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@ARTICLE{Brezinsek:202205,
author = {Brezinsek, Sebastijan},
title = {{P}lasma-surface interaction in the {B}e/{W} environment:
{C}onclusions drawn from the {JET}-{ILW} for {ITER}},
journal = {Journal of nuclear materials},
volume = {463},
issn = {0022-3115},
address = {Amsterdam [u.a.]},
publisher = {Elsevier Science},
reportid = {FZJ-2015-04494},
pages = {11 - 21},
year = {2015},
abstract = {The JET ITER-Like Wall experiment (JET-ILW) provides an
ideal test bed to investigate plasma-surface interaction
(PSI) and plasma operation with the ITER plasma-facing
material selection employing beryllium in the main chamber
and tungsten in the divertor. The main PSI processes:
material erosion and migration, (b) fuel recycling and
retention, (c) impurity concentration and radiation have
be1en studied and compared between JET-C and JET-ILW. The
current physics understanding of these key processes in the
JET-ILW revealed that both interpretation of previously
obtained carbon results (JET-C) and predictions to ITER need
to be revisited. The impact of the first-wall material on
the plasma was underestimated.Main observations are: (a) low
primary erosion source in H-mode plasmas and reduction of
the material migration from the main chamber to the divertor
(View the MathML sourcefactor7) as well as within the
divertor from plasma-facing to remote areas (View the MathML
sourcefactor30-50). The energetic threshold for beryllium
sputtering minimises the primary erosion source and inhibits
multi-step re-erosion in the divertor. The physical
sputtering yield of tungsten is low as 10-510-5 and
determined by beryllium ions. (b) Reduction of the long-term
fuel retention (View the MathML sourcefactor10-20) in
JET-ILW with respect to JET-C. The remaining retention is
caused by implantation and co-deposition with beryllium and
residual impurities. Outgassing has gained importance and
impacts on the recycling properties of beryllium and
tungsten. (c) The low effective plasma charge
(Zeff=1.2Zeff=1.2) and low radiation capability of beryllium
reveal the bare deuterium plasma physics. Moderate nitrogen
seeding, reaching Zeff=1.6Zeff=1.6, restores in particular
the confinement and the L-H threshold behaviour.
ITER-compatible divertor conditions with stable
semi-detachment were obtained owing to a higher density
limit with ILW. Overall JET demonstrated successful plasma
operation in the Be/W material combination and confirms its
advantageous PSI behaviour and gives strong support to the
ITER material selection.},
cin = {IEK-4},
ddc = {530},
cid = {I:(DE-Juel1)IEK-4-20101013},
pnm = {174 - Plasma-Wall-Interaction (POF3-174)},
pid = {G:(DE-HGF)POF3-174},
typ = {PUB:(DE-HGF)16},
UT = {WOS:000358467200003},
doi = {10.1016/j.jnucmat.2014.12.007},
url = {https://juser.fz-juelich.de/record/202205},
}