Publications of T. Schwarz-Selinger
All genres
Journal Article (203)
61.
Journal Article
60, 126034 (2020)
Blister-dominated retention mechanism in tungsten exposed to high-fluence deuterium plasma. Nuclear Fusion 62.
Journal Article
60, 126044 (2020)
Tungsten heavy alloy: an alternative plasma-facing material in terms of hydrogen isotope retention. Nuclear Fusion 63.
Journal Article
60, 106007 (2020)
Deuterium retention in solid and liquid tin after low-temperature plasma exposure. Nuclear Fusion 64.
Journal Article
60, 106029 (2020)
Deuterium transport and retention in the bulk of tungsten containing helium: the effect of helium concentration and microstructure. Nuclear Fusion 65.
Journal Article
2020 (T171), 014065 (2020)
ITER monoblock performance under lifetime loading conditions in Magnum-PSI. Physica Scripta 66.
Journal Article
539, 152321 (2020)
Gamma-ray irradiation effect on deuterium retention in reduced activation ferritic/martensitic steel and ceramic coatings. Journal of Nuclear Materials 67.
Journal Article
60, 036024 (2020)
New rate equation model to describe the stabilization of displacement damage by hydrogen atoms during ion irradiation in tungsten. Nuclear Fusion 68.
Journal Article
60, 106028 (2020)
Effect of D on the evolution of radiation damage in W during high temperature annealing. Nuclear Fusion 69.
Journal Article
60, 096002 (2020)
Deuterium retention in tungsten irradiated by different ions. Nuclear Fusion 70.
Journal Article
478, pp. 56 - 61 (2020)
Cross section of 15N-2D nuclear reactions from 3.3 to 7.0 MeV for simultaneous hydrogen and deuterium quantitation in surface layers with 15N ion beams. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 71.
Journal Article
18, pp. 72 - 76 (2019)
Angle-dependent sputter yield measurements of keV D ions on W and Fe and comparison with SDTrimSP and SDTrimSP-3D. Nuclear Materials and Energy 72.
Journal Article
19, pp. 403 - 410 (2019)
Tritium retention in W plasma-facing materials: Impact of the material structure and helium irradiation. Nuclear Materials and Energy 73.
Journal Article
154, pp. 1 - 6 (2019)
TEM investigation of the influence of dose rate on radiation damage and deuterium retention in tungsten. Materials Characterization 74.
Journal Article
146, Pt. A, pp. 242 - 245 (2019)
Erosion and deposition investigations on Wendelstein 7-X first wall components for the first operation phase in divertor configuration. Fusion Engineering and Design 75.
Journal Article
450, pp. 13 - 18 (2019)
Experimental determination of the 16O(3He,p0)18F differential cross section. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 76.
Journal Article
59, 016011 (2019)
Stabilization of defects by the presence of hydrogen in tungsten: simultaneous W-ion damaging and D-atom exposure. Nuclear Fusion 77.
Journal Article
18, pp. 245 - 249 (2019)
Deuterium retention in tungsten based materials for fusion applications. Nuclear Materials and Energy 78.
Journal Article
59, 086050 (2019)
Displacement damage stabilization by hydrogen presence under simultaneous W ion damage and D ion exposure. Nuclear Fusion 79.
Journal Article
59, 112014 (2019)
Overview of physics studies on ASDEX Upgrade. Nuclear Fusion 80.
Journal Article
513, pp. 198 - 208 (2019)
Influence of grain size on deuterium transport and retention in self-damaged tungsten. Journal of Nuclear Materials