Publikationen von H. Greuner
Alle Typen
Zeitschriftenartikel (181)
2021
Zeitschriftenartikel
163, 112120 (2021)
Flush-mounted Langmuir probes in the WEST tokamak divertor. Fusion Engineering and Design
Zeitschriftenartikel
96, 124029 (2021)
Acceptance tests of the industrial series manufacturing of WEST ITER-like tungsten actively cooled divertor. Physica Scripta
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
48 (6), S. 1519 - 1524 (2020)
Transient Computational and Experimental Thermal Analysis of Graphite Foam Monoblock. IEEE Transactions on Plasma Science
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
2020 (T171), 014037 (2020)
Impact of H-mode plasma operation on pre-damaged tungsten divertor tiles in ASDEX Upgrade. Physica Scripta
Zeitschriftenartikel
2020 (T171), 014035 (2020)
Material erosion and deposition on the divertor of W7-X. Physica Scripta
Zeitschriftenartikel
2020 (T171), 014015 (2020)
Application of tungsten–copper composite heat sink materials to plasma-facing component mock-ups. Physica Scripta
Zeitschriftenartikel
157, 111610 (2020)
Performance assessment of thick W/Cu graded interlayer for DEMO divertor target. Fusion Engineering and Design
Zeitschriftenartikel
161, 111886 (2020)
Ultrasonic test results before and after high heat flux testing on W-monoblock mock-ups of EU-DEMO vertical target. Fusion Engineering and Design
Zeitschriftenartikel
154, 111510 (2020)
Stress analysis of divertor plasma-facing component designs using tungsten particle-reinforced copper composite heat sink. Fusion Engineering and Design 2019
Zeitschriftenartikel
20, 100688 (2019)
Manufacturing, high heat flux testing and post mortem analyses of a W-PIM mock-up. Nuclear Materials and Energy
Zeitschriftenartikel
146, Pt. B, S. 1975 - 1978 (2019)
Progress in the production of the W7-X divertor target modules. Fusion Engineering and Design
Zeitschriftenartikel
146, Pt. B, S. 1431 - 1436 (2019)
Materials development for new high heat-flux component mock-ups for DEMO. Fusion Engineering and Design
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
516, S. 178 - 184 (2019)
Synergistic effects of ELMs and H–He irradiation on the degradation behavior of tungsten treated with high-energy-rate forging. Journal of Nuclear Materials
Zeitschriftenartikel
146, Pt. A, S. 216 - 219 (2019)
Progress in high heat flux testing of European DEMO divertor mock-ups. Fusion Engineering and Design
Zeitschriftenartikel
59, 112021 (2019)
Overview of the JET preparation for deuterium-tritium operation with the ITER like-wall. Nuclear Fusion
Zeitschriftenartikel
59, 112004 (2019)
Overview of first Wendelstein 7-X high-performance operation. Nuclear Fusion