Results 11 to 20 of about 217 (90)

The impact of surface morphology on the erosion of metallic surfaces – Modelling with the 3D Monte-Carlo code ERO2.0 [PDF]

Nuclear Materials and Energy, 2021
The roughness of metallic surfaces has a vital impact on the erosion of plasma-facing materials. Roughness determines the effective sputtering yield Yeff of the facing material.
A. Eksaeva, D. Borodin, J. Romazanov, A. Kirschner, A. Kreter, B.Göths, M. Rasinski, B. Unterberg, S. Brezinsek, Ch. Linsmeier, E.Vassallo, M. Passoni, D. Dellasega, M. Sala, F. Romeo, I. Borodkina   +15 more
doaj   +7 more sources

ERO2.0 modelling of nanoscale surface morphology evolution [PDF]

Nuclear Fusion, 2021
Abstract Plasma–material interaction (PMI) in tokamaks determines the life-time of first-wall (FW) components. Due to PMI, FW materials are eroded and transported within the device. Erosion is strongly influenced by the original morphology of the component, due to particle redeposition on near surface structures and to the changing of ...
G Alberti, M Sala, J Romazanov
exaly   +8 more sources

First ERO2.0 modeling of Be erosion and non-local transport in JET ITER-like wall [PDF]

Physica Scripta, 2017
ERO is a Monte-Carlo code for modeling plasma-wall interaction and 3D plasma impurity transport for applications in fusion research. The code has undergone a significant upgrade (ERO2.0) which allows increasing the simulation volume in order to cover the entire plasma edge of a fusion device, allowing a more self-consistent treatment of ...
J Romazanov, D Borodin, A Kirschner
exaly   +11 more sources

Global SOLPS-ITER and ERO2.0 coupling in a linear device for the study of plasma–wall interaction in helium plasma [PDF]

Nuclear Fusion, 2023
Plasma–wall interaction (PWI) is a great challenge in the development of a nuclear fusion power plant. To investigate phenomena like erosion of plasma-facing components, impurity transport and redeposition, one needs reliable numerical tools for the ...
G. Alberti, E. Tonello, P. Carminati, A. Uccello, X. Bonnin, J. Romazanov, S. Brezinsek, M. Passoni   +7 more
doaj   +7 more sources

ERO2.0 modelling of divertor marker erosion in ASDEX Upgrade L-mode experiments [PDF]

Nuclear Materials and Energy
Erosion of small marker surfaces in an experiment conducted at the ASDEX Upgrade tokamak was modelled using the ERO2.0 code. In the experiment 5 × 5 mm2 and 1 × 1 mm2 Au marker spots were exposed to a series of high-temperature L-mode plasmas in the low ...
S. Saari, A. Hakola, J. Karhunen, M. Balden, C. Baumann, A. Järvinen, K. Krieger, H. Kumpulainen, J. Likonen, J. Romazanov   +9 more
doaj   +6 more sources

ERO2.0 modelling of the effects of surface roughness on molybdenum erosion and redeposition in the PSI-2 linear plasma device [PDF]

Physica Scripta, 2020
The surface morphology of plasma-facing components (PFCs) and its evolution during plasma irradiation has been shown to have a significant effect on the erosion and subsequent transport of sputtered particles in plasma. This in turn can influence the resulting lifetime of PFCs.
A Eksaeva, D Borodin, J Romazanov
exaly   +8 more sources

Improved material mixing model in ERO2.0: Nonlinear effect of boron concentration on tungsten sputtering and influx from mixed tungsten-boron surfaces

Nuclear Materials and Energy
An upgraded homogeneous mixing model for plasma-facing surfaces in ERO2.0 has been developed using a database of SDTrimSP mixed-material simulations, replacing earlier linear interpolation between pure-material sputtering yields. The SDTrimSP simulations
H.A. Kumpulainen, S. Brezinsek, J. Romazanov, A. Kirschner, C. Baumann, K. Schmid   +5 more
doaj   +4 more sources

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

Plasma and Fusion Research, 2022
0000-0003-0655-7347The 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.
M Shoji, S Masuzaki, G Kawamura
exaly   +6 more sources

ELM and inter-ELM tungsten erosion sources in high-power, JET ITER-like wall H-mode plasmas

Nuclear Materials and Energy, 2022
Simulations of JET ITER-like wall high-confinement mode plasmas, including type-I edge-localised modes (ELMs), using JINTRAC for the background plasmas and ERO2.0 for tungsten erosion and transport, predict virtually perfect screening of the primary W ...
H.A. Kumpulainen, M. Groth, S. Brezinsek, G. Corrigan, L. Frassinetti, D. Harting, F. Koechl, J. Karhunen, A.G. Meigs, M. O'Mullane, J. Romazanov   +10 more
doaj   +2 more sources

First Monte-Carlo modelling of global beryllium migration in ITER using ERO2.0 [PDF]

Contributions to Plasma Physics, 2019
ERO2.0 is a recently developed Monte‐Carlo code for modelling global erosion and redeposition in fusion devices. We report here on the code's application to ITER for studying the erosion of the beryllium (Be) first wall armour under burning plasma steady state diverted conditions.
Romazanov, Juri, Brezinsek, Sebastijan, Kukushkin, Alexander B., Alekseev, Andrey G., Linsmeier, Christian, Kirschner, Andreas, Borodin, Dmitriy, Eksaeva, Alina, Pitts, Richard A., Lisgo, Steven W., Anand, Himank, Veshchev, Evgeny, Neverov, Vlad S.   +12 more
core   +4 more sources