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000864234 0247_ $$2doi$$a10.1016/j.nme.2019.04.007
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000864234 1001_ $$0P:(DE-Juel1)172037$$aZlobinski, M.$$b0$$eCorresponding author
000864234 245__ $$aLaser-Induced Desorption of co-deposited Deuterium in Beryllium Layers on Tungsten
000864234 260__ $$aAmsterdam [u.a.]$$bElsevier$$c2019
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000864234 520__ $$aFor the development of the tritium monitoring system in ITER the hydrogen isotope release by Laser-Induced Desorption (LID) from Be layers is studied to determine the laser parameters for a high desorption efficiency while minimising dust production and surface modifications is also pursued. Be layers of 1 µm thickness with 25–30 at% D and 3 × 1022 D/m2 comparable to JET-ILW areal concentrations [1] have been produced by High Power Impulse Magnetron Sputtering (HiPIMS) on ITER grade W. Laser pulses of 1, 5 and 10 ms duration heat the layer in vacuum in the Fuel REtention DIagnostic Setup (FREDIS) and release the retained D thermally. By mass spectrometry in FREDIS and subsequent Nuclear Reaction Analysis (NRA) inside the laser spot the desorbed and remaining D is quantified. While a pulse duration of 1 ms cannot fully desorb the deuterium, it is found that a single 5 or 10 ms laser pulse with an absorbed energy density of ca. 1.5 MJ/m2 corresponding to a heat flux factor around 20 MW√s/m2 leads to nearly complete desorption of the retained D. This encourages the development of a useful tritium monitoring system, although the present layers produce some dust due to local delamination of the layer on at least 11% of the heated surface (at 1.4 MJ/m2 absorbed energy within 5 ms) and lead to unavoidable crack formation.
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000864234 7001_ $$0P:(DE-Juel1)130158$$aSergienko, G.$$b1
000864234 7001_ $$0P:(DE-Juel1)167463$$aMartynova, Y.$$b2$$ufzj
000864234 7001_ $$0P:(DE-Juel1)8998$$aMatveev, D.$$b3$$ufzj
000864234 7001_ $$0P:(DE-Juel1)6784$$aUnterberg, B.$$b4$$ufzj
000864234 7001_ $$0P:(DE-Juel1)129976$$aBrezinsek, S.$$b5
000864234 7001_ $$0P:(DE-Juel1)159558$$aSpilker, B.$$b6
000864234 7001_ $$0P:(DE-Juel1)130112$$aNicolai, D.$$b7
000864234 7001_ $$0P:(DE-Juel1)162160$$aRasinski, M.$$b8$$ufzj
000864234 7001_ $$0P:(DE-Juel1)139534$$aMöller, S.$$b9
000864234 7001_ $$0P:(DE-Juel1)157640$$aLinsmeier, Ch.$$b10
000864234 7001_ $$0P:(DE-HGF)0$$aLungu, C. P.$$b11
000864234 7001_ $$0P:(DE-HGF)0$$aPorosnicu, C.$$b12
000864234 7001_ $$0P:(DE-HGF)0$$aDinca, P.$$b13
000864234 7001_ $$0P:(DE-HGF)0$$aDe Temmerman, G.$$b14
000864234 773__ $$0PERI:(DE-600)2808888-8$$a10.1016/j.nme.2019.04.007$$gVol. 19, p. 503 - 509$$p503 - 509$$tNuclear materials and energy$$v19$$x2352-1791$$y2019
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