Results 71 to 80 of about 217 (90)

Simulation Analysis of the Carbon Deposition Profile on Directional Material Probes in the Large Helical Device Using the ERO2.0 Code

Simulation Analysis of the Carbon Deposition Profile on Directional Material Probes in the Large Helical Device Using the ERO2.0 Code
0000-0003-0655-7347 The carbon deposition profile on a Directional Material Probe (DMP) installed in the inboard side of the torus in the Large Helical Device (LHD) is investigated using the ERO2.0 code. The experimental result of the carbon deposition profile with short and wide shadows (lower deposition density areas) on the DMP is reasonably ...
openaire  

3D-simulation of impurity transport in a fusion edge plasma by means of a massively parallelized Monte-Carlo code

, 2019
Die Erosion von Wandkomponenten und die Tritiumrückhaltung begrenzen die Verfügbarkeit und Lebensdauer von ITER und zukünftiger Fusionsreaktoren.
Romazanov, Juri (M. Sc.)
core  

Validation of the plasma-wall interaction simulation code ERO2.0 by the analysis of tungsten migration in the open divertor region in the Large Helical Device

Validation of the plasma-wall interaction simulation code ERO2.0 by the analysis of tungsten migration in the open divertor region in the Large Helical Device
0000-0003-0655-7347 Tungsten migration in the open divertor region in the Large Helical Device is analyzed for validating the three-dimensional plasma-wall interaction simulation code ERO2.0. The ERO2.0 simulation reproduced the measurement of localized tungsten migration from a tungsten-coated divertor plate installed in the inboard side of the torus.
openaire  

Erosion and impurity migration modelling in linear devices and tokamaks

DOTTORATOL’interazione plasma-materiali (PMI) è una delle principali sfide da affrontare per essere in grado di sfruttare, in futuro, la fusione nucleare come sorgente affidabile di energia.
ALBERTI, GABRIELE
core  

3D-Simulation des Verunreinigungstransports in einem Fusions-Randschichtplasma mit dem massiv-parallelen Monte Carlo-Code ERO2.0

, 2016
Romazanov, J., Borodin, D., Kirschner, A., Linsmeier, Ch., Gibbon, P., Brömmel, D., Steinbusch, B.   +6 more
openaire   +1 more source

First efforts in numerical modeling of tungsten migration in WEST with SolEdge2D-EIRENE and ERO2.0

Physica Scripta, 2020
The first simulations of tungsten migration in WEST are performed with the SolEdge2D-EIRENE and ERO2.0 codes to support experimental investigations into the erosion of plasma-facing components and plasma impurity content. The impact of varying the background density on (i) the amount of tungsten penetrating the confined plasma, (ii) the promptly ...
A Gallo, J Romazanov, S Brezinsek
exaly   +5 more sources

Multiphysics Modeling of Impurity Transport for FNSF Startup Scenario with ERO2.0

Fusion Science and Technology, 2023
This study focuses on performing a multiphysics study using the ERO2.0 and UEDGE codes for two standard double null configurations for the Fusion Nuclear Science Facility: (a) 100% recycling and (b) 99% recycling. Results show that the main contributor to tungsten erosion along the divertor plates is impurities from the midplane waveguides. In addition,
Marcos X. Navarro, Tom Rognlien, Marvin Rensink, Juri Romazanov, Andreas Kirschner, Oliver Schmitz   +5 more
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Predictive 3D modelling of erosion and deposition in ITER with ERO2.0: from beryllium main wall, tungsten divertor to full-tungsten device

Physica Scripta, 2022
Abstract Erosion and deposition is modelled with ERO2.0 for a hypothetical full-tungsten ITER for an ELM-free H-Mode baseline deuterium discharge. A parameter study considering seeding impurities (Ne, Ar, Kr, Xe) at constant percentages (0.05% to 1.0%) of the deuterium ion flux is done while neglecting their radiation cooling and core
A Eksaeva, A Kirschner, J Romazanov, S Brezinsek, Ch Linsmeier, F Maviglia, M Siccinio, S Ciattaglia   +7 more
openaire   +2 more sources

ERO2.0 and SOLPS-ITER modelling of rough W coatings exposures to He plasmas in the linear machine GyM [PDF]

, 2021
It is well-known that plasma-material interaction (PMI) deeply modifies the plasma-facing components in the tokamak environment [1]. Due to their simplified geometry and magnetic field topology, PMI is usually investigated in linear plasma devices, using non-hydrogenic plasmas [2], such as Argon and Helium. These type of plasmas are of interest also in
Sala M, Uccello A, Dellasega D, Tonello E, Alberti G, Vassallo E, Pedroni M, Romazanov J, Eksaeva A, Passoni M   +9 more
openaire   +1 more source

Study the role of roughness in the sputtering process of tungsten by GyM helium plasma: experiments and ERO2.0 modelling

2023
Erosion of plasma-facing components affects their lifetime and other plasma-material interaction (PMI) issues important for ITER. Microscale morphology is shown to have a significant effect on surface sputtering properties [1], thus influencing the erosion-deposition pattern in tokamaks.
Uccello A, Alberti G, Cremona A, Ghezzi F, Pedroni M, Vassallo E, Tonello E, Vavassori D, Dellasega D, Passoni M   +9 more
openaire   +2 more sources