Publications of T. Schwarz-Selinger
All genres
Journal Article (205)
41.
Journal Article
97, 024006 (2022)
The synergies between displacement damage creation and hydrogen presence: the effect of D ion energy and flux. Physica Scripta 42.
Journal Article
62, 042013 (2022)
Latest results of Eurofusion plasma-facing components research in the areas of power loading, material erosion and fuel retention. Nuclear Fusion 43.
Journal Article
30, 101093 (2022)
Irradiation effects in tungsten – from surface effects to bulk mechanical properties. Nuclear Materials and Energy 44.
Journal Article
62, 036012 (2022)
Reduced defect recovery in self-ion damaged W due to simultaneous deuterium exposure during annealing. Nuclear Fusion 45.
Journal Article
62, 042006 (2022)
Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development. Nuclear Fusion 46.
Journal Article
559, 153449 (2022)
Suppression of vacancy formation and hydrogen isotope retention in irradiated tungsten by addition of chromium. Journal of Nuclear Materials 47.
Journal Article
62, 096003 (2022)
Dislocation structure of tungsten irradiated by medium to high-mass ions. Nuclear Fusion 48.
Journal Article
162, 112100 (2021)
Tritium retention in displacement-damaged tungsten exposed to deuterium-tritium gas mixture at elevated temperatures. Fusion Engineering and Design 49.
Journal Article
174, 110991 (2021)
Microstructure evolution in helium implanted self-irradiated tungsten annealed at 1700 K studied by TEM. Materials Characterization 50.
Journal Article
27, 100994 (2021)
Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials. Nuclear Materials and Energy 51.
Journal Article
61, 116006 (2021)
Gross and net erosion balance of plasma-facing materials in full-W tokamaks. Nuclear Fusion 52.
Journal Article
555, 153135 (2021)
Influence of surface roughness on the sputter yield of Mo under keV D ion irradiation. Journal of Nuclear Materials 53.
Journal Article
27, 100991 (2021)
Influence of thin tungsten oxide films on hydrogen isotope uptake and retention in tungsten – Evidence for permeation barrier effect. Nuclear Materials and Energy 54.
Journal Article
5, 095403 (2021)
Parameter-free quantitative simulation of high-dose microstructure and hydrogen retention in ion-irradiated tungsten. Physical Review Materials 55.
Journal Article
550, 152947 (2021)
Experiments and modelling of multiple sequential MeV ion irradiations and deuterium exposures in tungsten. Journal of Nuclear Materials 56.
Journal Article
545, 152749 (2021)
Deuterium retention in W and binary W alloys irradiated with high energy Fe ions. Journal of Nuclear Materials 57.
Journal Article
61, 056003 (2021)
Dependence of blistering and deuterium retention on damage depth in damaged tungsten exposed to deuterium plasma. Nuclear Fusion 58.
Journal Article
96, 124042 (2021)
Penetration of deuterium into neutron-irradiated tungsten under plasma exposure. Physica Scripta 59.
Journal Article
555, 153139 (2021)
Deuterium retention in MeV ion-irradiated beryllium. Journal of Nuclear Materials 60.
Journal Article
60, 106011 (2020)
Kinetic model for hydrogen absorption in tungsten with coverage dependent surface mechanisms. Nuclear Fusion