Publikationen von K. Hunger
Alle Typen
Zeitschriftenartikel (17)
2023
Zeitschriftenartikel
34, 101343 (2023)
Investigations on cold spray tungsten/tantalum coatings for plasma facing applications. Nuclear Materials and Energy
Zeitschriftenartikel
34, 101320 (2023)
Surface features of strongly heated bulk tungsten divertor plates at ASDEX Upgrade. Nuclear Materials and Energy 2022
Zeitschriftenartikel
30, 101118 (2022)
Comparison experiment on the sputtering of EUROFER, RUSFER and CLAM steels by deuterium ions. Nuclear Materials and Energy
Zeitschriftenartikel
62, 042006 (2022)
Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development. Nuclear Fusion
Zeitschriftenartikel
174, 112988 (2022)
Limiters for DEMO wall protection: Initial design concepts & technology options. Fusion Engineering and Design
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
Zeitschriftenartikel
175, 113010 (2022)
Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design 2021
Zeitschriftenartikel
167, 112385 (2021)
A hot steam leak during baking of ASDEX Upgrade – Consequences and lessons learned. Fusion Engineering and Design
Zeitschriftenartikel
27, 100972 (2021)
Deuterium retention in tungsten fiber-reinforced tungsten composites. Nuclear Materials and Energy
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 2020
Zeitschriftenartikel
2020 (T171), 014003 (2020)
Assessment of the high heat flux performance of European DEMO divertor mock-ups. Physica Scripta
Zeitschriftenartikel
2020 (T171), 014050 (2020)
Helium irradiation effects on the surface modification and recrystallization of tungsten. Physica Scripta
Zeitschriftenartikel
60, 126044 (2020)
Tungsten heavy alloy: an alternative plasma-facing material in terms of hydrogen isotope retention. Nuclear Fusion
Zeitschriftenartikel
157, 111630 (2020)
Recovery from a hot water leakage at the tokamak ASDEX upgrade. Fusion Engineering and Design
Zeitschriftenartikel
24, 100770 (2020)
Microstructure, oxidation behaviour and thermal shock resistance of self-passivating W-Cr-Y-Zr alloys. Nuclear Materials and Energy 2019
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
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 (14)
2023
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)
Vortrag
Progress in the Development of Industrial Scale Tungsten Wire Composite Materials. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)
Vortrag
Performance of a liquid tin divertor target during ASDEX Upgrade L- and H-mode operation. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)