Dmitry Terentyev

Research output

Research output per year 2003 2008 2009 2010 2011 2013 2015 2016 2017 2018 2019 2020 2021 2022 2023 2025

• 315 Article
• 34 In-proceedings paper
• 13 BLG - Open report
• 5 Special issue
• 9 More
  • 4 ER - External report
  • 4 Doctoral thesis
  • 1 Chapter

Research output per year

Research output per year

Search results

• 2025

  Prediction of low cycle fatigue life for neutron-irradiated and nonirradiated RAFM steels using their tensile properties

  Zahran, H., Zinovev, A., Terentyev, D., Aiello, G. & Abdel Wahab, M., Jan 2025, In: International Journal of Fatigue. 190, 17 p., 108589.

  Research output › peer-review

• Small punch test size reduction to enable high flux irradiation

  Li, Z., Terentyev, D., Holmström, S. & Pardoen, T., Jan 2025, In: Journal of Nuclear Materials. 604, 155491, 13 p., 155491.

  Research output › peer-review
• 2024

  Comparative study of ITER conform tungsten grades exposed to high heat flux and neutron irradiation damage

  Terentyev, D., Wirtz, M., Morgan, T. W., Nozawa, T., Zinovev, A., Chang, C.-C., Poleshchuk, K. & Elenbaas, J., Mar 2024, In: Fusion Engineering & Design. 200, 8 p., 114200.

  Research output › peer-review

  Open Access

• Contributions of MYRRHA to the European Fusion Energy Roadmap

  Van Oost, G., Terentyev, D. & Abderrahim, H. A., Jan 2024, In: fusion engineering and design. 198, 10 p., 114098.

  Research output › peer-review

  Open Access

• Experimental investigation and constitutive material modelling of low cycle fatigue of EUROFER97 for fusion applications

  Zahran, H., Zinovev, A., Terentyev, D., Wang, X. & Abdel Wahab, M., Jan 2024, In: Journal of Nuclear Materials. 588, 16 p., 154809.

  Research output › peer-review

  Open Access

• IFMIF/EVEDA achievements overview

  the IFMIF/EVEDA Team, Apr 2024, In: Fusion Engineering and Design.. 201, 5 p., 114258.

  Research output › peer-review

  Open Access

• Influence of transmutation-induced Re/Os content on defect evolution in neutron-irradiated W

  Klimenkov, M., Jäntsch, U., Rieth, M., Schneider, H.-C., Terentyev, D. & Van Renterghem, W., 15 Apr 2024, In: Journal of Nuclear Materials. 592, 12 p., 154950.

  Research output › peer-review

  Open Access

• Initial microstructure and temperature dependence of irradiation defects evolution in tungsten

  Ma, H. Z., Li, Y. H., Niu, Y. Z., Terentyev, D., Yang, Z., Zhou, H. B. & Lu, G. H., 1 Apr 2024, In: Journal of Nuclear Materials. 591, 11 p., 154932.

  Research output › peer-review

• In-situ TEM investigation of recovery mechanisms in ion-irradiated ITER-grade tungsten

  Iroc, K., Terentyev, D., Van Renterghem, W., Dunatov, T., Tadić, T., Klimenkov, M., Baumier, C., Gentils, A. & Schryvers, D., Oct 2024, In: Journal of Nuclear Materials. 599, 17 p., 155223.

  Research output › peer-review

  Open Access

• Low cycle fatigue of EUROFER97 investigated for test blanket modules of ITER: An interlaboratory study

  Zinovev, A., Lamagnère, P., Poleshchuk, K., Terentyev, D., Bernardi, D., Cristalli, C., Leon-Gutierrez, E., García-Rodríguez, N., Caes, C., Pintsuk, G. & Aiello, G., Aug 2024, In: Journal of Nuclear Materials. 597, 10 p., 155127.

  Research output › peer-review

  Open Access

• Microstructural changes induced in advanced tungsten grades under high temperature neutron irradiation

  Van Renterghem, W., Iroc, K., Terentyev, D., Antusch, S. & Rieth, M., Aug 2024, In: International Journal of Refractory Metals & Hard Materials. 122, 11 p., 106718.

  Research output › peer-review

  Open Access

• TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000°C under 40keV He⁺ irradiation

  Ipatova, I., Greaves, G., Terentyev, D., Gilbert, M. R. & Chiu, Y. L., Apr 2024, In: Nuclear Engineering and Technology. 56, 4, p. 1490-1500 11 p.

  Research output › peer-review

  Open Access

• Thermal creep properties of virgin and irradiated cladding tubes made of Ti-stabilised DIN 1.4970 (15-15Ti) austenitic stainless steel

  Holmström, S., Delville, R. & Terentyev, D., 2024, In: Materials At High Temperatures. 41, 2, p. 284-293 10 p.

  Research output › peer-review

  Open Access
• 2023

  Defect evolution of neutron irradiated ITER grade tungsten after annealing

  Papadakis, D., Mergia, K., Manios, E., Chatzikos, V., Spilios, D., Bonny, G., Van Renterghem, W., Terentyev, D., Chang, C.-C. & Messoloras, S., Apr 2023, In: Fusion Engineering & Design. 189, 8 p., 113486.

  Research output › peer-review

  Open Access

• Development of sub-miniaturised testing methodology for W/Cu joints extracted from the ITER-specification monoblock

  Poleshchuk, K., Terentyev, D., Chang, C.-C., Galatanu, A., Gavrilov, S., Zhou, H. & Verbeken, K., Sep 2023, In: Fusion Engineering & Design. 194, 8 p., 113925.

  Research output › peer-review

  Open Access

• Effect of neutron irradiation on tensile properties of advanced Cu-based alloys and composites developed for fusion applications

  Terentyev, D., Rieth, M., Pintsuk, G., Müller, A. V., Antusch, S., Zinovev, A., Bakaev, A., Poleshchuk, K. & Aiello, G., Oct 2023, In: Journal of Nuclear Materials. 584, 20 p., 154587.

  Research output › peer-review

• Effect of neutron irradiation to 0.7 and 1.4 dpa on the tensile mechanical properties and microstructure of EUROFER97 steel

  Zinovev, A., Chang, C.-C., Eyken, J. V., Gaganidze, E. & Terentyev, D., May 2023, In: Science Talks. 6, 7 p., 100214.

  Research output › peer-review

• Effect of neutron irradiation to 0.7 dpa and 1.4 dpa on the tensile properties and fracture surface of EUROFER97 steel

  Zinovev, A., Chang, C. C., Van Eyken, J., Gaganidze, E. & Terentyev, D., 15 Dec 2023, In: Journal of Nuclear Materials. 587, 11 p., 154742.

  Research output › peer-review

• Estimation of fretting fatigue lifetime in heterogeneous material based on microstructure characterization and multi-scale homogenization

  Wang, C., Zinovev, A., Terentyev, D., Wang, D. & Abdel Wahab, M., Aug 2023, In: Theoretical and Applied Fracture Mechanics. 126, 16 p., 103949.

  Research output › peer-review

  Open Access

• Fretting fatigue crack propagation under out-of-phase loading conditions using extended maximum tangential stress criterion

  Wang, C., Pereira, K., Wang, D., Zinovev, A., Terentyev, D. & Abdel Wahab, M., Sep 2023, In: Tribology International. 187, 15 p., 108738.

  Research output › peer-review
  3 Scopus citations

• Fusion-dedicated material irradiation facilities at MYRRHA: Conceptual design and damage equivalence studies

  Terentyev, D., Leysen, W., Castin, N., Chang, C.-C., Kennedy, G., Stankovskiy, A. & Fiorito, L., Jun 2023, In: Fusion Engineering & Design. 191, 15 p., 113764.

  Research output › peer-review

  Open Access

• Hardening mechanisms of cold rolled tungsten after neutron irradiation Indentation and finite elements modelling

  Spilios, D., Xiao, X., Terentyev, D., Manios, E. & Mergia, K., Feb 2023, In: International Journal of Refractory Metals & Hard Materials. 111, 12 p., 106096.

  Research output › peer-review

  Open Access

• Influence of carbon on the evolution of irradiation defects in tungsten

  Niu, Y.-Z., Li, Y.-H., Ren, Q.-Y., Terentyev, D., Ma, H.-Z., Zhou, H.-B. & Lu, G.-H., Jun 2023, In: Journal of Nuclear Materials. 579, 11 p., 154393.

  Research output › peer-review

  Open Access

• Influence of rhenium-decorated dislocation loops on edge dislocation gliding in tungsten

  Yang, T.-R., Li, Y.-H., Ren, Q.-Y., Terentyev, D., Xie, H.-X., Gao, N., Zhou, H.-B., Gao, F. & Lu, G.-H., Oct 2023, In: Scripta Materialia. 235, 6 p., 115624.

  Research output › peer-review

  Open Access

• Interaction of edge dislocations with voids in tungsten

  Kazakov, A. M., Babicheva, R. I., Zinovev, A., Terentyev, D., Zhou, K., Korznikova, E. A. & Dmitriev, S. V., Dec 2023, (Accepted/In press) In: Tungsten. 14 p.

  Research output › peer-review

• Macro-scale modeling of finite strain viscoplasticity in irradiated F/M steels: a continuum thermodynamic framework

  Rajakrishnan, R. R., Gaganidze, E., Terentyev, D. & Aktaa, J., Mar 2023, In: Continuum Mechanics and Thermodynamics. 35, 2, p. 521-543 23 p.

  Research output › peer-review

  Open Access

• Mechanical properties of structural metallic alloys for nuclear applications deduced by small punch test

  Melkior, T., Terentyev, D., Chang, C.-C., Bakaev, A., Holmström, S., Lebediev, S. & Paputsia, A., Sep 2023, In: Journal of Nuclear Materials. 583, 33 p., 154521.

  Research output › peer-review

• On the equivalence of mini-flat and cylindrical tensile geometries to extract hardening law and ductility of Eurofer97

  Chang, C.-C., Terentyev, D., Bakaev, A., Zinovev, A., Serra, D. D., Verleysen, P. & Pardoen, T., Sep 2023, In: fusion engineering and design. 194, 12 p., 113717.

  Research output › peer-review

• On the microstructure evolution in tungsten ITER monoblocks: a computational study

  Castin, N., Van den Kerkhof, S., Bonny, G. & Terentyev, D., 25 Feb 2023, In: Computational Materials Science. 219, 13 p., 112001.

  Research output › peer-review

  Open Access

• TEM investigation of reduced activation ferritic/martensitic alloys developed by thermodynamic modeling

  Kachko, O., Puype, A., Terentyev, D., Duerrschnabel, M., Klimenkov, M. & Petrov, R., 15 Aug 2023, In: Journal of Nuclear Materials. 582, 11 p., 154480.

  Research output › peer-review
• 2022

  Application of sub-miniaturized bending tests to extract tensile properties from neutron-irradiated metallic alloys

  Bakaev, A., Terentyev, D., Zinovev, A., Chang, C.-C., Yin, C., Bakaev, V. A. & Zhurkin, E. E., Jan 2022, In: Journal of Nuclear Materials. 558, p. 1-19 19 p., 153320.

  Research output › peer-review

  Open Access

• Atomic-level study on the interaction of plastic slip with Σ3{112} tilt grain boundary and {112} twins in bcc metals

  Anento, N., Kvashin, N., Terentyev, D. & Serra, A., 25 Mar 2022, In: Physical Review Materials. 6, 3, 033606 .

  Research output › peer-review

  Open Access

• Comparison experiment on the sputtering of EUROFER, RUSFER and CLAM steels by deuterium ions: Journal Pre-proofs

  Arrendo, R., Balden, M., Schwarz-Selinger, T., Höschen, T., Dürbeck, T., Hunger, K., Schlueter, K., Golubeva, A., Wang, P., Terentyev, D. & Jacob, W., 10 Jan 2022, In: Nuclear Materials and Energy. p. 1-10 10 p., 101118.

  Research output › peer-review

  Open Access

• Development of irradiation tolerant tungsten alloys for high temperature nuclear applications

  Terentyev, D., Jenus, P., Sal, E., Zinovev, A., Chang, C.-C., Garcia-Rosales, C., Kocen, M., Novak, S. & Van Renterghem, W., 27 Jun 2022, In: Nuclear Fusion. 62, 8, p. 1-17 17 p., 086035.

  Research output › peer-review

  Open Access

• Development of RAFM steels for high temperature applications guided by thermodynamic modelling

  Kachko, O., Puype, A., Terentyev, D., Bonny, G., Van Renterghem, W. & Petrov, R., Sep 2022, In: Nuclear Materials and Energy. 32, p. 1-11 11 p., 101211.

  Research output › peer-review

  Open Access

• Divertor of the European DEMO: engineering and technologies for power exhaust

  You, J.-H., Mazzone, G., Visca, E., Greuner, H., Fursdon, M., Addab, Y., Bachmann, C., Barrett, T., Bonavolontà, U., Böswirth, B., Castrovinci, F. M., Carelli, C., Coccorese, D., Coppola, R., Crescenzi, F., Di Ginonimo, G., Di Maio, P. A., Di Mambro, G., Domptail, F. & Dongiovanni, D. & 29 others, Dose, G., Flammini, D., Forest, L., Frosi, P., Gallay, F., Ghidersa, B.-E., Harrington, C., Hunger, K., Imbriani, V., Li, M., Lukenskas, A., Maffucci, A., Mantel, N., Marzullo, D., Minniti, T., von Müller, A., Noce, S., Porfiri, M. T., Suartararo, A., Richou, M., Roccella, S., Terentyev, D., Tincani, A., Vallone, E., Ventre, S., Villari, R., Villone, F., Vorpahl, C. & Zhang, K., Feb 2022, In: Fusion Engineering & Design. 175, 36 p., 113010.

  Research output › peer-review

  Open Access

• Effect of irradiation defects on the plastic slip of {112} grain boundary atomic scale study

  Kvashin, N., Terentyev, D., Serra, A. & Anento, N., 24 Aug 2022, In: Computational Materials Science. 214, p. 1-9 9 p., 111739.

  Research output › peer-review

  Open Access

• Effect of neutron irradiation on ductility of tungsten foils developed for tungsten-copper laminates

  Zinovev, A., Terentyev, D., Chang, C.-C., Yin, C., Bakaev, A., Rieth, M., Lied, P., Reiser, J. & Bonnekoh, C., 10 Feb 2022, In: Nuclear Materials and Energy. 30, p. 1-10 10 p., 101133.

  Research output › peer-review

  Open Access

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• Effect of radiation defects on the early stages of nanoindentation tests in bcc Fe and Fe-Cr alloys

  Bakaev, A., Zhao, J., Terentyev, D., Bonny, G., Castin, N., Kuronen, A., Kvashin, N., Nordlund, K., Bakaev, V. A. & Golikov, I. G., Mar 2022, In: Computational Materials Science. 204, p. 1-18 18 p., 111151.

  Research output › peer-review

  Open Access

• Effect of temperature on the neutron irradiation-induced cavities in tungsten

  Chauhan, A., Yuan, Q., Litvinov, D., Gaganidze, E., Schneider, H.-C., Terentyev, D. & Aktaa, J., 2022, In: Philosophical Magazine. 102, 17, p. 1665-1683 18 p.

  Research output › peer-review

  Open Access

• High temperature nanoindentation of iron: experimental and computational study

  Khvan, T., Noels, L., Terentyev, D., Dencker, F., Stauffer, D., Hangen, U. D., Van Renterghem, W., Chang, C.-C. & Zinovev, A., 24 May 2022, In: Journal of Nuclear Materials. 153815.

  Research output › peer-review

  Open Access

• Irradiation hardening of advanced tungsten grades: An experimental and inverse finite element method study

  Bakaev, A., Terentyev, D., Zinovev, A. & Zhurkin, E. E., Jun 2022, In: International Journal of Refractory Metals & Hard Materials. 105, p. 1-10 10 p., 105839.

  Research output › peer-review

  Open Access

• Materials for in-vessel components

  Pintsuk, G., Aiello, G., Dudarev, S. L., Gorley, M., Henry, J., Richou, M., Rieth, M., Terentyev, D. & Vila, R., 3 Jan 2022, In: Fusion Engineering & Design. 174, p. 1-21 21 p., 112994.

  Research output › peer-review

  Open Access

• Microstructural analysis of W irradiated at different temperatures

  Klimenkov, M., Dürrschnabel, M., Jäntsch, U., Lied, P., Rieth, M., Schneider, H.-C., Terentyev, D. & Van Renterghem, W., 5 Sep 2022, In: Journal of Nuclear Materials. 572, p. 1-14 14 p., 154018.

  Research output › peer-review

  Open Access

• Modeling Crack Initiation in Low Cycle Fatigue: A Review

  Zahran, H., Zinovev, A., Terentyev, D. & Abdel Wahab, M., 3 Dec 2022, Lecture Notes in Mechanical Engineering: Proceedings of the 10th International Conference on Fracture Fatigue and Wear . Springer Singapore, p. 79-89 11 p. (Lecture Notes in Mechanical Engineering).

  Research output › peer-review

• Modification of Surfaces of Reduced-Activation Ferritic–Martensitic Steels upon Irradiation by Pulsed Deuterium Plasma with Parameters Typical for Peripheral Plasma Disruption

  Golubeva, A., Kovalenko, D. V., Lidzhigoryaev, S. D., Barsuk, V. A., Bobyr, N. P., Mednikov, A. A., Klimov, N. S., Huang, Q., Terentyev, D., Ashikawa, N. & Chernov, V. M., Feb 2022, In: Journal of Surface Investigation. X-ray, Synchrotron and Neutron Techniques. 16, 1, p. 23-32 10 p.

  Research output › peer-review

  Open Access

• On the equivalence of irradiation conditions on present and future facilities for fusion materials research and qualification: a computational study

  Castin, N., Terentyev, D., Bakaev, A., Stankovskiy, A. & Bonny, G., 7 Feb 2022, In: Journal of Nuclear Materials. 562, p. 1-20 20 p., 153589.

  Research output › peer-review

  Open Access

• Positron annihilation spectroscopy investigation of defects in neutron irradiated tungsten materials

  Chatzikos, V., Mergia, K., Bonny, G., Terentyev, D., Papadakis, D., Pavlou, G. E. & Messoloras, S., Jun 2022, In: International Journal of Refractory Metals & Hard Materials. 105, 13 p., 105838.

  Research output › peer-review

  Open Access

• Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys

  Terentyev, D., Rieth, M., Pintsuk, G., Riesch, J., von Müller, A., Antusch, S., Mergia, K., Gaganidze, E., Schneider, H.-C., Wirtz, M., Nogami, S., Coenen, J. W., You, J.-H., Zinovev, A. & Van Renterghem, W., 6 Jan 2022, In: Nuclear Fusion. 62, 2, 15 p., 026045.

  Research output › peer-review

  Open Access

• Selective sputtering of eurofer steel by deuterium plasma

  Golubeva, A., Khripunov, V. I., Alimov, V. K., Bobyr, N. P., Terentyev, D. & Kukueva, E. V., 3 Aug 2022, In: Journal of Surface Investigation. X-ray, Synchrotron and Neutron Techniques. 16, p. 469–479 11 p.

  Research output › peer-review