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

001     891433
005     20240711114034.0
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037 _ _ |a FZJ-2021-01518
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100 1 _ |a Borodin, D.
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245 _ _ |a Improved ERO modelling of beryllium erosion at ITER upper first wall panel using JET-ILW and PISCES-B experience
260 _ _ |a Amsterdam [u.a.]
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520 _ _ |a 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.
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700 1 _ |a Romazanov, J.
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700 1 _ |a Pitts, R. A.
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700 1 _ |a Lisgo, S. W.
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700 1 _ |a Brezinsek, S.
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700 1 _ |a Borodkina, I.
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700 1 _ |a Eksaeva, Alina
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700 1 _ |a Nordlund, K.
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700 1 _ |a Kirschner, A.
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700 1 _ |a Linsmeier, Ch.
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