Publications of H. Greuner
All genres
Journal Article (167)
1.
Journal Article
62, 042007 (2022)
Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation. Nuclear Fusion 2.
Journal Article
62, 042022 (2022)
Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X. Nuclear Fusion 3.
Journal Article
62, 042006 (2022)
Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development. Nuclear Fusion 4.
Journal Article
175, 113010 (2022)
Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design 5.
Journal Article
96, 124065 (2021)
Typology of defects in DEMO divertor target mockups. Physica Scripta 6.
Journal Article
166, 112293 (2021)
Completion of the production of the W7-X divertor target modules. Fusion Engineering and Design 7.
Journal Article
163, 112120 (2021)
Flush-mounted Langmuir probes in the WEST tokamak divertor. Fusion Engineering and Design 8.
Journal Article
96, 124029 (2021)
Acceptance tests of the industrial series manufacturing of WEST ITER-like tungsten actively cooled divertor. Physica Scripta 9.
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 10.
Journal Article
48 (6), pp. 1519 - 1524 (2020)
Transient Computational and Experimental Thermal Analysis of Graphite Foam Monoblock. IEEE Transactions on Plasma Science 11.
Journal Article
2020 (T171), 014003 (2020)
Assessment of the high heat flux performance of European DEMO divertor mock-ups. Physica Scripta 12.
Journal Article
2020 (T171), 014050 (2020)
Helium irradiation effects on the surface modification and recrystallization of tungsten. Physica Scripta 13.
Journal Article
2020 (T171), 014037 (2020)
Impact of H-mode plasma operation on pre-damaged tungsten divertor tiles in ASDEX Upgrade. Physica Scripta 14.
Journal Article
2020 (T171), 014035 (2020)
Material erosion and deposition on the divertor of W7-X. Physica Scripta 15.
Journal Article
2020 (T171), 014015 (2020)
Application of tungsten–copper composite heat sink materials to plasma-facing component mock-ups. Physica Scripta 16.
Journal Article
157, 111610 (2020)
Performance assessment of thick W/Cu graded interlayer for DEMO divertor target. Fusion Engineering and Design 17.
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 18.
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 19.
Journal Article
20, 100688 (2019)
Manufacturing, high heat flux testing and post mortem analyses of a W-PIM mock-up. Nuclear Materials and Energy 20.
Journal Article
146, Pt. B, pp. 1975 - 1978 (2019)
Progress in the production of the W7-X divertor target modules. Fusion Engineering and Design