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Modelling of Impurity Transport and Plasma–Wall Interaction in Fusion Devices with the ERO Code: Basics of the Code and Examples of Application
Author(s) -
Kirschner A.,
Tskhakaya D.,
Kawamura G.,
Borodin D.,
Brezinsek S.,
Ding R.,
Linsmeier Ch.,
Romazanov J.
Publication year - 2016
Publication title -
contributions to plasma physics
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.531
H-Index - 47
eISSN - 1521-3986
pISSN - 0863-1042
DOI - 10.1002/ctpp.201610014
Subject(s) - tungsten , plasma , impurity , materials science , deposition (geology) , fusion , atomic physics , fusion power , magnetic field , debye sheath , physics , nuclear physics , geology , paleontology , linguistics , philosophy , sediment , metallurgy , quantum mechanics
The 3D ERO code, which simulates plasma–wall interaction and impurity transport in magnetically confined fusion‐relevant devices is described. As application, prompt deposition of eroded tungsten has been simulated at surfaces with shallow magnetic field of 3 T. Dedicated PIC simulations have been performed to calculate the characteristics of the sheath in front of plasma–exposed surfaces to use as input for these ERO simulations. Prompt deposition of tungsten reaches 100% at the highest electron temperature and density. In comparison to more simplified assumptions for the sheath the amount of prompt deposition is in general smaller if the PIC–calculated sheath is used. Due to friction with the background plasma the impact energy of deposited tungsten can be significantly larger than the energy gained in the sheath potential.