Simulations of tungsten transport in the edge of JET ELMy H-mode plasmas

A. Järvinen; M. Groth; D. Moulton; J. Strachan; S. Wiesen; P. Belo; M. N.A. Beurskens; G. Corrigan; T. Eich; C. Giroud; E. Havlickova; S. Jachmich; M. Lehnen; J. Lönnroth; D. Tskhakaya

doi:10.1016/j.jnucmat.2013.01.219

Simulations of tungsten transport in the edge of JET ELMy H-mode plasmas

A. Järvinen^*
, M. Groth
, D. Moulton
, J. Strachan
, S. Wiesen
, P. Belo
, M. N.A. Beurskens
, G. Corrigan
, T. Eich
, C. Giroud
, E. Havlickova
, S. Jachmich
, M. Lehnen
, J. Lönnroth
, D. Tskhakaya

^*Corresponding author for this work

Not published at VTT

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

18 Citations (Scopus)

Abstract

Tungsten contamination can significantly impact the performance of future fusion reactors via fuel dilution and radiation in the plasma centre. Therefore, understanding tungsten sputtering and divertor retention is essential for optimising the core performance in tokamaks operating with tungsten. This study investigates these issues numerically in JET high-triangularity, type-I ELMy H-mode plasmas with the Monte-Carlo code DIVIMP used on background plasmas dynamically evolved with the multi-fluid code EDGE2D/EIRENE. During the ELM, the simulations show target temperatures in excess of a few 100 eV, causing two orders of magnitude increase in the tungsten core contamination rate. During the ELM recovery, target densities of five times the pre-ELM values are obtained at the low field side, which strongly enhance divertor retention via increased friction with the main ions. Therefore, the core contamination is determined here dominantly by the intra-ELM divertor plasma characteristics.

Original language	English
Pages (from-to)	S1005-S1009
Journal	Journal of Nuclear Materials
Volume	438
Issue number	SUPPL
DOIs	https://doi.org/10.1016/j.jnucmat.2013.01.219
Publication status	Published - 2013
MoE publication type	A1 Journal article-refereed

Funding

This work, supported by the European Communities under the contract of association between EURATOM/TEKES was carried out within the framework of the European Fusion Development Agreement. The views and opinions expressed herein do not necessarily reflect those of the European Commission. The work was also partly funded by the Academy of Finland under the Grant number 13253222.

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 7 Affordable and Clean Energy

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10.1016/j.jnucmat.2013.01.219

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Järvinen, A., Groth, M., Moulton, D., Strachan, J., Wiesen, S., Belo, P., Beurskens, M. N. A., Corrigan, G., Eich, T., Giroud, C., Havlickova, E., Jachmich, S., Lehnen, M., Lönnroth, J., & Tskhakaya, D. (2013). Simulations of tungsten transport in the edge of JET ELMy H-mode plasmas. Journal of Nuclear Materials, 438(SUPPL), S1005-S1009. https://doi.org/10.1016/j.jnucmat.2013.01.219

@article{678d15e1547d4ddf96338b8f01ff913d,

title = "Simulations of tungsten transport in the edge of JET ELMy H-mode plasmas",

abstract = "Tungsten contamination can significantly impact the performance of future fusion reactors via fuel dilution and radiation in the plasma centre. Therefore, understanding tungsten sputtering and divertor retention is essential for optimising the core performance in tokamaks operating with tungsten. This study investigates these issues numerically in JET high-triangularity, type-I ELMy H-mode plasmas with the Monte-Carlo code DIVIMP used on background plasmas dynamically evolved with the multi-fluid code EDGE2D/EIRENE. During the ELM, the simulations show target temperatures in excess of a few 100 eV, causing two orders of magnitude increase in the tungsten core contamination rate. During the ELM recovery, target densities of five times the pre-ELM values are obtained at the low field side, which strongly enhance divertor retention via increased friction with the main ions. Therefore, the core contamination is determined here dominantly by the intra-ELM divertor plasma characteristics.",

author = "A. J{\"a}rvinen and M. Groth and D. Moulton and J. Strachan and S. Wiesen and P. Belo and Beurskens, \{M. N.A.\} and G. Corrigan and T. Eich and C. Giroud and E. Havlickova and S. Jachmich and M. Lehnen and J. L{\"o}nnroth and D. Tskhakaya",

note = "Funding Information: This work, supported by the European Communities under the contract of association between EURATOM/TEKES was carried out within the framework of the European Fusion Development Agreement. The views and opinions expressed herein do not necessarily reflect those of the European Commission. The work was also partly funded by the Academy of Finland under the Grant number 13253222.",

year = "2013",

doi = "10.1016/j.jnucmat.2013.01.219",

language = "English",

volume = "438",

pages = "S1005--S1009",

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Järvinen, A, Groth, M, Moulton, D, Strachan, J, Wiesen, S, Belo, P, Beurskens, MNA, Corrigan, G, Eich, T, Giroud, C, Havlickova, E, Jachmich, S, Lehnen, M, Lönnroth, J & Tskhakaya, D 2013, 'Simulations of tungsten transport in the edge of JET ELMy H-mode plasmas', Journal of Nuclear Materials, vol. 438, no. SUPPL, pp. S1005-S1009. https://doi.org/10.1016/j.jnucmat.2013.01.219

TY - JOUR

T1 - Simulations of tungsten transport in the edge of JET ELMy H-mode plasmas

AU - Järvinen, A.

AU - Groth, M.

AU - Moulton, D.

AU - Strachan, J.

AU - Wiesen, S.

AU - Belo, P.

AU - Beurskens, M. N.A.

AU - Corrigan, G.

AU - Eich, T.

AU - Giroud, C.

AU - Havlickova, E.

AU - Jachmich, S.

AU - Lehnen, M.

AU - Lönnroth, J.

AU - Tskhakaya, D.

N1 - Funding Information: This work, supported by the European Communities under the contract of association between EURATOM/TEKES was carried out within the framework of the European Fusion Development Agreement. The views and opinions expressed herein do not necessarily reflect those of the European Commission. The work was also partly funded by the Academy of Finland under the Grant number 13253222.

PY - 2013

Y1 - 2013

N2 - Tungsten contamination can significantly impact the performance of future fusion reactors via fuel dilution and radiation in the plasma centre. Therefore, understanding tungsten sputtering and divertor retention is essential for optimising the core performance in tokamaks operating with tungsten. This study investigates these issues numerically in JET high-triangularity, type-I ELMy H-mode plasmas with the Monte-Carlo code DIVIMP used on background plasmas dynamically evolved with the multi-fluid code EDGE2D/EIRENE. During the ELM, the simulations show target temperatures in excess of a few 100 eV, causing two orders of magnitude increase in the tungsten core contamination rate. During the ELM recovery, target densities of five times the pre-ELM values are obtained at the low field side, which strongly enhance divertor retention via increased friction with the main ions. Therefore, the core contamination is determined here dominantly by the intra-ELM divertor plasma characteristics.

AB - Tungsten contamination can significantly impact the performance of future fusion reactors via fuel dilution and radiation in the plasma centre. Therefore, understanding tungsten sputtering and divertor retention is essential for optimising the core performance in tokamaks operating with tungsten. This study investigates these issues numerically in JET high-triangularity, type-I ELMy H-mode plasmas with the Monte-Carlo code DIVIMP used on background plasmas dynamically evolved with the multi-fluid code EDGE2D/EIRENE. During the ELM, the simulations show target temperatures in excess of a few 100 eV, causing two orders of magnitude increase in the tungsten core contamination rate. During the ELM recovery, target densities of five times the pre-ELM values are obtained at the low field side, which strongly enhance divertor retention via increased friction with the main ions. Therefore, the core contamination is determined here dominantly by the intra-ELM divertor plasma characteristics.

UR - https://www.scopus.com/pages/publications/84885426362

U2 - 10.1016/j.jnucmat.2013.01.219

DO - 10.1016/j.jnucmat.2013.01.219

M3 - Article

AN - SCOPUS:84885426362

SN - 0022-3115

VL - 438

SP - S1005-S1009

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - SUPPL

ER -

Simulations of tungsten transport in the edge of JET ELMy H-mode plasmas

Abstract

Funding

UN SDGs

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