Publications of T. Schwarz-Selinger
All genres
Journal Article (189)
2023
Journal Article
63, 026005 (2023)
Dislocation structure of tungsten irradiated by light ions. Nuclear Fusion 2022
Journal Article
30, 101118 (2022)
Comparison experiment on the sputtering of EUROFER, RUSFER and CLAM steels by deuterium ions. Nuclear Materials and Energy
Journal Article
30, 101137 (2022)
Influence of thin surface oxide films on hydrogen isotope release from ion-irradiated tungsten. Nuclear Materials and Energy
Journal Article
97, 024006 (2022)
The synergies between displacement damage creation and hydrogen presence: the effect of D ion energy and flux. Physica Scripta
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
Journal Article
30, 101093 (2022)
Irradiation effects in tungsten – from surface effects to bulk mechanical properties. Nuclear Materials and Energy
Journal Article
62, 036012 (2022)
Reduced defect recovery in self-ion damaged W due to simultaneous deuterium exposure during annealing. Nuclear Fusion
Journal Article
62, 042006 (2022)
Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development. Nuclear Fusion
Journal Article
559, 153449 (2022)
Suppression of vacancy formation and hydrogen isotope retention in irradiated tungsten by addition of chromium. Journal of Nuclear Materials
Journal Article
62, 096003 (2022)
Dislocation structure of tungsten irradiated by medium to high-mass ions. Nuclear Fusion 2021
Journal Article
162, 112100 (2021)
Tritium retention in displacement-damaged tungsten exposed to deuterium-tritium gas mixture at elevated temperatures. Fusion Engineering and Design
Journal Article
174, 110991 (2021)
Microstructure evolution in helium implanted self-irradiated tungsten annealed at 1700 K studied by TEM. Materials Characterization
Journal Article
27, 100994 (2021)
Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials. Nuclear Materials and Energy
Journal Article
61, 116006 (2021)
Gross and net erosion balance of plasma-facing materials in full-W tokamaks. Nuclear Fusion
Journal Article
555, 153135 (2021)
Influence of surface roughness on the sputter yield of Mo under keV D ion irradiation. Journal of Nuclear Materials
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
Journal Article
5, 095403 (2021)
Parameter-free quantitative simulation of high-dose microstructure and hydrogen retention in ion-irradiated tungsten. Physical Review Materials
Journal Article
550, 152947 (2021)
Experiments and modelling of multiple sequential MeV ion irradiations and deuterium exposures in tungsten. Journal of Nuclear Materials
Journal Article
545, 152749 (2021)
Deuterium retention in W and binary W alloys irradiated with high energy Fe ions. Journal of Nuclear Materials
Journal Article
61, 056003 (2021)
Dependence of blistering and deuterium retention on damage depth in damaged tungsten exposed to deuterium plasma. Nuclear Fusion