Author

B. Böswirth

Observed names: B Boeswirth, B Böswirth, B. Boeswirth, B. Boswirth, Bernd Boeswirth, Bernd Boswirth, Bernd Böswirth, Boeswirth, B. ; https://orcid.org/0000-0002-9317-6261, Böswirth, B., Böswirth, B. ; https://orcid.org/0000-0002-9317-6261, Böswirth, Bernd

Institution: Max Planck Institute for Plasma Physics

Observed institutions: University of Rome Tor Vergata, Max Planck Society, Commissariat à l'Énergie Atomique et aux Énergies Alternatives, CEA Cadarache, Max Planck Institute for Plasma Physics - Greifswald, Max Planck Institute for Plasma Physics

ORCID: 0000-0002-9317-6261

Observed ORCID: 0000-0002-9317-6261

OpenAlex ID: A5011704851

Overview of first Wendelstein 7-X high-performance operation

2019 · T. Klinger, T. Andreeva, et al. · Nuclear Fusion · 248

Demonstration of reduced neoclassical energy transport in Wendelstein 7-X

2021 · C. D. Beidler, H. M. Smith, et al. · Nature · 169

High heat flux facility GLADIS:

2007 · H. Greuner, B. Boeswirth, et al. · Journal of Nuclear Materials · 165

European divertor target concepts for DEMO: Design rationales and high heat flux performance

2018 · J.H. You, E. Visca, et al. · Nuclear Materials and Energy · 155

Divertor of the European DEMO: Engineering and technologies for power exhaust

2022 · J.H. You, G. Mazzone, et al. · Fusion Engineering and Design · 146

Divertor Tokamak Test facility project: status of design and implementation

2024 · Francesco Romanelli, on behalf of DTT Contributors, et al. · Nuclear Fusion · 87

Vacuum plasma-sprayed tungsten on EUROFER and 316L: Results of characterisation and thermal loading tests

2005 · H. Greuner, H. Bolt, et al. · Fusion Engineering and Design · 82

High-heat-flux technologies for the European demo divertor targets: State-of-the-art and a review of the latest testing campaign

2020 · J.H. You, E. Visca, et al. · Journal of Nuclear Materials · 80

Recrystallization and grain growth behavior of rolled tungsten under VDE-like short pulse high heat flux loads

2012 · Y. Yuan, H. Greuner, et al. · Journal of Nuclear Materials · 63

Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X

2021 · Thomas Sunn Pedersen, I. Abramovic, et al. · Nuclear Fusion · 56

Design, performance and construction of a 2MW ion beam test facility for plasma facing components

2005 · H. Greuner, H. Bolt, et al. · Fusion Engineering and Design · 53

Overview of physics studies on ASDEX Upgrade

2019 · H. Meyer, C. Angioni, et al. · Nuclear Fusion · 50

Performance assessment of thick W/Cu graded interlayer for DEMO divertor target

2020 · M. Richou, F. Gallay, et al. · Fusion Engineering and Design · 46

Application of tungsten–copper composite heat sink materials to plasma-facing component mock-ups

2020 · A v Müller, B Böswirth, et al. · Physica Scripta · 40

Irradiation effects of hydrogen and helium plasma on different grade tungsten materials

2017 · X. Liu, Y.Y. Lian, et al. · Nuclear Materials and Energy · 40

Investigation of W components exposed to high thermal and high H/He fluxes

2010 · H. Greuner, H. Maier, et al. · Journal of Nuclear Materials · 39

Surface modification of molten W exposed to high heat flux helium neutral beams

2013 · Y. Yuan, H. Greuner, et al. · Journal of Nuclear Materials · 37

Qualification of tungsten coatings on plasma-facing components for JET

2009 · H Maier, R Neu, et al. · Physica Scripta · 34

Final design of W7-X divertor plasma facing components—tests and thermo-mechanical analysis of baffle prototypes

2003 · H Greuner, B Böswirth, et al. · Fusion Engineering and Design · 34

Manufacturing and testing of ITER-like divertor plasma facing mock-ups for DEMO

2018 · Eliseo Visca, B. Böswirth, et al. · Fusion Engineering and Design · 33

High-heat-flux performance limit of tungsten monoblock targets: Impact on the armor materials and implications for power exhaust capacity

2022 · Jeong-Ha You, Henri Greuner, et al. · Nuclear Materials and Energy · 32

Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development

2021 · U. Stroth, D. Aguiam, et al. · Nuclear Fusion · 32

Overview of the different processes of tungsten coating implemented into WEST tokamak

2017 · M. Firdaouss, C. Desgranges, et al. · Fusion Engineering and Design · 32

Realization of high heat flux tungsten monoblock type target with graded interlayer for application to DEMO divertor

2017 · M Richou, F Gallay, et al. · Physica Scripta · 28

Design improvement of the target elements of Wendelstein 7-X divertor

2012 · J. Boscary, A. Peacock, et al. · Fusion Engineering and Design · 28

Works count: 156

Citation count: 2,564

H-index: 26

I10-index: 59