Z. E. Ostrovsky - Concepedia

Author

Z. E. Ostrovsky

State Scientific Center - Research Institute of Atomic Reactors

Also Known As

Z Ostrovsky, Z. E. OSTROVSKY, Z. E. Ostrovsky, Z. Ostrovsky, Z.E Ostrovsky, Z.E. Ostrovsky, ZE Ostrovsky

Publications

456

Citations

H-Index

Concepts

All Affiliations

State Scientific Center - Research Institute of Atomic Reactors "VNIINM" named after AA Bochvar

About

Z. E. Ostrovsky is an author at State Scientific Center - Research Institute of Atomic Reactors specializing in materials science, engineering, and microstructure.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	10	11	274
2	Applied Physics	5	5	175
3	Materials Engineering	5	5	176
4	Chemical Engineering	2	2	34
5	Chemistry	1	1	17

Z. E. Ostrovsky

Publications

274

Citations

H-Index

Page 1

	Year	Citations
Influence of Structure—Phase State of Nb Containing Zr Alloys on Irradiation-Induced Growth V. N. Shishov, M. M. Peregud, A. V. Nikulina, Journal of ASTM International Materials EngineeringMaterials ScienceCrystal StructureHigh Temperature MaterialsEngineering	2005	57
Structure-Phase State, Corrosion and Irradiation Properties of Zr-Nb-Fe-Sn System Alloys V. N. Shishov, M. M. Peregud, A. V. Nikulina, Journal of ASTM International Materials ScienceMaterials EngineeringUnique Corrosion ResistanceEngineeringHigh Temperature Materials	2008	51
Mechanical properties and microstructure of advanced ferritic–martensitic steels used under high dose neutron irradiation V.K. Shamardin, T.M. Bulanova, A.V Povstianko, Journal of Nuclear Materials Materials ScienceEngineeringMechanical PropertiesRadiation Materials ScienceMechanical Engineering	1999	29
Irradiation-Induced Growth and Microstructure of Recrystallized, Cold Worked and Quenched Zircaloy-2, NSF, and E635 Alloys G. P. Kobylyansky, A. E. Novoselov, Z. E. Ostrovsky, Journal of ASTM International EngineeringIrradiation GrowthMechanical EngineeringIrradiation-induced GrowthCold Worked	2008	27
Investigation of ITER candidate beryllium grades irradiated at high temperature I.B. Kupriyanov, R.R. Mel'der, Z. E. Ostrovsky, Journal of Nuclear Materials Materials ScienceMaterials EngineeringNuclear CeramicHigh Temperature MaterialsEngineering	1998	24
Radiation Damage of E635 Alloy Under High Dose Irradiation in the VVER-1000 and BOR-60 Reactors G. P. Kobylyansky, A. E. Novoselov, Z. E. Ostrovsky, Journal of ASTM International EngineeringRadiation Materials ScienceRadiation EffectRadiation ExposureFusion Materials	2011	17
Structure and properties of hafnium after a 9-year operation in the RBT-6 research reactor V.D. Risovany, V.I. Prokhorov, Z. E. Ostrovsky, Journal of Nuclear Materials Materials ScienceChemical EngineeringEngineeringChemistryHydrogen	2010	17
High dose neutron irradiation damage in beryllium as blanket material V. Chakin, A.A. Teykovtsev, V.V. Pimenov, Fusion Engineering and Design Materials ScienceEngineeringRadiation EffectApplied PhysicsNeutron Source	2001	16
Radiation embrittlement of Mo–Re welds under low-temperature irradiation in the SM reactor V. Chakin, Fumio Morito, Yu.D. Goncharenko, Journal of Nuclear Materials Materials ScienceLow-temperature IrradiationEngineeringRadiation EmbrittlementCorrosion	1998	14
Formation of the σ-phase in Cr-Fe alloys under irradiation V. Chakin, Yu.D. Goncharenko, Z. E. Ostrovsky Journal of Nuclear Materials Materials ScienceEngineeringAlloy DesignCr-fe AlloysAlloy Phase	1996	12

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