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

JET Contributors

doi:10.1016/j.nme.2019.03.016

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

JET Contributors

Research output: Contribution to journal › Article › peer-review

20 Scopus citations

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 language	English
Pages (from-to)	510-515
Number of pages	6
Journal	Nuclear Materials and Energy
Volume	19
DOIs	https://doi.org/10.1016/j.nme.2019.03.016
State	Published - May 2019
Externally published	Yes

Bibliographical note

Publisher Copyright:
© 2019

Funding

This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom Research and Training Programme 2014–2018 under grant agreement No 633053 . The views and opinions expressed herein do not necessarily reflect those of the European Commission or of the ITER organization. The authors thank R. Doerner and D. Nishijima for the discussions and valuable insight from the PISCES-B side. The computer simulation time is provided by the Jülich Supercomputing Centre. We acknowledge grants of computer capacity from the IT Centre for Science in Finland, CSC and the Finnish Grid and Cloud Infrastructure (persistent identifier urn:nbn:fi:research-infras-2016072533).

Funders	Funder number
IT Centre for Science in Finland
Horizon 2020 Framework Programme
H2020 Euratom	633053
China Scholarship Council	research-infras-2016072533

Keywords

Beryllium
ERO code
Erosion
ITER first wall
JET ITER-like wall
Modelling

Access to Document

10.1016/j.nme.2019.03.016

Cite this

@article{4b00aa69afba4d9aa24f2dd8e4bbf1fa,

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

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.",

keywords = "Beryllium, ERO code, Erosion, ITER first wall, JET ITER-like wall, Modelling",

author = "\{JET Contributors\} and D. Borodin and J. Romazanov and Pitts, \{R. A.\} and Lisgo, \{S. W.\} and S. Brezinsek and I. Borodkina and A. Eksaeva and E. Safi and K. Nordlund and A. Kirschner and Ch Linsmeier",

note = "Publisher Copyright: {\textcopyright} 2019",

year = "2019",

month = may,

doi = "10.1016/j.nme.2019.03.016",

language = "אנגלית",

volume = "19",

pages = "510--515",

journal = "Nuclear Materials and Energy",

issn = "2352-1791",

publisher = "Elsevier Ltd.",

}

TY - JOUR

T1 - Improved ERO modelling of beryllium erosion at ITER upper first wall panel using JET-ILW and PISCES-B experience

AU - JET Contributors

AU - Borodin, D.

AU - Romazanov, J.

AU - Pitts, R. A.

AU - Lisgo, S. W.

AU - Brezinsek, S.

AU - Borodkina, I.

AU - Eksaeva, A.

AU - Safi, E.

AU - Nordlund, K.

AU - Kirschner, A.

AU - Linsmeier, Ch

PY - 2019/5

Y1 - 2019/5

N2 - 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.

AB - 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.

KW - Beryllium

KW - ERO code

KW - Erosion

KW - ITER first wall

KW - JET ITER-like wall

KW - Modelling

UR - https://www.scopus.com/pages/publications/85064311721

U2 - 10.1016/j.nme.2019.03.016

DO - 10.1016/j.nme.2019.03.016

M3 - ???researchoutput.researchoutputtypes.contributiontojournal.article???

AN - SCOPUS:85064311721

SN - 2352-1791

VL - 19

SP - 510

EP - 515

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

ER -

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

Abstract

Bibliographical note

Funding

Keywords

Access to Document

Other files and links

Fingerprint

Cite this