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Laser re-melting of tungsten damaged by transient heat loads

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    0468205 - UFP-V 2017 RIV NL eng J - Journal Article
    Loewenhoff, Th. - Linke, J. - Matějíček, Jiří - Rasinski, M. - Vostřák, M. - Wirtz, M.
    Laser re-melting of tungsten damaged by transient heat loads.
    Nuclear Materials and Energy. Roč. 9, December (2016), s. 165-170. ISSN 2352-1791.
    [International Conference of Fusion Reactor Material (ICFRM-17) /17./. Aachen, 11.10.2015-16.10.2015]
    R&D Projects: GA ČR(CZ) GA14-12837S
    Institutional support: RVO:61389021
    Keywords : Plasma facing material * Laser surface remelting * Transient heat load * Tungsten
    Subject RIV: JG - Metallurgy
    http://dx.doi.org/10.1016/j.nme.2016.04.004

    In the current study, a solid state disc laser with a wavelength of 1030 nm and maximum power of 5.3 kW was used to melt the surface of pure tungsten samples (manufactured according to ITER specifications by Plansee SE). Several combinations of laser power and traverse velocity were tested, with the aim of eliminating any pre-existing cracks and forming a smooth and contiguous resolidified surface. Some of the samples were previously damaged by the electron beam simulation of 100 THLs of 0.38 GW/m² intensity (Δt = 1 ms) on a 4 × 4 mm² area in the JUDITH 1 facility. These conditions were chosen because the resulting damage (crack network) and the crack depth (∼200–300 µm) are known from previous identical material tests with subsequent cross sectioning. After laser melting, the samples were analyzed by SEM, laser profilometry and metallographic cross sectioning. A closed surface without cracks, an increased grain size and pronounced grain boundaries in the resolidified area were found. Profilometry proved that the surface height variations are within ±25 µm from the original surface height, meaning a very smooth surface was achieved. These results successfully demonstrate the possibility of repairing a cracked tungsten surface by laser surface re-melting. This “laser repair” could be used to extend the lifetime of future plasma facing components.
    Permanent Link: http://hdl.handle.net/11104/0266054