D. Terentyev

7.5k total citations
257 papers, 6.0k citations indexed

About

D. Terentyev is a scholar working on Materials Chemistry, Mechanical Engineering and Mechanics of Materials. According to data from OpenAlex, D. Terentyev has authored 257 papers receiving a total of 6.0k indexed citations (citations by other indexed papers that have themselves been cited), including 239 papers in Materials Chemistry, 104 papers in Mechanical Engineering and 55 papers in Mechanics of Materials. Recurrent topics in D. Terentyev's work include Fusion materials and technologies (222 papers), Nuclear Materials and Properties (168 papers) and Advanced materials and composites (58 papers). D. Terentyev is often cited by papers focused on Fusion materials and technologies (222 papers), Nuclear Materials and Properties (168 papers) and Advanced materials and composites (58 papers). D. Terentyev collaborates with scholars based in Belgium, Russia and Germany. D. Terentyev's co-authors include G. Bonny, L. Malerba, A. Bakaev, Е. Е. Журкин, Yu.N. Osetsky, David Bacon, Pär Olsson, A. Dubinko, Chao Yin and Petr Grigorev and has published in prestigious journals such as Physical Review Letters, Journal of Applied Physics and Physical Review B.

In The Last Decade

D. Terentyev

245 papers receiving 5.8k citations

Peers — A (Enhanced Table)

Peers by citation overlap · career bar shows stage (early→late) cites · hero ref

Name h Career Trend Papers Cites
D. Terentyev Belgium 40 5.3k 2.4k 1.1k 724 657 257 6.0k
Guang-Hong Lü China 38 5.0k 0.9× 2.0k 0.8× 1.3k 1.2× 592 0.8× 540 0.8× 286 5.6k
Richard J. Kurtz United States 37 4.1k 0.8× 1.7k 0.7× 871 0.8× 469 0.6× 506 0.8× 126 4.6k
Charlotte Becquart France 34 4.0k 0.8× 1.5k 0.6× 561 0.5× 617 0.9× 513 0.8× 99 4.4k
M. Rieth Germany 42 4.9k 0.9× 3.1k 1.3× 1.1k 1.0× 395 0.5× 405 0.6× 202 5.6k
G.R. Odette United States 38 4.9k 0.9× 2.4k 1.0× 973 0.9× 638 0.9× 792 1.2× 141 5.8k
David Rodney France 43 4.7k 0.9× 2.8k 1.2× 1.3k 1.2× 472 0.7× 358 0.5× 110 6.0k
L. Malerba Belgium 46 5.9k 1.1× 2.1k 0.9× 530 0.5× 1.0k 1.4× 895 1.4× 158 6.7k
Jaime Marian United States 40 4.3k 0.8× 2.0k 0.8× 1.1k 1.0× 550 0.8× 325 0.5× 158 5.4k
A. Arsenlis United States 26 4.9k 0.9× 3.2k 1.3× 2.1k 2.0× 335 0.5× 320 0.5× 62 6.0k
Yu.N. Osetsky United Kingdom 39 4.5k 0.8× 1.3k 0.5× 382 0.4× 1.1k 1.5× 416 0.6× 101 4.8k

Countries citing papers authored by D. Terentyev

Since Specialization
Citations

This map shows the geographic impact of D. Terentyev's research. It shows the number of citations coming from papers published by authors working in each country. You can also color the map by specialization and compare the number of citations received by D. Terentyev with the expected number of citations based on a country's size and research output (numbers larger than one mean the country cites D. Terentyev more than expected).

Fields of papers citing papers by D. Terentyev

Since Specialization
Physical SciencesHealth SciencesLife SciencesSocial Sciences

This network shows the impact of papers produced by D. Terentyev. Nodes represent research fields, and links connect fields that are likely to share authors. Colored nodes show fields that tend to cite the papers produced by D. Terentyev. The network helps show where D. Terentyev may publish in the future.

Co-authorship network of co-authors of D. Terentyev

This figure shows the co-authorship network connecting the top 25 collaborators of D. Terentyev. A scholar is included among the top collaborators of D. Terentyev based on the total number of citations received by their joint publications. Widths of edges represent the number of papers authors have co-authored together. Node borders signify the number of papers an author published with D. Terentyev. D. Terentyev is excluded from the visualization to improve readability, since they are connected to all nodes in the network.

All Works

20 of 20 papers shown
1.
Zinovev, Aleksandr, et al.. (2025). Low cycle fatigue life prediction for neutron-irradiated and nonirradiated RAFM steels via machine learning. Fusion Engineering and Design. 221. 115394–115394. 1 indexed citations
2.
Chang, Chih-Cheng, D. Terentyev, A. Bakaev, et al.. (2025). Application of mini-flat and cylindrical test specimens to extract hardening law and ductility of neutron irradiated Eurofer97. Fusion Engineering and Design. 216. 115072–115072.
3.
Klimenkov, M., Carsten Bonnekoh, M. Rieth, et al.. (2025). Microstructure of CuCrZrV and ODS(Y2O3)-Cu Alloys After Neutron Irradiation at 150, 350, and 450 °C to 2.5 dpa. Materials. 18(7). 1401–1401.
4.
Vasilopoulou, T., I. E. Stamatelatos, D. Terentyev, et al.. (2025). Experimental validation of transmutation products calculations in neutron irradiated tungsten. Fusion Engineering and Design. 215. 115012–115012. 1 indexed citations
5.
Zinovev, Aleksandr, et al.. (2024). Prediction of low cycle fatigue life for neutron-irradiated and nonirradiated RAFM steels using their tensile properties. International Journal of Fatigue. 190. 108589–108589. 5 indexed citations
6.
Renterghem, W. Van, et al.. (2024). Microstructural changes induced in advanced tungsten grades under high temperature neutron irradiation. International Journal of Refractory Metals and Hard Materials. 122. 106718–106718. 1 indexed citations
7.
Terentyev, D., et al.. (2023). Mechanical properties of structural metallic alloys for nuclear applications deduced by small punch test. Journal of Nuclear Materials. 583. 154521–154521. 11 indexed citations
8.
Chang, Chih-Cheng, D. Terentyev, A. Bakaev, et al.. (2023). On the equivalence of mini-flat and cylindrical tensile geometries to extract hardening law and ductility of Eurofer97. Fusion Engineering and Design. 194. 113717–113717. 1 indexed citations
9.
Zinovev, Aleksandr, et al.. (2023). Experimental investigation and constitutive material modelling of low cycle fatigue of EUROFER97 for fusion applications. Journal of Nuclear Materials. 588. 154809–154809. 14 indexed citations
10.
Li, Yu‐Hao, et al.. (2023). Influence of carbon on the evolution of irradiation defects in tungsten. Journal of Nuclear Materials. 579. 154393–154393. 8 indexed citations
11.
Terentyev, D., Willem Leysen, N. Castin, et al.. (2023). Fusion-dedicated material irradiation facilities at MYRRHA: Conceptual design and damage equivalence studies. Fusion Engineering and Design. 191. 113764–113764. 1 indexed citations
12.
Terentyev, D., M. Rieth, G. Pintsuk, et al.. (2023). Effect of neutron irradiation on tensile properties of advanced Cu-based alloys and composites developed for fusion applications. Journal of Nuclear Materials. 584. 154587–154587. 12 indexed citations
13.
Terentyev, D., Chih-Cheng Chang, Andrei Galatanu, et al.. (2023). Development of sub-miniaturised testing methodology for W/Cu joints extracted from the ITER-specification monoblock. Fusion Engineering and Design. 194. 113925–113925. 3 indexed citations
14.
Terentyev, D., Petra Jenuš, Aleksandr Zinovev, et al.. (2022). Development of irradiation tolerant tungsten alloys for high temperature nuclear applications. Nuclear Fusion. 62(8). 86035–86035. 16 indexed citations
15.
Terentyev, D., M. Rieth, G. Pintsuk, et al.. (2021). Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys. Nuclear Fusion. 62(2). 26045–26045. 24 indexed citations
16.
Yin, Chao, D. Terentyev, A. Dubinko, et al.. (2021). Impact of neutron irradiation on hardening of baseline and advanced tungsten grades and its link to initial microstructure. Nuclear Fusion. 61(6). 66012–66012. 14 indexed citations
17.
Morgan, T.W., J.A.W. van Dommelen, Steffen Antusch, et al.. (2020). Fracture behavior of tungsten-based composites exposed to steady-state/transient hydrogen plasma. Nuclear Fusion. 60(4). 46029–46029. 23 indexed citations
18.
Morgan, T.W., D. Terentyev, Audrey Favache, et al.. (2020). Three mechanisms of hydrogen-induced dislocation pinning in tungsten. Nuclear Fusion. 60(8). 86015–86015. 15 indexed citations
19.
20.
Bakaeva, A., D. Terentyev, T.W. Morgan, et al.. (2018). Impact of plastic deformation on retention under pure D or He high flux plasma expose. Nuclear Materials and Energy. 15. 48–54. 1 indexed citations

Rankless uses publication and citation data sourced from OpenAlex, an open and comprehensive bibliographic database. While OpenAlex provides broad and valuable coverage of the global research landscape, it—like all bibliographic datasets—has inherent limitations. These include incomplete records, variations in author disambiguation, differences in journal indexing, and delays in data updates. As a result, some metrics and network relationships displayed in Rankless may not fully capture the entirety of a scholar's output or impact.

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