Publications
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Materials research under ITER-like divertor conditions at FOM Rijnhuizen, J. Nucl. Mater. 417 (2011) 457-462.
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TMAP7 simulations of deuterium trapping in pre-irradiated tungsten exposed to high-flux plasma, J. Nucl. Mater. 1415 (2011) S636-S640.
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Saturation of deuterium retention in self-damaged tungsten exposed to high-flux plasmas, Nucl. Fusion 52 (2012) 023008.
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Strongly Reduced Penetration of Atomic Deuterium in Radiation-Damaged Tungsten, Phys. Rev. Lett. 111 (2013) 225001.
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2013_54898.pdf (160.9 KB)
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First studies of ITER-diagnostic mirrors in a tokamak with an all-metal interior: results of the first mirror test in ASDEX Upgrade, Nucl. Fusion 753 (2013) 073033.
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Reduced deuterium retention in self-damaged tungsten exposed to high-flux plasmas at high surface temperatures, Nucl. Fusion 453 (2013) 043003.
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2013_52051.pdf (513.57 KB)
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Overview on plasma operation with a full tungsten wall in ASDEX Upgrade, J. Nucl. Mater. 438, Supplement (2013) S34-S41.
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Surface morphology and deuterium retention of tungsten after low- and high-flux deuterium plasma exposure, Nucl. Fusion 54 (2014) 083014.
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2014_57285.pdf (3.39 MB)
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Deuterium trapping and surface modification of polycrystalline tungsten exposed to a high-flux plasma at high fluences, Nucl. Fusion 57 (2017) 046004.
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The high-flux effect on deuterium retention in TiC and TaC doped tungsten at high temperatures, J. Nucl. Mater. 494 (2017) 211-218.
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Plasma–wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification, Nucl. Fusion 57 (2017) 116041.
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