D. Terentyev - Concepedia

Concepedia

Author

D. Terentyev

Belgian Nuclear Research Centre

Also Known As

D Terentyev, D. A. Terentyev, D. Terentyev

50

Publications

1.8K

Citations

24

H-Index

40

Concepts

All Affiliations

Belgian Nuclear Research Centre Université Libre de Bruxelles Ghent University University of Helsinki University of Liverpool

DT

About

D. Terentyev is an author at Belgian Nuclear Research Centre specializing in engineering, materials science, and physics.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	19	26	1.2K
2	Materials Science	15	20	750
3	Applied Physics	13	15	622
4	Materials Engineering	8	8	314
5	Natural Sciences	2	2	222

D. Terentyev

×

33

Publications

1.8K

Citations

24

H-Index

	Year	Citations
Interatomic potential for studying ageing under irradiation in stainless steels: the FeNiCr model alloy G. Bonny, N. Castin, D. Terentyev Modelling and Simulation in Materials Science and Engineering	2013	300
Dimensionality of interstitial cluster motion in bcc-Fe D. Terentyev, L. Malerba, M. Hou Physical Review B EngineeringComputational ChemistryMolecular DynamicsNanoscale ModelingLow-dimensional System	2007	141
On the binding of nanometric hydrogen–helium clusters in tungsten G. Bonny, Petr Grigorev, D. Terentyev Journal of Physics Condensed Matter	2014	115
Iron chromium potential to model high-chromium ferritic alloys G. Bonny, R.C. Pasianot, D. Terentyev, The Philosophical Magazine A Journal of Theoretical Experimental and Applied Physics	2011	107
On the thermal stability of late blooming phases in reactor pressure vessel steels: An atomistic study G. Bonny, D. Terentyev, A. Bakaev, Journal of Nuclear Materials Materials ScienceEngineeringMechanical EngineeringAtomistic StudyHot Working	2013	92
Molecular dynamics simulation of displacement cascades in Fe–Cr alloys L. Malerba, D. Terentyev, Pär Olsson, Journal of Nuclear Materials EngineeringMechanical EngineeringMaterial SimulationMolecular Dynamics SimulationAlloy Phase	2004	89
On the correlation between self-interstitial cluster diffusivity and irradiation-induced swelling in Fe–Cr alloys D. Terentyev, L. Malerba, A.V. Barashev Philosophical Magazine Letters Cr AtomsEngineeringFe–cr AlloysMicrostructure-strength RelationshipMaterials Engineering	2005	87
The EU programme for modelling radiation effects in fusion reactor materials: An overview of recent advances and future goals S. L. Dudarev, Jean-Louis Boutard, R. Lässer, Journal of Nuclear Materials EngineeringPhysicsFusion Reactor MaterialsControlled Nuclear FusionFusion Power	2008	85
Ab initio calculations and interatomic potentials for iron and iron alloys: Achievements within the Perfect Project L. Malerba, Graeme J. Ackland, C.S. Becquart, Journal of Nuclear Materials Materials ScienceEngineeringPhysicsIron AlloysNatural Sciences	2010	81
On the migration and trapping of single self-interstitial atoms in dilute and concentrated Fe–Cr alloys: Atomistic study and comparison with resistivity recovery experiments D. Terentyev, Pär Olsson, T.P.C. Klaver, Computational Materials Science Materials ScienceMaterials EngineeringEngineeringSingle Self-interstitial AtomsPhysics	2008	75

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