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Characterization of laser-irradiated co-deposited layers on plasma facing components from a tokamak
Vise andre og tillknytning
2006 (engelsk)Inngår i: Physica Scripta, ISSN 0031-8949, E-ISSN 1402-4896, Vol. T123, s. 99-103Artikkel i tidsskrift (Fagfellevurdert) Published
Abstract [en]

An experimental setup and ion diagnostic method for laser-induced fuel removal and decomposition of co-deposited layers on plasma facing components from tokamaks are described. Nd:YAG 3.5 ns pulse laser with a repetition rate of 10 Hz and single-pulse energy of up to 0.8J at 1.06 mu m has been used for irradiation of a graphite limiter tile from the TEXTOR tokamak. Comparative studies have been performed for a pure graphite plate as a reference target. Energy of emitted ions has been measured using a time-of-flight method. Early results show that laser pulses efficiently ablate the co-deposit removing both fuel species and heavy components such as Si, Ni, Cr, Fe and W present in the layers. Surface topography of the irradiated targets is also presented.

sted, utgiver, år, opplag, sider
2006. Vol. T123, s. 99-103
Emneord [en]
tritium retention, jet, removal, tftr, codeposits, composite, divertor, tiles
HSV kategori
Identifikatorer
URN: urn:nbn:se:kth:diva-15618DOI: 10.1088/0031-8949/2006/T123/013ISI: 000236918600014Scopus ID: 2-s2.0-33750701403OAI: oai:DiVA.org:kth-15618DiVA, id: diva2:333660
Merknad
QC 20100525 QC 20111003. Conference: 5th International Workshop and Summer School on Plasma Physics. POLAND. JUN 06-10, 2005 Tilgjengelig fra: 2010-08-05 Laget: 2010-08-05 Sist oppdatert: 2017-12-12bibliografisk kontrollert

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