
Publications of B. Curzadd
All genres
Journal Article (7)
1.
Journal Article
High heat flux testing of plasma-facing component mock-ups with tailored tungsten-copper composite heat sinks. Journal of Nuclear Materials 618, 156233 (2026)
2.
Journal Article
The General-Purpose Irradiated Fiber and Foil Experiment for material characterization under fusion-relevant loads. Fusion Engineering and Design 217, 115114 (2025)
3.
Journal Article
Experimental investigation of the impact of irradiation damages on the mechanical properties of tungsten. Nuclear Materials and Energy 42, 101858 (2025)
4.
Journal Article
: Material and component developments for the DEMO divertor using fibre reinforcement and additive manufacturing. Materials Research Express 10, 116516 (2023)
5.
Journal Article
Progress in additive manufacturing of pure tungsten for plasma-facing component applications. Journal of Nuclear Materials 566, 153760 (2022)
6.
Journal Article
Irradiation effects in tungsten – from surface effects to bulk mechanical properties. Nuclear Materials and Energy 30, 101093 (2022)
7.
Journal Article
Topology optimization of tungsten/copper structures for plasma-facing component applications. Nuclear Fusion 59, 086003 (2019)
Meeting Abstract (2)
8.
Meeting Abstract
The GIRAFFE experiment: in situ tensile tests of irradiated tungsten fibers. In: Verhandlungen der Deutschen Physikalischen Gesellschaft, (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)
9.
Meeting Abstract
Investigating the deformation of drawn tungsten wires. In: Verhandlungen der Deutschen Physikalischen Gesellschaft, (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)
Talk (16)
10.
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)
11.
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)
12.
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)
13.
Talk
: Giraffe – Mechanical testing with in-situ irradiation. The Nuclear Materials Conference (NuMat 2022), Ghent (submitted)
14.
Talk
In situ mechanical characterization of ion-irradiated tungsten. DPG-Tagung der Sektion Materie und Kosmos (SMuK), Virtual (submitted)
15.
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)
16.
Talk
: Materials and Components for the DEMO Divertor. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (submitted)
17.
Talk
: Solving the Brittleness Problem of Tungsten – Tungsten Fibrereinforced Tungsten Composites. TMS 2021 Virtual Annual Meeting & Exhibition, Virtual (submitted)
18.
Talk
: Solving the Brittleness Problem of Tungsten – Tungsten Fibrereinforced Tungsten Composites. TMS2021 - Composite Materials for Nuclear Applications, Virtual (submitted)
19.
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)
20.
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)