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. Santala; J. Varje; P. Siren; J. Likonen; A. Jarvinen; D. Borodin

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
, 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. Santala

J. Varje, P. Siren, J. Likonen, A. Jarvinen, D. Borodin

Tutkimustuotos: Artikkelijulkaisu › Artikkeli › Tieteellinen › vertaisarvioitu

Abstrakti

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.

Alkuperäiskieli	englanti
Lehti	Nuclear Materials and Energy
Vuosikerta	19
Sivut	510-515
Sivumäärä	6
ISSN	2352-1791
DOI - pysyväislinkit	https://doi.org/10.1016/j.nme.2019.03.016
Tila	Julkaistu - toukok. 2019
OKM-julkaisutyyppi	A1 Alkuperäisartikkeli tieteellisessä aikakauslehdessä, vertaisarvioitu

Tieteenalat

114 Fysiikka

Pääsy asiakirjaan

10.1016/j.nme.2019.03.016Lisenssi: CC BY-NC-ND

1-s2.0-S2352179118302722-mainLopullinen julkaistu versio, 2,52 MBLisenssi: CC BY-NC-ND

Siteeraa tätä

JET Contributors, Mlynar, J., Ahlgren, T., Aho-Mantila, L., Airila, M., Björkas, C., Lahtinen, A., Nordlund, K., Safi, E., Sipila , S. K., Asunta, O., Groth, M., Hakola, A., Karhunen, J., Koivuranta, S., Kurki-Suonio, T., Lomanowski, B., Lonnroth, J., Salmi, A., ... Borodin, D. (2019). Improved ERO modelling of beryllium erosion at ITER upper first wall panel using JET-ILW and PISCES-B experience. Nuclear Materials and Energy, 19, 510-515. https://doi.org/10.1016/j.nme.2019.03.016

@article{970ddfb5fd0744e69ad8e7c99f0f6243,

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 = "114 Physical sciences",

author = "\{JET Contributors\} and Jan Mlynar and Teddy Craciunescu and Ferreira, \{Diogo R.\} and Pedro Carvalho and Ondrej Ficker and Ondrej Grover and Martin Imrisek and Jakub Svoboda and S. Abduallev and M. Abhangi and P. Abreu and M. Afzal and Aggarwal, \{K. M.\} and T. Ahlgren and Ahn, \{J. H.\} and L. Aho-Mantila and N. Aiba and M. Airila and R. Albanese and V. Aldred and D. Alegre and E. Alessi and P. Aleynikov and A. Alfier and A. Alkseev and M. Allinson and B. Alper and E. Alves and G. Ambrosino and R. Ambrosino and L. Amicucci and V. Amosov and Sunden, \{E. Andersson\} and M. Angelone and C. Bj{\"o}rkas and Chang, \{C. S.\} and X. Gao and Y. Gao and J. Harrison and A. Lahtinen and Y. Liu and K. Nordlund and A. Patel and S. Ranjan and E. Safi and J. Wu and Y. Zhou and Sipila, \{S. K.\} and O. Asunta and M. Groth and A. Hakola and J. Karhunen and S. Koivuranta and T. Kurki-Suonio and B. Lomanowski and J. Lonnroth and A. Salmi and Santala, \{M. I. K.\} and J. Varje and P. Siren and J. Likonen and A. Jarvinen and J. Denis and D. Borodin",

year = "2019",

month = may,

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

language = "English",

volume = "19",

pages = "510--515",

journal = "Nuclear Materials and Energy",

issn = "2352-1791",

publisher = "Elsevier Ltd. ",

}

JET Contributors, Mlynar, J, Ahlgren, T, Aho-Mantila, L, Airila, M, Björkas, C , Lahtinen, A , Nordlund, K, Safi, E, Sipila , SK, Asunta, O, Groth, M, Hakola, A, Karhunen, J, Koivuranta, S, Kurki-Suonio, T, Lomanowski, B, Lonnroth, J, Salmi, A, Santala, MIK, Varje, J, Siren, P, Likonen, J, Jarvinen, A & Borodin, D 2019, 'Improved ERO modelling of beryllium erosion at ITER upper first wall panel using JET-ILW and PISCES-B experience', Nuclear Materials and Energy, Vuosikerta 19, Sivut 510-515. https://doi.org/10.1016/j.nme.2019.03.016

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 - Mlynar, Jan

AU - Craciunescu, Teddy

AU - Ferreira, Diogo R.

AU - Carvalho, Pedro

AU - Ficker, Ondrej

AU - Grover, Ondrej

AU - Imrisek, Martin

AU - Svoboda, Jakub

AU - Abduallev, S.

AU - Abhangi, M.

AU - Abreu, P.

AU - Afzal, M.

AU - Aggarwal, K. M.

AU - Ahlgren, T.

AU - Ahn, J. H.

AU - Aho-Mantila, L.

AU - Aiba, N.

AU - Airila, M.

AU - Albanese, R.

AU - Aldred, V.

AU - Alegre, D.

AU - Alessi, E.

AU - Aleynikov, P.

AU - Alfier, A.

AU - Alkseev, A.

AU - Allinson, M.

AU - Alper, B.

AU - Alves, E.

AU - Ambrosino, G.

AU - Ambrosino, R.

AU - Amicucci, L.

AU - Amosov, V.

AU - Sunden, E. Andersson

AU - Angelone, M.

AU - Björkas, C.

AU - Chang, C. S.

AU - Gao, X.

AU - Gao, Y.

AU - Harrison, J.

AU - Lahtinen, A.

AU - Liu, Y.

AU - Nordlund, K.

AU - Patel, A.

AU - Ranjan, S.

AU - Safi, E.

AU - Wu, J.

AU - Zhou, Y.

AU - Sipila , S. K.

AU - Asunta, O.

AU - Groth, M.

AU - Hakola, A.

AU - Karhunen, J.

AU - Koivuranta, S.

AU - Kurki-Suonio, T.

AU - Lomanowski, B.

AU - Lonnroth, J.

AU - Salmi, A.

AU - Santala, M. I. K.

AU - Varje, J.

AU - Siren, P.

AU - Likonen, J.

AU - Jarvinen, A.

AU - Denis, J.

AU - Borodin, D.

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 - 114 Physical sciences

U2 - 10.1016/j.nme.2019.03.016

DO - 10.1016/j.nme.2019.03.016

M3 - Article

SN - 2352-1791

VL - 19

SP - 510

EP - 515

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

ER -