Carsten Bonnekoh
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Carsten Bonnekoh has a total of 105 co-authors. Here are the top co-authors by number of shared publications:
- Michael Rieth
Institute for Applied Materials, Karlsruhe Institute of Technology, 76344 Karlsruhe, Germany
14 shared publications Andreas Hoffmann
8 shared publicationsJens Reiser
8 shared publicationsMichael Klimenkov
6 shared publicationsUte Jäntsch
5 shared publicationsJan Hoffmann
4 shared publications
Latest Publications
- Open Access
- 16 August 2026
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 633
Tensile and Charpy impact properties of EUROFER97-3 and three RAFM steels after neutron irradiation at 330 ºC and 540 ºC to damage doses of 19-24 dpa
- 16 August 2026
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 633
Open AccessTensile and Charpy impact properties of EUROFER97-3 and three RAFM steels after neutron irradiation at 330 ºC and 540 ºC to damage doses of 19-24 dpa
- 11 August 2026
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 633
Effect of thermal neutron shielding on the irradiation hardening and recrystallization of tungsten
- 11 August 2026
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 633
Effect of thermal neutron shielding on the irradiation hardening and recrystallization of tungsten
- Open Access
- 2 February 2026
- Published by Elsevier in Nuclear Materials and Energy
- Vol. 46
Charpy impact properties of EUROFER97-3 after neutron irradiation at 330 °C and 540 °C to damage doses of 21–23 dpa
- 2 February 2026
- Published by Elsevier in Nuclear Materials and Energy
- Vol. 46
Open AccessCharpy impact properties of EUROFER97-3 after neutron irradiation at 330 °C and 540 °C to damage doses of 21–23 dpa
- Open Access
- 25 November 2025
- Published by Elsevier in Nuclear Materials and Energy
- Vol. 45
Tensile properties of EUROFER97-3 after neutron irradiation at 330 °C and 540 °C to damage doses of 19–23 dpa
- 25 November 2025
- Published by Elsevier in Nuclear Materials and Energy
- Vol. 45
Open AccessTensile properties of EUROFER97-3 after neutron irradiation at 330 °C and 540 °C to damage doses of 19–23 dpa
- Open Access
- 20 May 2025
- Published by Elsevier in Journal of Materials Research and Technology
- Vol. 36, 9262-9273
Suppression of Cr nanoclusters and enrichments in Fe–Cr based alloys with cryogenic processing for future energy sector
- 20 May 2025
- Published by Elsevier in Journal of Materials Research and Technology
- Vol. 36, 9262-9273
Open AccessSuppression of Cr nanoclusters and enrichments in Fe–Cr based alloys with cryogenic processing for future energy sector
- Open Access
Microstructure of CuCrZrV and ODS(Y2O3)-Cu Alloys After Neutron Irradiation at 150, 350, and 450 °C to 2.5 dpa
In this study, the results of transmission electron microscopy (TEM) examinations of neutron-irradiated (2.5 dpa at 150 °C, 350 °C, and 450 °C) CuCrZrV and ODS(Y2O3)-Cu alloys are presented. These materials were developed for application as heat sink materials in fusion technology. This study includes TEM imaging and quantitative analysis of neutron radiation-induced defects such as dislocation loops and voids as well as the determination of the conditions for their formation. It was found that dislocation loops of a0½⟨110⟩ type form in both alloys at all irradiation temperatures. The formation of voids in CuCrZrV alloy is effectively suppressed. The neutron irradiation causes a redistribution of Cr, Zr, and V in the CuCrZrV alloy. A particular focus was on the investigation of the distribution of the transmutation products Ni and Zn. Ni tends to segregate at the Cr-rich clusters and forms a shell around them, while Zn is evenly distributed.
Open AccessMicrostructure of CuCrZrV and ODS(Y2O3)-Cu Alloys After Neutron Irradiation at 150, 350, and 450 °C to 2.5 dpa
In this study, the results of transmission electron microscopy (TEM) examinations of neutron-irradiated (2.5 dpa at 150 °C, 350 °C, and 450 °C) CuCrZrV and ODS(Y2O3)-Cu alloys are presented. These materials were developed for application as heat sink materials in fusion technology. This study includes TEM imaging and quantitative analysis of neutron radiation-induced defects such as dislocation loops and voids as well as the determination of the conditions for their formation. It was found that dislocation loops of a0½⟨110⟩ type form in both alloys at all irradiation temperatures. The formation of voids in CuCrZrV alloy is effectively suppressed. The neutron irradiation causes a redistribution of Cr, Zr, and V in the CuCrZrV alloy. A particular focus was on the investigation of the distribution of the transmutation products Ni and Zn. Ni tends to segregate at the Cr-rich clusters and forms a shell around them, while Zn is evenly distributed.
- Open Access
- 11 January 2025
- Published by Elsevier in Corrosion Science
- Vol. 245
Understanding nanoscale oxide build up on EUROFER97
- 11 January 2025
- Published by Elsevier in Corrosion Science
- Vol. 245
Open AccessUnderstanding nanoscale oxide build up on EUROFER97
- Open Access
- 29 May 2024
- Published by Elsevier in Nuclear Materials and Energy
- Vol. 39
Additive manufacturing of novel complex tungsten components via electron beam melting: Basic properties and evaluation of the high heat flux behavior
- 29 May 2024
- Published by Elsevier in Nuclear Materials and Energy
- Vol. 39
Open AccessAdditive manufacturing of novel complex tungsten components via electron beam melting: Basic properties and evaluation of the high heat flux behavior
- Open Access
- 16 May 2024
- Published by Elsevier in Applied Surface Science
- Vol. 665
Designing advanced high-Cr ferrous alloys for next-generation energy applications through cryogenic processing
- 16 May 2024
- Published by Elsevier in Applied Surface Science
- Vol. 665
Open AccessDesigning advanced high-Cr ferrous alloys for next-generation energy applications through cryogenic processing