Publikationen von K. Hunger
Alle Typen
Zeitschriftenartikel (34)
2022
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 (28)
2024
Vortrag
High Heat Flux Testing and Modeling of SPARC Plasma-Facing Components. 26th Technology of Fusion Energy Meeting (TOFE 2024), Madison, WI (2024)
Vortrag
Additive manufacturing for tungsten-based plasma-facing components. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (eingereicht)
Vortrag
High heat flux testing of plasma-facing components for the compact, high field tokamak SPARC. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (eingereicht)
Vortrag
Appearance and analysis of a reflecting coating damage. 22nd Joint Workshop on Electron Cyclotron Emission (ECE) and Electron Cyclotron Resonance Heating (ECRH) (EC-22), Daejeon (eingereicht)
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
Results and conclusions of high-power cycling of European DEMO divertor target mock-ups. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (eingereicht)