Laser-induced removal of co-deposits from graphitic plasma-facing components: Characterization of irradiated surfaces and dust particles

被引：16

作者：

Gasior, P. ^{[1
]}

Irrek, F. ^{[2
]}

Petersson, P. ^{[3
]}

Penkalla, Hj. ^{[2
]}

Rubel, M. ^{[4
]}

Schweer, B. ^{[2
]}

Sundelin, P. ^{[4
]}

Wessel, E. ^{[2
]}

Linke, J. ^{[2
]}

Philipps, V. ^{[2
]}

Emmoth, B. ^{[5
]}

Wolowski, J. ^{[2
]}

Hirai, T. ^{[2
]}

机构：

[1] Assoc EURATOM IPPLM, Inst Plasma Phys & Laser Microfus, PL-00908 Warsaw, Poland

[2] Forschungszentrum Julich, Assoc EURATOM FZJ, IEF 4, D-52425 Julich, Germany

[3] Uppsala Univ, Angstrom Lab, Assoc EURATOM VR, S-75120 Uppsala, Sweden

[4] Royal Inst Technol, Alfven Lab, Assoc EURATOM VR, S-10044 Stockholm, Sweden

[5] KTH, Sch Commun & Informat Technol, Assoc EURATOM VR, S-16440 Kista, Sweden

来源：

JOURNAL OF NUCLEAR MATERIALS | 2009年 / 390-91卷

关键词：

EXCIMER-LASER; LAYERS; TRITIUM; TILES; TOKAMAK; JET; CODEPOSITS; DEUTERIUM; DEVICES; TFTR;

D O I：

10.1016/j.jnucmat.2009.01.115

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Laser-induced fuel desorption and ablation of co-deposited layers on limiter plates from the TEXTOR tokamak have been studied. Gas phase composition was monitored in situ, whereas the ex situ studies have been focused on the examination of irradiated surfaces and broad analysis of dust generated by ablation of co-deposits. The size of the dust grains is in the range of few nanometers to hundreds of micrometers. These are fuel-rich dust particles, as determined by nuclear reaction analysis. The presence of deuterium in dust indicates that not all fuel species are transferred to the gas phase during irradiation. This also suggests that photonic removal of fuel and the ablation of co-deposit from plasma-facing components may lead to the redistribution of fuel-containing dust to surrounding areas. (C) 2009 Elsevier B.V. All rights reserved.

引用

页码：585 / 588

页数：4

共 18 条

[1] Tritium retention in next step devices and the requirements for mitigation and removal techniques [J].

Counsell, G. ;

Coad, P. ;

Grisola, C. ;

Hopf, C. ;

Jacob, W. ;

Kirschner, A. ;

Kreter, A. ;

Krieger, K. ;

Likonen, J. ;

Philipps, V. ;

Roth, J. ;

Rubel, M. ;

Salancon, E. ;

Semerok, A. ;

Tabares, F. L. ;

Widdowson, A. .

PLASMA PHYSICS AND CONTROLLED FUSION, 2006, 48 (12B) :B189-B199

[2] Fuel removal from bumper limiter tiles by using a pulsed excimer laser [J].

Emmoth, B ;

Khartsev, S ;

Pisarev, A ;

Grishin, A ;

Karlsson, U ;

Litnovsky, A ;

Rubel, M ;

Wienhold, P .

JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) :639-643

[3] Characterization of laser-irradiated co-deposited layers on plasma facing components from a tokamak [J].

Gasior, P. ;

Badziak, J. ;

Czarnecka, A. ;

Parys, P. ;

Wolowski, J. ;

Rosinski, M. ;

Rubel, M. ;

Philipps, V. .

PHYSICA SCRIPTA, 2006, T123 :99-103

[4] Effective laser-induced removal of co-deposited layers from plasma-facing components in a tokamak [J].

Gasior, P. ;

Czarnecka, A. ;

Parys, P. ;

Rosinski, M. ;

Wolowski, J. ;

Hoffman, J. ;

Szymanski, Z. ;

Philipps, V. ;

Rubel, M. .

CZECHOSLOVAK JOURNAL OF PHYSICS, 2006, 56 :B67-B72

[5] In-situ tokamak laser applications for detritiation and co-deposited layers studies [J].

Grisolia, C. ;

Semerok, A. ;

Weulersse, J. M. ;

Le Guern, F. ;

Fomichev, S. ;

Brygo, F. ;

Fichet, P. ;

Thro, P. Y. ;

Coad, P. ;

Bekris, N. ;

Stamp, M. ;

Rosanvallon, S. ;

Piazza, G. .

JOURNAL OF NUCLEAR MATERIALS, 2007, 363 :1138-1147

[6] Deuterium retention in different carbon materials exposed in TEXTOR [J].

Kreter, A. ;

Brezinsek, S. ;

Rubel, M. ;

Emmoth, B. ;

Freisinger, M. ;

Pelicon, P. ;

Philipps, V. ;

Schmitz, O. ;

Sundelin, P. ;

Sergienko, G. .

PROCEEDINGS OF THE 17TH INTERNATIONAL VACUUM CONGRESS/13TH INTERNATIONAL CONFERENCE ON SURFACE SCIENCE/INTERNATIONAL CONFERENCE ON NANOSCIENCE AND TECHNOLOGY, 2008, 100

[7]

Le Guern F., 2004, J NUCL MATER, V335

[8]

Le Guern F., 2006, FUS ENG DES, V81, P8

[9] DEPOSITION AND IN-DEPTH PENETRATION OF DEUTERIUM IN CARBON-FIBER COMPOSITES [J].

RUBEL, M ;

EMMOTH, B ;

BERGSAKER, H ;

WIENHOLD, P ;

DUNAEV, V ;

SUKHOMLINOV, V .

JOURNAL OF NUCLEAR MATERIALS, 1992, 196 :285-291

[10] Thick co-deposits and dust in controlled fusion devices with carbon walls: Fuel inventory and growth rate of co-deposited layers [J].

Rubel, M ;

Philipps, V ;

Tanabe, T ;

Wienhold, P ;

Freisinger, M ;

Linke, J ;

von Seggern, J ;

Wessel, E .

PHYSICA SCRIPTA, 2003, T103 :20-24

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