite test divertor units, which were equipped operational phase OP 1.2 analysed post-mortem. Synthetic spectroscopy line emission is compared with experimental results spectrometer measurement...
The ITER beryllium (Be) first wall (FW) panels are shaped to protect leading edges between neighbouring arising from assembly tolerances. This departure a perfectly cylindrical surface automatically leads magnetically shadowed regions where eroded Be can be re-deposited, together with co-deposition of tritium fuel. To provide benchmark for series erosion/re-deposition simulation studies performed the FW panels, dedicated experiments have been on EAST tokamak using specially designed,...
Rate coefficients for the excitation and ionization of neutral as well singly ionized particles and-–predominantly-–their ratios S(D)/XB, which are important conversion photon into particle fluxes in ionizing fusion boundary plasma, have been modelled experimentally determined plasmas fusion-relevant species such He I, Li C B I&II, O Si Mo W H2, CH(D), C2.
Mater.415 S165-S169) carried out with the LIM code of ITER first wall (FW) on beryllium (Be) erosion, re-deposition and tritium retention by co-deposition under steady-state burning plasma conditions have shown that, depending input parameter assumptions sputtering yields, erosion lifetime fuel some parts FW can be a serious concern.The importance issue is such that benchmark this previous work sought has been provided ERO (Pitts et al 2011 J. Nucl.Mater.415 S957-S964) simulations described...
ERO is a Monte-Carlo code for modeling plasma-wall interaction and 3D plasma impurity transport applications in fusion research. The has undergone significant upgrade (ERO2.0) which allows increasing the simulation volume order to cover entire edge of device, allowing more self-consistent treatment comparison with larger number variety experimental diagnostics. In this contribution, physics-relevant technical innovations new version are described discussed. capabilities demonstrated by...
Main processes of plasma-wall interaction and impurity transport in fusion devices their impact on the availability are presented modelling tools, particular three-dimensional Monte-Carlo code ERO, introduced. The capability ERO is demonstrated example tungsten erosion deposition modelling. dependence plasma temperature density studied by simulations with a simplified geometry assuming (almost) constant parameters. amount increases increasing electron density. Up to 100% eroded can be...
We report calculations of total (and absolute) electron-impact ionization cross sections (EICSs) for the fusion-relevant diatomic molecular species BeH, BeN, BeO, WH, WBe, WN, WO, O2, and N2 by means Deutsch-Märk binary-encounter-Bethe methods in energy range from threshold to 10 keV. In addition, we discuss an empirical scheme estimate partial ones based on reaction energetics laws explore its accuracy assessing available experimental data EICSs. Finally, also parameters obtained fitting...
The erosion, transport and deposition of tungsten in the outer divertor JET-ILW has been studied for an H-Mode discharge with low frequency ELMs. For this specific case inter-ELM electron temperature at strike point about 20 eV, sputtering between ELMs is almost exclusively due to beryllium impurity self-sputtering. However, during deuterium becomes important even dominates. amount simulated local relative sputtered very high reaches values 99% density 5E13 cm−3 temperatures 10 30 eV....
Abstract The Monte-Carlo code ERO2.0 was used to simulate steady-state erosion and transport of beryllium (Be) in the ITER main chamber. Various plasma scenarios were tested, including a variation species (hydrogen, deuterium, helium), conditions (density, temperature, flow velocity) magnetic configurations. study provides valuable predictions for Be divertor, where it is expected be an important contributor dust formation fuel retention due build-up co-deposited layers. gross net rates...
Abstract Neutral gas physics and neutral interactions with the plasma are key aspects of edge divertor in a fusion reactor including detachment phenomenon often seen as to dealing power exhaust challenges. A full description dynamics requires 6D kinetic approach, potentially time dependent, where details wall geometry play substantial role, extent that, e.g., subdivertor region has be included. The Monte Carlo (MC) approach used for about 30 years EIRENE (Reiter et al 2005 Fusion Sci....
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 After a long device enhancement phase, scientific operation resumed in 2022. The main new components are the water cooling of all plasma facing and water-cooled high heat flux divertor units. Water allowed for first long-pulse campaign. A maximum discharge length 8 min was achieved with total heating energy 1.3 GJ. Safe demonstrated attached detached mode. Stable detachment is readily some magnetic configurations but requires impurity seeding small pitch angle within edge islands....
Tungsten is foreseen as the plasma-facing component material for baffles, dome and strike-point area in ITER divertor. Quantification of W source, which connected with components lifetime plasma concentration, one outstanding issues qualification process. A dedicated experiment TEXTOR exposure a W/C twin limiter to near scrape-off layer has been carried out order address sputtering local mixing electron temperature range between Te=30 85 eV, achieved deuterium fueling four steps. The Te...
The low-energy erosion mechanisms of first-wall materials subject to a fusion plasma are poorly known theoretically, even though they pose critical problem for the development tokamak-like reactors. Using molecular dynamics computer simulations and analytical theory, we have examined fundamental materials, focusing on release from beryllium surfaces. We show that observed sputtering BeD molecules when exposed D can be explained by swift chemical mechanism, it also happen in BeW alloys. This...