Development of laser-based techniques for in situ characterization of the first wall in ITER and future fusion devices

V. Philipps, A. Malaquias, Antti Hakola, Juuso Karhunen, G. Maddaluno, S. Almaviva, L. Caneve, F. Colao, E. Fortuna, P. Gasior, M. Kubkowska, A. Czarnecka, M. Laan, A. Lissovski, P. Paris, H.J. van der Meiden, P. Petersson, M. Rubel, A. Huber, M. ZlobinskiB. Schweer, N. Gierse, Q. Xiao, G. Sergienko

Research output: Contribution to journalArticleScientificpeer-review

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Abstract

Analysis and understanding of wall erosion, material transport and fuel retention are among the most important tasks for ITER and future devices, since these questions determine largely the lifetime and availability of the fusion reactor. These data are also of extreme value to improve the understanding and validate the models of the in vessel build-up of the T inventory in ITER and future D–T devices. So far, research in these areas is largely supported by post-mortem analysis of wall tiles. However, access to samples will be very much restricted in the next-generation devices (such as ITER, JT-60SA, W7-X, etc) with actively cooled plasma-facing components (PFC) and increasing duty cycle.

This has motivated the development of methods to measure the deposition of material and retention of plasma fuel on the walls of fusion devices in situ, without removal of PFC samples. For this purpose, laser-based methods are the most promising candidates. Their feasibility has been assessed in a cooperative undertaking in various European associations under EFDA coordination. Different laser techniques have been explored both under laboratory and tokamak conditions with the emphasis to develop a conceptual design for a laser-based wall diagnostic which is integrated into an ITER port plug, aiming to characterize in situ relevant parts of the inner wall, the upper region of the inner divertor, part of the dome and the upper X-point region.
Original languageEnglish
Article number093002
JournalNuclear Fusion
Volume53
Issue number9
DOIs
Publication statusPublished - 2013
MoE publication typeA1 Journal article-refereed

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fusion
lasers
fusion reactors
tiles
plugs
domes
erosion
vessels
availability
life (durability)
cycles

Cite this

Philipps, V. ; Malaquias, A. ; Hakola, Antti ; Karhunen, Juuso ; Maddaluno, G. ; Almaviva, S. ; Caneve, L. ; Colao, F. ; Fortuna, E. ; Gasior, P. ; Kubkowska, M. ; Czarnecka, A. ; Laan, M. ; Lissovski, A. ; Paris, P. ; van der Meiden, H.J. ; Petersson, P. ; Rubel, M. ; Huber, A. ; Zlobinski, M. ; Schweer, B. ; Gierse, N. ; Xiao, Q. ; Sergienko, G. / Development of laser-based techniques for in situ characterization of the first wall in ITER and future fusion devices. In: Nuclear Fusion. 2013 ; Vol. 53, No. 9.
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abstract = "Analysis and understanding of wall erosion, material transport and fuel retention are among the most important tasks for ITER and future devices, since these questions determine largely the lifetime and availability of the fusion reactor. These data are also of extreme value to improve the understanding and validate the models of the in vessel build-up of the T inventory in ITER and future D–T devices. So far, research in these areas is largely supported by post-mortem analysis of wall tiles. However, access to samples will be very much restricted in the next-generation devices (such as ITER, JT-60SA, W7-X, etc) with actively cooled plasma-facing components (PFC) and increasing duty cycle.This has motivated the development of methods to measure the deposition of material and retention of plasma fuel on the walls of fusion devices in situ, without removal of PFC samples. For this purpose, laser-based methods are the most promising candidates. Their feasibility has been assessed in a cooperative undertaking in various European associations under EFDA coordination. Different laser techniques have been explored both under laboratory and tokamak conditions with the emphasis to develop a conceptual design for a laser-based wall diagnostic which is integrated into an ITER port plug, aiming to characterize in situ relevant parts of the inner wall, the upper region of the inner divertor, part of the dome and the upper X-point region.",
author = "V. Philipps and A. Malaquias and Antti Hakola and Juuso Karhunen and G. Maddaluno and S. Almaviva and L. Caneve and F. Colao and E. Fortuna and P. Gasior and M. Kubkowska and A. Czarnecka and M. Laan and A. Lissovski and P. Paris and {van der Meiden}, H.J. and P. Petersson and M. Rubel and A. Huber and M. Zlobinski and B. Schweer and N. Gierse and Q. Xiao and G. Sergienko",
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Philipps, V, Malaquias, A, Hakola, A, Karhunen, J, Maddaluno, G, Almaviva, S, Caneve, L, Colao, F, Fortuna, E, Gasior, P, Kubkowska, M, Czarnecka, A, Laan, M, Lissovski, A, Paris, P, van der Meiden, HJ, Petersson, P, Rubel, M, Huber, A, Zlobinski, M, Schweer, B, Gierse, N, Xiao, Q & Sergienko, G 2013, 'Development of laser-based techniques for in situ characterization of the first wall in ITER and future fusion devices', Nuclear Fusion, vol. 53, no. 9, 093002. https://doi.org/10.1088/0029-5515/53/9/093002

Development of laser-based techniques for in situ characterization of the first wall in ITER and future fusion devices. / Philipps, V.; Malaquias, A.; Hakola, Antti; Karhunen, Juuso; Maddaluno, G.; Almaviva, S.; Caneve, L.; Colao, F.; Fortuna, E.; Gasior, P.; Kubkowska, M.; Czarnecka, A.; Laan, M.; Lissovski, A.; Paris, P.; van der Meiden, H.J.; Petersson, P.; Rubel, M.; Huber, A.; Zlobinski, M.; Schweer, B.; Gierse, N.; Xiao, Q.; Sergienko, G.

In: Nuclear Fusion, Vol. 53, No. 9, 093002, 2013.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Development of laser-based techniques for in situ characterization of the first wall in ITER and future fusion devices

AU - Philipps, V.

AU - Malaquias, A.

AU - Hakola, Antti

AU - Karhunen, Juuso

AU - Maddaluno, G.

AU - Almaviva, S.

AU - Caneve, L.

AU - Colao, F.

AU - Fortuna, E.

AU - Gasior, P.

AU - Kubkowska, M.

AU - Czarnecka, A.

AU - Laan, M.

AU - Lissovski, A.

AU - Paris, P.

AU - van der Meiden, H.J.

AU - Petersson, P.

AU - Rubel, M.

AU - Huber, A.

AU - Zlobinski, M.

AU - Schweer, B.

AU - Gierse, N.

AU - Xiao, Q.

AU - Sergienko, G.

PY - 2013

Y1 - 2013

N2 - Analysis and understanding of wall erosion, material transport and fuel retention are among the most important tasks for ITER and future devices, since these questions determine largely the lifetime and availability of the fusion reactor. These data are also of extreme value to improve the understanding and validate the models of the in vessel build-up of the T inventory in ITER and future D–T devices. So far, research in these areas is largely supported by post-mortem analysis of wall tiles. However, access to samples will be very much restricted in the next-generation devices (such as ITER, JT-60SA, W7-X, etc) with actively cooled plasma-facing components (PFC) and increasing duty cycle.This has motivated the development of methods to measure the deposition of material and retention of plasma fuel on the walls of fusion devices in situ, without removal of PFC samples. For this purpose, laser-based methods are the most promising candidates. Their feasibility has been assessed in a cooperative undertaking in various European associations under EFDA coordination. Different laser techniques have been explored both under laboratory and tokamak conditions with the emphasis to develop a conceptual design for a laser-based wall diagnostic which is integrated into an ITER port plug, aiming to characterize in situ relevant parts of the inner wall, the upper region of the inner divertor, part of the dome and the upper X-point region.

AB - Analysis and understanding of wall erosion, material transport and fuel retention are among the most important tasks for ITER and future devices, since these questions determine largely the lifetime and availability of the fusion reactor. These data are also of extreme value to improve the understanding and validate the models of the in vessel build-up of the T inventory in ITER and future D–T devices. So far, research in these areas is largely supported by post-mortem analysis of wall tiles. However, access to samples will be very much restricted in the next-generation devices (such as ITER, JT-60SA, W7-X, etc) with actively cooled plasma-facing components (PFC) and increasing duty cycle.This has motivated the development of methods to measure the deposition of material and retention of plasma fuel on the walls of fusion devices in situ, without removal of PFC samples. For this purpose, laser-based methods are the most promising candidates. Their feasibility has been assessed in a cooperative undertaking in various European associations under EFDA coordination. Different laser techniques have been explored both under laboratory and tokamak conditions with the emphasis to develop a conceptual design for a laser-based wall diagnostic which is integrated into an ITER port plug, aiming to characterize in situ relevant parts of the inner wall, the upper region of the inner divertor, part of the dome and the upper X-point region.

U2 - 10.1088/0029-5515/53/9/093002

DO - 10.1088/0029-5515/53/9/093002

M3 - Article

VL - 53

JO - Nuclear Fusion

JF - Nuclear Fusion

SN - 0029-5515

IS - 9

M1 - 093002

ER -