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

JET Contributors, Jan Mlynar, T. Ahlgren, L. Aho-Mantila, M. Airila, C. Björkas, A. Lahtinen, K. Nordlund, E. Safi, S. K. Sipila , O. Asunta, M. Groth, A. Hakola, J. Karhunen, S. Koivuranta, T. Kurki-Suonio, B. Lomanowski, J. Lonnroth, A. Salmi, M. I. K. SantalaJ. Varje, P. Siren, J. Likonen, A. Jarvinen, D. Borodin

Research output: Contribution to journalArticleScientificpeer-review

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.
Original languageEnglish
JournalNuclear Materials and Energy
Volume19
Pages (from-to)510-515
Number of pages6
ISSN2352-1791
DOIs
Publication statusPublished - May 2019
MoE publication typeA1 Journal article-refereed

Fields of Science

  • 114 Physical sciences

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