Publications of T. Schwarz-Selinger
All genres
Talk (205)
241.
Talk
Effect of D on the evolution of displacement damage in W during annealing to 1000 K. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (submitted)
242.
Talk
Basic Data for NRA and Best Practises for IBA. 1st Research Coordination Meeting of the CRP on “Development and Application of Ion Beam Techniques for Materials Irradiation and Characterization Relevant to Fusion Technology” (Virtual), Vienna (submitted)
243.
Talk
Accelerated Lifetime Tests of ITER-like Tungsten Monoblocks in Magnum-PSI. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (submitted)
244.
Talk
Effect of elevated temperature and D presence on defect creation in W. 5th International Workshop Models and Data for Plasma-Material Interaction in Fusion Devices (MoD-PMI 2021) (virtual), Jülich (2021)
245.
Talk
Influence of the initial D concentration on damage stabilization during selfdamaging of tungsten. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (submitted)
246.
Talk
Understanding Retention and Transport of Hydrogen in Displacement-damaged Tungsten. Seminar: NOMATEN Centre of Excellence in Multifunctional Materials for Industrial and Medical Applications, Virtual (submitted)
247.
Talk
Saturation of defect densities at elevated temperature in displacement-damaged tungsten. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (submitted)
248.
Talk
Radiation damaging of tungsten: Recent advances in predicting tritium retention and transport for DEMO. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (submitted)
249.
Talk
Fuel removal: complementary research at the TOMAS experimental facility. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (2021)
250.
Talk
Deuterium retention and dislocation structure of tungsten irradiated by different ions. 5th International Workshop Models and Data for Plasma-Material Interaction in Fusion Devices (MoD-PMI 2021) (virtual), Jülich (submitted)
251.
Talk
Solving the Brittleness Problem of Tungsten – Tungsten Fibrereinforced Tungsten Composites. TMS 2021 Virtual Annual Meeting & Exhibition, Virtual (submitted)
252.
Talk
Solving the Brittleness Problem of Tungsten – Tungsten Fibrereinforced Tungsten Composites. TMS2021 - Composite Materials for Nuclear Applications, Virtual (submitted)
253.
Talk
Saturation of defect densities in displacement-damaged tungsten. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (submitted)
254.
Talk
Sputtering of EUROFER: The Role of Roughness. 3rd Research Coordination Meeting of CRP on "Plasma-wall Interaction with Reduced-activation Steel Surfaces in Fusion Devices (2015-2020)", Vienna (submitted)
255.
Talk
Behavior of Tin under Low-Temperature Deuterium Plasma Irradiation. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (submitted)
256.
Talk
Influence of He concentration and He bubbles on deuterium retention and transport in the bulk of tungsten. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)
257.
Talk
Displacement damage stabilization by hydrogen presence under simultaneous W ion damaging and D ion exposure. 4th International Workshop on Models and Data for Plasma-Material Interaction in Fusion Devices, Toki, Gifu (2019)
258.
Talk
Influence of He concentration on deuterium retention and transport in the bulk of tungsten. 24th International Conference on Ion Beam Analysis (IBA 2019), Antibes (submitted)
259.
Talk
ITER monoblock performance under lifetime loading conditions in Magnum-PSI. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)
260.
Talk
Gamma-ray irradiation effect on deuterium retention in reduced activation ferritic/martensitic steel and ceramic coatings. 19th International Conference on Fusion Reactor Materials (ICFRM-19), La Jolla, CA (submitted)