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Improved ERO modelling of beryllium erosion at ITER upper first wall panel using JET-ILW and PISCES-B experience

Authors
  • Borodin, D.
  • Andersson Sundén, Erik
  • Binda, F.
  • Cecconello, Marco
  • Conroy, Sean
  • Dzysiuk, N.
  • Ericsson, Göran
  • Eriksson, Jacob
  • Hellesen, C.
  • Hjalmarsson, Anders
  • Possnert, Göran
  • Sjöstrand, Henrik
  • Skiba, M.
  • Weiszflog, Matthias
  • Zychor, I.
Publication Date
Jan 01, 2019
Identifiers
DOI: 10.1016/j.nme.2019.03.016
OAI: oai:DiVA.org:uu-398658
Source
DiVA - Academic Archive On-line
Keywords
Language
English
License
Green
External links

Abstract

ERO is a 3D Monte-Carlo impurity transport and plasma-surface interaction code. In 2011 it was applied for the ITER first wall (FW) life time predictions [1] (critical blanket module BM11). After that the same code was significantly improved during its application to existing fusion-relevant plasma devices: the tokamak JET equipped with an ITER-like wall and linear plasma device PISCES-B. This has allowed testing the sputtering data for beryllium (Be) and showing that the "ERO-min" fit based on the large (50%) deuterium (D) surface content is well suitable for plasma-wetted areas (D plasma). The improved procedure for calculating of the effective sputtering yields for each location along the plasma-facing surface using the recently developed semi-analytical sheath approach was validated. The re-evaluation of the effective yields for BM11 following the similar revisit of the JET data has indicated significant increase of erosion and motivated the current re-visit of ERO simulations. / <p>For complete list of authors see http://dx.doi.org/10.1016/j.nme.2019.03.016</p>

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