Search Results - "'t Hoen, M. H. J."

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  1. 1

    Self-shielding of a plasma-exposed surface during extreme transient heat loads by Zielinski, J. J., van der Meiden, H. J., Morgan, T. W., 't Hoen, M. H. J., Schram, D. C., De Temmerman, G.

    Published in Applied physics letters (24-03-2014)
    “…The power deposition on a tungsten surface exposed to combined pulsed/continuous high power plasma is studied. A study of the correlation between the plasma…”
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    Journal Article
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    Strongly reduced penetration of atomic deuterium in radiation-damaged tungsten by 't Hoen, M H J, Mayer, M, Kleyn, A W, Zeijlmans van Emmichoven, P A

    Published in Physical review letters (27-11-2013)
    “…Radiation-damaged tungsten is exposed to high-flux, low-energy deuterium plasmas at self-bias conditions. We observe that the fraction of deuterium that…”
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  4. 4

    The effect of ion flux on plasma-induced modification and deuterium retention in tungsten and tungsten–tantalum alloys by Zayachuk, Y., Manhard, A., ‘t Hoen, M.H.J., Jacob, W., Zeijlmans van Emmichoven, P.A., Van Oost, G.

    Published in Journal of nuclear materials (01-09-2015)
    “…The paper presents the results of an experimental study of deuterium retention in W and W–Ta alloy that were exposed to first-wall relevant low flux…”
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  5. 5

    Deuterium retention and surface modifications of nanocrystalline tungsten films exposed to high-flux plasma by ‘t Hoen, M.H.J., Dellasega, D., Pezzoli, A., Passoni, M., Kleyn, A.W., Zeijlmans van Emmichoven, P.A.

    Published in Journal of nuclear materials (01-08-2015)
    “…•The films withstand the intense plasma exposure maintaining overall integrity.•An increase of deuterium retention was observed with decreasing tungsten…”
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    Hydrogen retention in tungsten materials studied by Laser Induced Desorption by Zlobinski, M., Philipps, V., Schweer, B., Huber, A., Reinhart, M., Möller, S., Sergienko, G., Samm, U., ’t Hoen, M.H.J., Manhard, A., Schmid, K.

    Published in Journal of nuclear materials (01-07-2013)
    “…Development of methods to characterise the first wall in ITER and future fusion devices without removal of wall tiles is important to support safety…”
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