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