Journal Article

FZJ-2020-00026

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png First Monte-Carlo modelling of global beryllium migration in ITER using ERO2.0

Romazanov, J. (Corresponding author)FZJ* ; Brezinsek, S.FZJ* ; Kirschner, A.FZJ* ; Borodin, D.FZJ* ; Eksaeva, A.FZJ* ; Pitts, R. A. ; Lisgo, S. W. ; Anand, H. ; Veshchev, E. ; Neverov, V. S. ; Kukushkin, A. B. ; Alekseev, A. G. ; Linsmeier, C.FZJ*

2019
Wiley-VCH Weinheim

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Please use a persistent id in citations: http://hdl.handle.net/2128/25516  doi:10.1002/ctpp.201900149

Abstract: 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. An important goal of the study is to provide synthetic signals for the design of two key diagnostics: the main chamber visible spectroscopy and the laser in‐vessel viewing systems. The simulations are performed using toroidally symmetric plasma backgrounds obtained by combining SOLPS simulations extended to the wall using the OSM‐EIRENE‐DIVIMP edge code package. These are then further combined with a shadowing model using magnetic field line tracing to provide a three‐dimensional correction for the flux patterns. The resulting plasma wetted area, which amounts to ∼10% of the total first wall area, is in excellent agreement with shadowing calculations obtained with the SMITER field line tracing code. The simulations reveal that the main Be erosion zones are located in regions intersected by the secondary separatrix, in particular the upper Be panels, which are close to the secondary X‐point. For the particular high‐density Q = 10 background plasma case studied here, ∼80% of the eroded Be is found to re‐deposit on main chamber surfaces. The rest migrates in almost equal parts to the inner and outer divertor and is deposited close to the strike lines.

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Contributing Institute(s):

1. Plasmaphysik (IEK-4)
2. JARA - HPC (JARA-HPC)

Research Program(s):

1. 174 - Plasma-Wall-Interaction (POF3-174) (POF3-174)
2. 3D Monte-Carlo simulations of plasma-wall interaction and impurity transport in fusion devices (jiek43_20190501) (jiek43_20190501)

Appears in the scientific report 2020

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Database coverage:
; ; Clarivate Analytics Master Journal List ; Current Contents - Physical, Chemical and Earth Sciences ; Ebsco Academic Search ; IF < 5 ; JCR ; Nationallizenz ; SCOPUS ; Science Citation Index ; Science Citation Index Expanded ; Web of Science Core Collection

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