Publikationen von K. Hunger
Alle Typen
Zeitschriftenartikel (14)
1.
Zeitschriftenartikel
30, 101118 (2022)
Comparison experiment on the sputtering of EUROFER, RUSFER and CLAM steels by deuterium ions. Nuclear Materials and Energy 2.
Zeitschriftenartikel
62, 042006 (2022)
Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development. Nuclear Fusion 3.
Zeitschriftenartikel
174, 112988 (2022)
Limiters for DEMO wall protection: Initial design concepts & technology options. Fusion Engineering and Design 4.
Zeitschriftenartikel
175, 113010 (2022)
Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design 5.
Zeitschriftenartikel
167, 112385 (2021)
A hot steam leak during baking of ASDEX Upgrade – Consequences and lessons learned. Fusion Engineering and Design 6.
Zeitschriftenartikel
27, 100972 (2021)
Deuterium retention in tungsten fiber-reinforced tungsten composites. Nuclear Materials and Energy 7.
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 8.
Zeitschriftenartikel
2020 (T171), 014003 (2020)
Assessment of the high heat flux performance of European DEMO divertor mock-ups. Physica Scripta 9.
Zeitschriftenartikel
2020 (T171), 014050 (2020)
Helium irradiation effects on the surface modification and recrystallization of tungsten. Physica Scripta 10.
Zeitschriftenartikel
60, 126044 (2020)
Tungsten heavy alloy: an alternative plasma-facing material in terms of hydrogen isotope retention. Nuclear Fusion 11.
Zeitschriftenartikel
157, 111630 (2020)
Recovery from a hot water leakage at the tokamak ASDEX upgrade. Fusion Engineering and Design 12.
Zeitschriftenartikel
24, 100770 (2020)
Microstructure, oxidation behaviour and thermal shock resistance of self-passivating W-Cr-Y-Zr alloys. Nuclear Materials and Energy 13.
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 14.
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 (9)
15.
Vortrag
Progress in R&D on Plasma-Facing Materials and Components for Fusion Devices. aiv XXV Conference, Naples (eingereicht)
16.
Vortrag
Results of high heat flux overload tests of European DEMO tungsten divertor target mock-ups. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (eingereicht)
17.
Vortrag
Beneficial Deuterium Retention Properties of Tungsten Heavy Alloy. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (eingereicht)
18.
Vortrag
Sacrificial limiter for DEMO wall protection: material concepts, technology and performance under extreme heat loads. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (eingereicht)
19.
Vortrag
Materials and Components for the DEMO Divertor. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (eingereicht)
20.
Vortrag
The quest for a durable high-heat-flux component: requirements and issues. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (eingereicht)