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.
Improved ERO modelling of beryllium erosion at ITER upper first wall panel using JET-ILW and PISCES-B experience
Borodin D.; Romazanov J.; Pitts R.A.; Lisgo S.W.; Brezinsek S.; Borodkina I.; Eksaeva A.; Safi E.; Nordlund K.; Kirschner A.; Linsmeier C.; JET Contributors
Journal:
Nuclear materials and energy 19 pp. 510 - 515
Year:
2019
ISTP Authors: Andrea Murari
Nicola Pomaro
Carlo Sozzi
Cesare Taliercio
Gabriele Gervasini
Paolo Innocente
Nicola Vianello
David Terranova
Matteo Brombin
Enzo Lazzaro
Enzo Lazzaro
Laura Laguardia
Edoardo Alessi
Andrea Muraro
Andrea Uccello
Marco Valisa
Marco Tardocchi
Lorella Carraro
Fabio Degli Agostini
Paola Mantica
Roberto Pasqualotto
Keywords: Modelling, Beryllium, Erosion, ITER first wall, JET ITER-like wall, ERO code
Research Activitie: JOURNAL ARTICLES
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