Hauptseite > Publikationsdatenbank > Laser-Induced Desorption of co-deposited Deuterium in Beryllium Layers on Tungsten > print

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024 7 _ |a 10.1016/j.nme.2019.04.007
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100 1 _ |a Zlobinski, M.
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245 _ _ |a Laser-Induced Desorption of co-deposited Deuterium in Beryllium Layers on Tungsten
260 _ _ |a Amsterdam [u.a.]
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520 _ _ |a For the development of the tritium monitoring system in ITER the hydrogen isotope release by Laser-Induced Desorption (LID) from Be layers is studied to determine the laser parameters for a high desorption efficiency while minimising dust production and surface modifications is also pursued. Be layers of 1 µm thickness with 25–30 at% D and 3 × 1022 D/m2 comparable to JET-ILW areal concentrations [1] have been produced by High Power Impulse Magnetron Sputtering (HiPIMS) on ITER grade W. Laser pulses of 1, 5 and 10 ms duration heat the layer in vacuum in the Fuel REtention DIagnostic Setup (FREDIS) and release the retained D thermally. By mass spectrometry in FREDIS and subsequent Nuclear Reaction Analysis (NRA) inside the laser spot the desorbed and remaining D is quantified. While a pulse duration of 1 ms cannot fully desorb the deuterium, it is found that a single 5 or 10 ms laser pulse with an absorbed energy density of ca. 1.5 MJ/m2 corresponding to a heat flux factor around 20 MW√s/m2 leads to nearly complete desorption of the retained D. This encourages the development of a useful tritium monitoring system, although the present layers produce some dust due to local delamination of the layer on at least 11% of the heated surface (at 1.4 MJ/m2 absorbed energy within 5 ms) and lead to unavoidable crack formation.
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700 1 _ |a Sergienko, G.
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700 1 _ |a Martynova, Y.
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700 1 _ |a Matveev, D.
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700 1 _ |a Unterberg, B.
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700 1 _ |a Brezinsek, S.
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700 1 _ |a Spilker, B.
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700 1 _ |a Nicolai, D.
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700 1 _ |a Rasinski, M.
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700 1 _ |a Möller, S.
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700 1 _ |a Linsmeier, Ch.
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700 1 _ |a Porosnicu, C.
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700 1 _ |a De Temmerman, G.
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773 _ _ |a 10.1016/j.nme.2019.04.007
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