Publikationen von K. Hunger
Alle Typen
Zeitschriftenartikel (35)
21.
Zeitschriftenartikel
: Comparison experiment on the sputtering of EUROFER, RUSFER and CLAM steels by deuterium ions. Nuclear Materials and Energy 30, 101118 (2022)
22.
Zeitschriftenartikel
: Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development. Nuclear Fusion 62, 042006 (2022)
23.
Zeitschriftenartikel
: Limiters for DEMO wall protection: Initial design concepts & technology options. Fusion Engineering and Design 174, 112988 (2022)
24.
Zeitschriftenartikel
High-heat-flux performance limit of tungsten monoblock targets: Impact on the armor materials and implications for power exhaust capacity. Nuclear Materials and Energy 33, 101307 (2022)
25.
Zeitschriftenartikel
: Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design 175, 113010 (2022)
26.
Zeitschriftenartikel
: A hot steam leak during baking of ASDEX Upgrade – Consequences and lessons learned. Fusion Engineering and Design 167, 112385 (2021)
27.
Zeitschriftenartikel
: Deuterium retention in tungsten fiber-reinforced tungsten composites. Nuclear Materials and Energy 27, 100972 (2021)
28.
Zeitschriftenartikel
: 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.
Zeitschriftenartikel
Assessment of the high heat flux performance of European DEMO divertor mock-ups. Physica Scripta 2020 (T171), 014003 (2020)
30.
Zeitschriftenartikel
: Helium irradiation effects on the surface modification and recrystallization of tungsten. Physica Scripta 2020 (T171), 014050 (2020)
31.
Zeitschriftenartikel
Tungsten heavy alloy: an alternative plasma-facing material in terms of hydrogen isotope retention. Nuclear Fusion 60, 126044 (2020)
32.
Zeitschriftenartikel
Recovery from a hot water leakage at the tokamak ASDEX upgrade. Fusion Engineering and Design 157, 111630 (2020)
33.
Zeitschriftenartikel
Microstructure, oxidation behaviour and thermal shock resistance of self-passivating W-Cr-Y-Zr alloys. Nuclear Materials and Energy 24, 100770 (2020)
34.
Zeitschriftenartikel
Ultrasonic analysis of tungsten monoblock divertor mock-ups after high heat flux test. Fusion Engineering and Design 146, Pt. A, S. 870 - 873 (2019)
35.
Zeitschriftenartikel
Progress in high heat flux testing of European DEMO divertor mock-ups. Fusion Engineering and Design 146, Pt. A, S. 216 - 219 (2019)
Vortrag (31)
36.
Vortrag
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 (eingereicht)
37.
Vortrag
: Detection of defects in displacement-damaged tungsten and iron. 7th International Workshop on Models and Data for Plasma-Material Interactions in Fusion Devices (MoD-PMI 2025), Vienna (eingereicht)
38.
Vortrag
: Current status and challenges of the development of plasma-facing components. 31st IEEE Symposium on Fusion Engineering (SOFE 2025), Cambridge, MA (eingereicht)
39.
Vortrag
: High Heat Flux Testing and Modeling of SPARC Plasma-Facing Components. 26th Technology of Fusion Energy Meeting (TOFE 2024), Madison, WI (2024)
40.
Vortrag
: Additive manufacturing for tungsten-based plasma-facing components. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (eingereicht)