Publikationen von T. Schwarz-Selinger
Alle Typen
Vortrag (205)
241.
Vortrag
Defect stabilisation in tungsten during simultaneous D loading and displacement damage creation: importance for fuel retention and transport in DEMO. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (eingereicht)
242.
Vortrag
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 (eingereicht)
243.
Vortrag
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 (eingereicht)
244.
Vortrag
Accelerated Lifetime Tests of ITER-like Tungsten Monoblocks in Magnum-PSI. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (eingereicht)
245.
Vortrag
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)
246.
Vortrag
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 (eingereicht)
247.
Vortrag
Understanding Retention and Transport of Hydrogen in Displacement-damaged Tungsten. Seminar: NOMATEN Centre of Excellence in Multifunctional Materials for Industrial and Medical Applications, Virtual (eingereicht)
248.
Vortrag
Saturation of defect densities at elevated temperature in displacement-damaged tungsten. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (eingereicht)
249.
Vortrag
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 (eingereicht)
250.
Vortrag
Fuel removal: complementary research at the TOMAS experimental facility. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (2021)
251.
Vortrag
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 (eingereicht)
252.
Vortrag
Solving the Brittleness Problem of Tungsten – Tungsten Fibrereinforced Tungsten Composites. TMS 2021 Virtual Annual Meeting & Exhibition, Virtual (eingereicht)
253.
Vortrag
Solving the Brittleness Problem of Tungsten – Tungsten Fibrereinforced Tungsten Composites. TMS2021 - Composite Materials for Nuclear Applications, Virtual (eingereicht)
254.
Vortrag
Saturation of defect densities in displacement-damaged tungsten. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (eingereicht)
255.
Vortrag
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 (eingereicht)
256.
Vortrag
Behavior of Tin under Low-Temperature Deuterium Plasma Irradiation. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (eingereicht)
257.
Vortrag
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 (eingereicht)
258.
Vortrag
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)
259.
Vortrag
Influence of He concentration on deuterium retention and transport in the bulk of tungsten. 24th International Conference on Ion Beam Analysis (IBA 2019), Antibes (eingereicht)
260.
Vortrag
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 (eingereicht)