Publications of B. Curzadd
All genres
Journal Article (5)
1.
Journal Article
42, 101858 (2025)
Experimental investigation of the impact of irradiation damages on the mechanical properties of tungsten. Nuclear Materials and Energy 2.
Journal Article
10, 116516 (2023)
Material and component developments for the DEMO divertor using fibre reinforcement and additive manufacturing. Materials Research Express 3.
Journal Article
566, 153760 (2022)
Progress in additive manufacturing of pure tungsten for plasma-facing component applications. Journal of Nuclear Materials 4.
Journal Article
30, 101093 (2022)
Irradiation effects in tungsten – from surface effects to bulk mechanical properties. Nuclear Materials and Energy 5.
Journal Article
59, 086003 (2019)
Topology optimization of tungsten/copper structures for plasma-facing component applications. Nuclear Fusion Meeting Abstract (2)
6.
Meeting Abstract
(VI) 55 (1), P 16.7. DPG-Frühjahrstagung der Sektion Atome, Moleküle, Quantenoptik und Plasmen (SAMOP), Hannover, March 08, 2020 - March 13, 2020. DPG, Bad Honnef (submitted)
The GIRAFFE experiment: in situ tensile tests of irradiated tungsten fibers. In: Verhandlungen der Deutschen Physikalischen Gesellschaft, 7.
Meeting Abstract
(VI) 55 (1), P 10.25. DPG-Frühjahrstagung der Sektion Atome, Moleküle, Quantenoptik und Plasmen (SAMOP), Hannover, March 08, 2020 - March 13, 2020. DPG, Bad Honnef (submitted)
Investigating the deformation of drawn tungsten wires. In: Verhandlungen der Deutschen Physikalischen Gesellschaft, Talk (16)
8.
Talk
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 (submitted)
9.
Talk
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 (submitted)
10.
Talk
Fusion Materials Research with the GIRAFFE Experiment – Mechanical Testing under Fusion-Relevant Loads. International Conference on Processing & Manufacturing of Advanced Materials (Thermec 2023), Vienna (submitted)
11.
Talk
Giraffe – Mechanical testing with in-situ irradiation. The Nuclear Materials Conference (NuMat 2022), Ghent (submitted)
12.
Talk
In situ mechanical characterization of ion-irradiated tungsten. DPG-Tagung der Sektion Materie und Kosmos (SMuK), Virtual (submitted)
13.
Talk
In situ tensile testing of ion-irradiated thin samples and radiation-induced load relaxation in tungsten. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (submitted)
14.
Talk
Materials and Components for the DEMO Divertor. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (submitted)
15.
Talk
Solving the Brittleness Problem of Tungsten – Tungsten Fibrereinforced Tungsten Composites. TMS 2021 Virtual Annual Meeting & Exhibition, Virtual (submitted)
16.
Talk
Solving the Brittleness Problem of Tungsten – Tungsten Fibrereinforced Tungsten Composites. TMS2021 - Composite Materials for Nuclear Applications, Virtual (submitted)
17.
Talk
Additive manufacturing of tungsten by means of laser powder bed fusion for plasma-facing component applications. 3rd IAEA Technical Meeting on Divertor Concepts, Vienna (submitted)
18.
Talk
Progress in additive manufacturing of pure tungsten for plasma-facing component applications. International Conference on Processing & Manufacturing of Advanced Materials (Thermec 2021), Virtual (submitted)
19.
Talk
Tungsten-copper composite materials for plasma-facing component heat sink applications. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)
20.
Talk
Tungsten fibre-reinforced tungsten composite – extrinsic toughening of a new high performance material. 10th International Conference on High Temperature Ceramic Matrix Composites (HT-CMC10), Bordeaux (submitted)