Publikationen von T. Schwarz-Selinger
Alle Typen
Vortrag (215)
221.
Vortrag
Experimental Investigation of Fast Low-Temperature Irradiation Creep – A Novel Experiment for Materials Testing under Extreme Conditions. 19th European Mechanics of Materials Conference (EMMC19), Madrid (eingereicht)
222.
Vortrag
Studies of deuterium retention in pre-damaged tungsten with laser-induced ablation quadrupole mass spectrometry. DPG-Frühjahrstagung 2024, Greifswald (2024)
223.
Vortrag
Depth-resolved deuterium retention profiles in displacement-damaged tungsten with laser-induced ablation quadrupole mass spectrometry. DPG-Frühjahrstagung der Sektion Materie und Kosmos (SMuK), Göttingen (eingereicht)
224.
Vortrag
Validating multiscale models of highly irradiated metals: from thermal desorption spectroscopy to transmission electron microscopy. 11th International Conference on Multiscale Materials Modeling (MMM11), Prague (eingereicht)
225.
Vortrag
The role of ion beam analysis in fusion research. International Conference Applied Nuclear Physics 2024 (ANP 2024), Thessaloniki (2024)
226.
Vortrag
State-of-the-art femtosecond LIA-QMS for the detection of trapped deuterium and helium in plasma-facing materials. 13th International Meeting & 2nd Latin American Meeting on Laser Induced Breakdown Spectroscopy (LIBS XIII & LAM LIBS II), Iguazu (eingereicht)
227.
Vortrag
GIRAFFE – In Situ Material Tests under Fusion‐Relevant Conditions. TMS 2025 154th Annual Meeting & Exhibition, Las Vegas, NV (eingereicht)
228.
Vortrag
Deuterium retention in tungsten, self-ion irradiated at elevated temperature. 17th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-17), Chamonix (eingereicht)
229.
Vortrag
Deuterium retention in EUROFER after gas and plasma loading. 17th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-17), Chamonix (eingereicht)
230.
Vortrag
Deuterium retention analysis in pre-damaged tungsten using laser-induced breakdown spectroscopy. DPG-Frühjahrstagung 2024, Greifswald (2024)
231.
Vortrag
Deuterium retention in self-ion irradiated tungsten: influence of irradiation temperature, damage dose, and alloying elements. The Decennial IAEA Technical Meeting on Atomic, Molecular and Plasma-Material Interaction Data for Fusion Science and Technology (AMPMI 2024), Helsinki (eingereicht)
232.
Vortrag
Plasma-Wall Interaction studies towards realizing a DEMO fusion reactor. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (eingereicht)
233.
Vortrag
Irradiation-Induced Stress Relaxation in Plasma-Facing Materials – An In-situ Investigation on Thin Tungsten Wires. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (eingereicht)
234.
Vortrag
Is stable Frenkel pair formation necessary for H irradiation-induced lattice damage? 19th International Conference on Diffusion in Solids and Liquids (DSL 2022), Heraklion (eingereicht)
235.
Vortrag
12C(3He,px)14N and 13C(3He,px)15N Cross- Sections for Nuclear Reaction Analysis at Energies up to 6 MeV. 2nd Research Coordination Meeting of the CRP on "Development and Application of Ion Beam Techniques for Materials Irradiation and Characterization relevant to Fusion Technology", Zagreb (eingereicht)
236.
Vortrag
Analysis of radiation effects in tungsten by comparing molecular dynamics simulations to experiments of RBS-Channeling. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (eingereicht)
237.
Vortrag
Helium retention and helium depth distribution in displacement-damaged tungsten. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (eingereicht)
238.
Vortrag
Liquid tin interaction with deuterium plasmas. 49th EPS Conference on Plasma Physics, Bordeaux (eingereicht)
239.
Vortrag
Analysis of deuterium and defects in tungsten by Rutherford backscattering spectroscopy and nuclear reaction analysis in channeling configuration. Materials in Nuclear Energy Systems (MiNES 2023), New Orleans, LA (eingereicht)
240.
Vortrag
The influence of grain size on the displacement damage creation, D retention and D transport in tungsten. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)