Publikationen von A. Feichtmayer
Alle Typen
Zeitschriftenartikel (6)
1.
Zeitschriftenartikel
42, 101858 (2025)
Experimental investigation of the impact of irradiation damages on the mechanical properties of tungsten. Nuclear Materials and Energy 2.
Zeitschriftenartikel
5, 218 (2024)
Fast low-temperature irradiation creep driven by athermal defect dynamics. Communications Materials 3.
Zeitschriftenartikel
191, 113742 (2023)
Pre-conceptual design of a PFC equipped with a W lattice armour for first wall limiters in the EU-DEMO fusion reactor. Fusion Engineering and Design 4.
Zeitschriftenartikel
30, 101093 (2022)
Irradiation effects in tungsten – from surface effects to bulk mechanical properties. Nuclear Materials and Energy 5.
Zeitschriftenartikel
41 (5), S. 3030 - 3036 (2021)
Novel ceramic matrix composites with tungsten and molybdenum fiber reinforcement. Journal of the European Ceramic Society 6.
Zeitschriftenartikel
T170, 014032 (2017)
Tensile behaviour of drawn tungsten wire used in tungsten fibre-reinforced tungsten composites. Physica Scripta Meeting Abstract (1)
7.
Meeting Abstract
(VI) 55 (1), P 16.7. DPG-Frühjahrstagung der Sektion Atome, Moleküle, Quantenoptik und Plasmen (SAMOP), Hannover, 08. März 2020 - 13. März 2020. DPG, Bad Honnef (eingereicht)
The GIRAFFE experiment: in situ tensile tests of irradiated tungsten fibers. In: Verhandlungen der Deutschen Physikalischen Gesellschaft, Vortrag (16)
8.
Vortrag
Theoretical investigation of fast low-temperature irradiation creep – Development of a parameter-free digital shadow for quantitative predictions. 19th European Mechanics of Materials Conference (EMMC19), Madrid (2024)
9.
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)
10.
Vortrag
Additive manufacturing for tungsten-based plasma-facing components. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (eingereicht)
11.
Vortrag
GIRAFFE – In Situ Material Tests under Fusion‐Relevant Conditions. TMS 2025 154th Annual Meeting & Exhibition, Las Vegas, NV (eingereicht)
12.
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)
13.
Vortrag
Additive manufacturing of tungsten-copper bi-material structures for plasma-facing component applications in fusion devices. Additive Manufacturing with Powder Metallurgy (AMPM 2023), Las Vegas, NV (eingereicht)
14.
Vortrag
Experimental Determination of Irradiation-Induced Stress Relaxation in Thin Tungsten Wires. 86. Jahrestagung der DPG und DPG-Frühjahrstagung der Sektion Materie und Kosmos (SMuK), Dresden (eingereicht)
15.
Vortrag
Fusion Materials Research with the GIRAFFE Experiment – Mechanical Testing under Fusion-Relevant Loads. International Conference on Processing & Manufacturing of Advanced Materials (Thermec 2023), Vienna (eingereicht)
16.
Vortrag
Deformation mechanisms and Structure-Property Relations of Drawn W Wires. 19th International Conference on Strength of Materials, Metz (eingereicht)
17.
Vortrag
Progress in R&D on Plasma-Facing Materials and Components for Fusion Devices. aiv XXV Conference, Naples (eingereicht)
18.
Vortrag
Recent Progress in the Development of Tungsten Fibre-reinforced Tungsten Composite. TMS 2023 Annual Meeting & Exhibition, San Diego, CA (eingereicht)
19.
Vortrag
Giraffe – Mechanical testing with in-situ irradiation. The Nuclear Materials Conference (NuMat 2022), Ghent (eingereicht)
20.
Vortrag
Novel ceramic matrix composites with tungsten and molybdenum fiber reinforcement. 10th International Conference on High Temperature Ceramic Matrix Composites (HT-CMC10), Bordeaux (2019)