Publikationen von K. Hunger
Alle Typen
Zeitschriftenartikel (19)
1.
Zeitschriftenartikel
94, 053503 (2023)
Layer thickness characterization of Faraday cup fast ion loss detectors. Review of Scientific Instruments 2.
Zeitschriftenartikel
36, 101465 (2023)
Microstructural evolution of tungsten under thermal loads: A comparative study between cyclic high heat flux loading and isochronous furnace heating. Nuclear Materials and Energy 3.
Zeitschriftenartikel
34, 101343 (2023)
Investigations on cold spray tungsten/tantalum coatings for plasma facing applications. Nuclear Materials and Energy 4.
Zeitschriftenartikel
34, 101320 (2023)
Surface features of strongly heated bulk tungsten divertor plates at ASDEX Upgrade. Nuclear Materials and Energy 5.
Zeitschriftenartikel
30, 101118 (2022)
Comparison experiment on the sputtering of EUROFER, RUSFER and CLAM steels by deuterium ions. Nuclear Materials and Energy 6.
Zeitschriftenartikel
62, 042006 (2022)
Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development. Nuclear Fusion 7.
Zeitschriftenartikel
174, 112988 (2022)
Limiters for DEMO wall protection: Initial design concepts & technology options. Fusion Engineering and Design 8.
Zeitschriftenartikel
33, 101307 (2022)
High-heat-flux performance limit of tungsten monoblock targets: Impact on the armor materials and implications for power exhaust capacity. Nuclear Materials and Energy 9.
Zeitschriftenartikel
175, 113010 (2022)
Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design 10.
Zeitschriftenartikel
167, 112385 (2021)
A hot steam leak during baking of ASDEX Upgrade – Consequences and lessons learned. Fusion Engineering and Design 11.
Zeitschriftenartikel
27, 100972 (2021)
Deuterium retention in tungsten fiber-reinforced tungsten composites. Nuclear Materials and Energy 12.
Zeitschriftenartikel
544, 152670 (2021)
High-heat-flux technologies for the European demo divertor targets: State-of-the-art and a review of the latest testing campaign. Journal of Nuclear Materials 13.
Zeitschriftenartikel
2020 (T171), 014003 (2020)
Assessment of the high heat flux performance of European DEMO divertor mock-ups. Physica Scripta 14.
Zeitschriftenartikel
2020 (T171), 014050 (2020)
Helium irradiation effects on the surface modification and recrystallization of tungsten. Physica Scripta 15.
Zeitschriftenartikel
60, 126044 (2020)
Tungsten heavy alloy: an alternative plasma-facing material in terms of hydrogen isotope retention. Nuclear Fusion 16.
Zeitschriftenartikel
157, 111630 (2020)
Recovery from a hot water leakage at the tokamak ASDEX upgrade. Fusion Engineering and Design 17.
Zeitschriftenartikel
24, 100770 (2020)
Microstructure, oxidation behaviour and thermal shock resistance of self-passivating W-Cr-Y-Zr alloys. Nuclear Materials and Energy 18.
Zeitschriftenartikel
146, Pt. A, S. 870 - 873 (2019)
Ultrasonic analysis of tungsten monoblock divertor mock-ups after high heat flux test. Fusion Engineering and Design 19.
Zeitschriftenartikel
146, Pt. A, S. 216 - 219 (2019)
Progress in high heat flux testing of European DEMO divertor mock-ups. Fusion Engineering and Design Vortrag (20)
20.
Vortrag
Tungsten based target element development for Wendelstein 7-X. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)