Dmitry Terentyev
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Dmitry Terentyev has a total of 102 co-authors. Here are the top co-authors by number of shared publications:
- Aleksandr Zinovev
LHMA, SCK-CEN, Mol, BELGIUM
4 shared publications - Carsten Bonnekoh
Karlsruhe Institute of Technology, Institute for Applied Materials, 76344 Eggenstein-Leopoldshafen, Germany
3 shared publications - Giacomo Aiello3 shared publications
- Wouter Van Renterghem
Institute of Nuclear Materials Science, SCK CEN, 2400 Mol, Belgium
3 shared publications - Alexander Bakaev
Belgian Nuclear Research Centre, Institute of Nuclear Materials Science, Boeretang 200, 2400 Mol, Belgium
2 shared publications - Alexey Stankovskiy
Belgian Nuclear Research Centre, Institute of Nuclear Materials Science, Boeretang 200, 2400 Mol, Belgium
2 shared publications
Latest Publications
- Open Access
- 20 October 2026
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 635
Qualification of EUROFER97 and design rule validation for ITER TBM: EUROfusion contribution
- 20 October 2026
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 635
Open AccessQualification of EUROFER97 and design rule validation for ITER TBM: EUROfusion contribution
- Open Access
- 5 October 2026
- Published by Elsevier in Fusion Engineering and Design
- Vol. 233
Fracture toughness of European reference RAFM steel EUROFER97
- 5 October 2026
- Published by Elsevier in Fusion Engineering and Design
- Vol. 233
Open AccessFracture toughness of European reference RAFM steel EUROFER97
- 28 September 2026
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 634
Yield stress of nuclear structural metallic alloys deduced from three-point bend testing
- 28 September 2026
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 634
Yield stress of nuclear structural metallic alloys deduced from three-point bend testing
- 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
- 4 August 2026
- Published by Elsevier in Fusion Engineering and Design
- Vol. 231
The roles of different nuclear facilities for the qualification of the breeding blanket
- 4 August 2026
- Published by Elsevier in Fusion Engineering and Design
- Vol. 231
The roles of different nuclear facilities for the qualification of the breeding blanket
- 27 June 2026
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 632
Microstructural response of high-temperature neutron-irradiated different grades of tungsten
- 27 June 2026
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 632
Microstructural response of high-temperature neutron-irradiated different grades of tungsten
- Open Access
- 14 June 2026
- Published by Elsevier in Fusion Engineering and Design
- Vol. 230
DEMO design criteria for in-vessel components – strategic vision and overarching considerations
- 14 June 2026
- Published by Elsevier in Fusion Engineering and Design
- Vol. 230
Open AccessDEMO design criteria for in-vessel components – strategic vision and overarching considerations
- Open Access
Gamma Irradiation Effect on the Verdet Constant of Standard Single-Mode Ge-Doped Optical Fibre
Optical fibres are considered for applications in various nuclear environments in the presence of radiation exposure. Under irradiation, the properties of the optical fibres are modified. In the present paper we investigate the influence of gamma radiation on the magneto-optical properties of the Corning SMF-28e optical fibre. The stability of the Verdet constant is an important requirement for performing current measurements under radiation, for example, in magnetic fusion installations during nuclear (deuterium–tritium) plasma operation, where radiation at MGy dose levels can be accumulated. Our results demonstrate that radiation-induced changes in the Verdet constant are within its measurement accuracy (0.56%) for gamma radiation doses up to 770 kGy.
Open AccessGamma Irradiation Effect on the Verdet Constant of Standard Single-Mode Ge-Doped Optical Fibre
Optical fibres are considered for applications in various nuclear environments in the presence of radiation exposure. Under irradiation, the properties of the optical fibres are modified. In the present paper we investigate the influence of gamma radiation on the magneto-optical properties of the Corning SMF-28e optical fibre. The stability of the Verdet constant is an important requirement for performing current measurements under radiation, for example, in magnetic fusion installations during nuclear (deuterium–tritium) plasma operation, where radiation at MGy dose levels can be accumulated. Our results demonstrate that radiation-induced changes in the Verdet constant are within its measurement accuracy (0.56%) for gamma radiation doses up to 770 kGy.
- 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.