Publications of H. Greuner
All genres
Journal Article (181)
2021
Journal Article
163, 112120 (2021)
Flush-mounted Langmuir probes in the WEST tokamak divertor. Fusion Engineering and Design
Journal Article
96, 124029 (2021)
Acceptance tests of the industrial series manufacturing of WEST ITER-like tungsten actively cooled divertor. Physica Scripta
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 2020
Journal Article
48 (6), pp. 1519 - 1524 (2020)
Transient Computational and Experimental Thermal Analysis of Graphite Foam Monoblock. IEEE Transactions on Plasma Science
Journal Article
2020 (T171), 014003 (2020)
Assessment of the high heat flux performance of European DEMO divertor mock-ups. Physica Scripta
Journal Article
2020 (T171), 014050 (2020)
Helium irradiation effects on the surface modification and recrystallization of tungsten. Physica Scripta
Journal Article
2020 (T171), 014037 (2020)
Impact of H-mode plasma operation on pre-damaged tungsten divertor tiles in ASDEX Upgrade. Physica Scripta
Journal Article
2020 (T171), 014035 (2020)
Material erosion and deposition on the divertor of W7-X. Physica Scripta
Journal Article
2020 (T171), 014015 (2020)
Application of tungsten–copper composite heat sink materials to plasma-facing component mock-ups. Physica Scripta
Journal Article
157, 111610 (2020)
Performance assessment of thick W/Cu graded interlayer for DEMO divertor target. Fusion Engineering and Design
Journal Article
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
Journal Article
154, 111510 (2020)
Stress analysis of divertor plasma-facing component designs using tungsten particle-reinforced copper composite heat sink. Fusion Engineering and Design 2019
Journal Article
20, 100688 (2019)
Manufacturing, high heat flux testing and post mortem analyses of a W-PIM mock-up. Nuclear Materials and Energy
Journal Article
146, Pt. B, pp. 1975 - 1978 (2019)
Progress in the production of the W7-X divertor target modules. Fusion Engineering and Design
Journal Article
146, Pt. B, pp. 1431 - 1436 (2019)
Materials development for new high heat-flux component mock-ups for DEMO. Fusion Engineering and Design
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
Journal Article
516, pp. 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
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
Journal Article
59, 112021 (2019)
Overview of the JET preparation for deuterium-tritium operation with the ITER like-wall. Nuclear Fusion
Journal Article
59, 112004 (2019)
Overview of first Wendelstein 7-X high-performance operation. Nuclear Fusion