Publications of B. Böswirth
All genres
Journal Article (77)
2024
Journal Article
38, 101563 (2024)
Qualification of W heavy alloys as plasma facing material. Nuclear Materials and Energy
Journal Article
201, 114232 (2024)
Mock-ups fabrication by HRP technology with advanced W-alloy monoblocks for DEMO divertor target. Fusion Engineering and Design
Journal Article
38, 101591 (2024)
Progress in the development of industrial scale tungsten fibre-reinforced composite materials. Nuclear Materials and Energy 2023
Journal Article
194, 113886 (2023)
Predictive and interpretative modelling of ASDEX-upgrade liquid metal divertor experiment. Fusion Engineering and Design
Journal Article
36, 101465 (2023)
Microstructural evolution of tungsten under thermal loads: A comparative study between cyclic high heat flux loading and isochronous furnace heating. Nuclear Materials and Energy
Journal Article
34, 101343 (2023)
Investigations on cold spray tungsten/tantalum coatings for plasma facing applications. Nuclear Materials and Energy
Journal Article
37, 101528 (2023)
Design and GLADIS testing of a liquid tin divertor module prior to exposure in ASDEX Upgrade. Nuclear Materials and Energy 2022
Journal Article
62, 042022 (2022)
Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X. Nuclear Fusion
Journal Article
62, 042006 (2022)
Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development. Nuclear Fusion
Journal Article
33, 101307 (2022)
High-heat-flux performance limit of tungsten monoblock targets: Impact on the armor materials and implications for power exhaust capacity. Nuclear Materials and Energy
Journal Article
175, 113010 (2022)
Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design 2021
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), 014037 (2020)
Impact of H-mode plasma operation on pre-damaged tungsten divertor tiles in ASDEX Upgrade. 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 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
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