Publications of K. Hunger
All genres
Journal Article (35)
21.
Journal Article
: Comparison experiment on the sputtering of EUROFER, RUSFER and CLAM steels by deuterium ions. Nuclear Materials and Energy 30, 101118 (2022)
22.
Journal Article
: Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development. Nuclear Fusion 62, 042006 (2022)
23.
Journal Article
: Limiters for DEMO wall protection: Initial design concepts & technology options. Fusion Engineering and Design 174, 112988 (2022)
24.
Journal Article
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 25.
Journal Article
: Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design 175, 113010 (2022)
26.
Journal Article
: A hot steam leak during baking of ASDEX Upgrade – Consequences and lessons learned. Fusion Engineering and Design 167, 112385 (2021)
27.
Journal Article
: Deuterium retention in tungsten fiber-reinforced tungsten composites. Nuclear Materials and Energy 27, 100972 (2021)
28.
Journal Article
: 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 544, 152670 (2021)
29.
Journal Article
2020 (T171), 014003 (2020)
Assessment of the high heat flux performance of European DEMO divertor mock-ups. Physica Scripta 30.
Journal Article
: Helium irradiation effects on the surface modification and recrystallization of tungsten. Physica Scripta 2020 (T171), 014050 (2020)
31.
Journal Article
60, 126044 (2020)
Tungsten heavy alloy: an alternative plasma-facing material in terms of hydrogen isotope retention. Nuclear Fusion 32.
Journal Article
157, 111630 (2020)
Recovery from a hot water leakage at the tokamak ASDEX upgrade. Fusion Engineering and Design 33.
Journal Article
24, 100770 (2020)
Microstructure, oxidation behaviour and thermal shock resistance of self-passivating W-Cr-Y-Zr alloys. Nuclear Materials and Energy 34.
Journal Article
146, Pt. A, pp. 870 - 873 (2019)
Ultrasonic analysis of tungsten monoblock divertor mock-ups after high heat flux test. Fusion Engineering and Design 35.
Journal Article
146, Pt. A, pp. 216 - 219 (2019)
Progress in high heat flux testing of European DEMO divertor mock-ups. Fusion Engineering and Design Talk (29)
36.
Talk
High heat flux testing of actively cooled graphite- and tungsten-armoured JT-60SA flattile divertor mock-ups. 20th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-20), Ljubljana (submitted)
37.
Talk
: High Heat Flux Testing and Modeling of SPARC Plasma-Facing Components. 26th Technology of Fusion Energy Meeting (TOFE 2024), Madison, WI (2024)
38.
Talk
: Additive manufacturing for tungsten-based plasma-facing components. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (submitted)
39.
Talk
: High heat flux testing of plasma-facing components for the compact, high field tokamak SPARC. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (submitted)
40.
Talk
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 (submitted)