%0 Journal Article
%A Borodin, D.
%A Romazanov, J.
%A Pitts, R. A.
%A Lisgo, S. W.
%A Brezinsek, S.
%A Borodkina, I.
%A Eksaeva, Alina
%A Safi, E.
%A Nordlund, K.
%A Kirschner, A.
%A Linsmeier, Ch.
%T Improved ERO modelling of beryllium erosion at ITER upper first wall panel using JET-ILW and PISCES-B experience
%J Nuclear materials and energy
%V 19
%@ 2352-1791
%C Amsterdam [u.a.]
%I Elsevier
%M FZJ-2021-01518
%P 510 - 515
%D 2019
%X 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.
%F PUB:(DE-HGF)16
%9 Journal Article
%U <Go to ISI:>//WOS:000470746100080
%R 10.1016/j.nme.2019.03.016
%U https://juser.fz-juelich.de/record/891433