N.I. Budylkin - Concepedia

Author

N.I. Budylkin

"VNIINM" named after AA Bochvar

Also Known As

N. Budylkin, N. I. Budylkin, N.I Budylkin, N.I. Budylkin, NI Budylkin

Publications

289

Citations

H-Index

Concepts

All Affiliations

"VNIINM" named after AA Bochvar Institute for Physics and Power Engineering Pacific Northwest National Laboratory State Scientific Center - Research Institute of Atomic Reactors Rosatom (Russia)

About

N.I. Budylkin is an author at "VNIINM" named after AA Bochvar specializing in materials science, engineering, and mechanical engineering.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	7	7	254
2	Materials Science	7	7	254
3	Materials Engineering	5	5	183
4	Mechanical Engineering	5	5	167
5	Applied Physics	1	1	39

N.I. Budylkin

Publications

254

Citations

H-Index

Page 1

	Year	Citations
Structural materials for fusion power reactors—the RF R&D activities N.I. Budylkin, Yu. N. Devyatko, A.G. Ioltoukhovskiy, Nuclear Fusion Materials ScienceMaterials EngineeringNuclear CeramicEngineeringIrradiation Temperature 320	2007	94
Neutron-induced swelling and embrittlement of pure iron and pure nickel irradiated in the BN-350 and BOR-60 fast reactors N.I. Budylkin, E.G. Mironova, V.A. Krasnoselov, Journal of Nuclear Materials Materials SciencePure IronEngineeringNeutron SourceNeutron-induced Swelling	2008	48
Swelling and void-induced embrittlement of austenitic stainless steel irradiated to 73–82 dpa at 335–365°C S. I. Porollo, A. N. Vorobjev, Yu. V. Konobeev, Journal of Nuclear Materials Materials EngineeringMaterials ScienceEngineeringMicrostructureApplied Physics	1998	39
Mechanical properties and microstructure of three Russian ferritic/martensitic steels irradiated in BN-350 reactor to 50dpa at 490°C A.M. Dvoriashin, S. I. Porollo, Yu. V. Konobeev, Journal of Nuclear Materials Materials ScienceEngineeringRussian Ferritic/martensitic SteelsMechanical PropertiesBn-350 Reactor	2007	23
The strong influence of displacement rate on void swelling in variants of Fe–16Cr–15Ni–3Mo austenitic stainless steel irradiated in BN-350 and BOR-60 N.I. Budylkin, T.M. Bulanova, E.G. Mironova, Journal of Nuclear Materials Materials ScienceMaterials EngineeringEngineeringCorrosionStrong Influence	2004	21
Material science and manufacturing of heat-resistant reduced-activation ferritic–martensitic steels for fusion A.G. Ioltukhovskiy, A. I. Blokhin, N.I. Budylkin, Journal of Nuclear Materials Materials ScienceMaterials EngineeringEngineeringMechanical EngineeringHigh Strength Low Alloy Steel	2000	18
Irradiation creep and stress-enhanced swelling of Fe–16Cr–15Ni–Nb austenitic stainless steel in BN-350 A. N. Vorobjev, N.I. Budylkin, E.G. Mironova, Journal of Nuclear Materials Materials ScienceMaterials EngineeringEngineeringSuperalloyMechanical Engineering	1998	11

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