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N.I. Budylkin

Observed names: N. Budylkin, N. I. Budylkin, N.I Budylkin, NI Budylkin, Будылкин, Н. И.
Observed institution: "VNIINM" named after AA Bochvar
OpenAlex ID: A5111651249
Structural materials for fusion power reactors—the RF R&D activities
2007 · V.M Chernov, M.V Leonteva-Smirnova, et al. · Nuclear Fusion · 97
Neutron-induced swelling and embrittlement of pure iron and pure nickel irradiated in the BN-350 and BOR-60 fast reactors
2008 · N.I. Budylkin, E.G. Mironova, et al. · Journal of Nuclear Materials · 52
Swelling and void-induced embrittlement of austenitic stainless steel irradiated to 73–82 dpa at 335–365°C
1998 · S.I Porollo, A.N Vorobjev, et al. · Journal of Nuclear Materials · 42
Mechanical properties and microstructure of three Russian ferritic/martensitic steels irradiated in BN-350 reactor to 50dpa at 490°C
2007 · A.M. Dvoriashin, S.I. Porollo, et al. · Journal of Nuclear Materials · 25
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
2004 · N.I Budylkin, T.M Bulanova, et al. · Journal of Nuclear Materials · 23
Material science and manufacturing of heat-resistant reduced-activation ferritic–martensitic steels for fusion
2000 · A.G. Ioltukhovskiy, A.I. Blokhin, et al. · Journal of Nuclear Materials · 19
Irradiation creep and stress-enhanced swelling of Fe–16Cr–15Ni–Nb austenitic stainless steel in BN-350
1998 · A.N. Vorobjev, N.I. Budylkin, et al. · Journal of Nuclear Materials · 13
Irradiation Creep and Mechanical Properties of Two Ferritic-martensitic Steels Irradiated in the Bn-350 Fast Reactor
2002 · S. I. Porollo, Yu. V. Konobeev, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 8
Hydrogen isotopes mobility and trapping in VCrTi alloys
1996 · N. Budylkin, L. Voloschin, et al. · Journal of Nuclear Materials · 8
Swelling and radiation creep of austenitic corrosion-resistant steel irradiated by neutrons in wide dose and temperature ranges
2011 · S. I. Porollo, S. V. Shulepin, et al. · Atomic Energy · 4
Mechanical properties of high-nickel alloys EP-753 and РЕ-16 after neutron irradiation to 54 dpa at 400–650 °С
2011 · Yu.V. Konobeev, S.I. Porollo, et al. · Journal of Nuclear Materials · 4
Swelling of steels and alloys irradiated in the BOR-60 reactor to a fluence of 1.1�1023 neutrons/cm2
1978 · N. P. Agapova, V. S. Ageev, et al. · Atomic Energy · 4
Void swelling and irradiation creep of two high-nickel steels after irradiation at 400–410°C to 84–91 dpa in the BN-350 fast reactor
2000 · S.I Porollo, A.M Dvoriashin, et al. · Journal of Nuclear Materials · 3
Void-Induced Swelling and Embrittlement in the Russian EI-847 Stainless Steel at PWR-Relevant End-of-Life Conditions
2000 · FA Garner, SI Porollo, et al. · 3
The microstructural stability of low-activation 12%-chromium ferritic-martensitic steel EK-181 during thermal aging
2014 · N. A. Polekhina, I. Yu. Litovchenko, et al. · AIP conference proceedings · 2
Irradiation Creep and Swelling of Russian Ferritic-Martensitic Steels Irradiated to Very High Exposures in the BN-350 Fast Reactor at 305–335°C
2004 · YV Konobeev, AM Dvoriashin, et al. · Journal of ASTM International · 2
Irradiation Creep and Swelling of Russian Ferritic-Martensitic Steels Irradiated to Very High Exposures in the BN-350 Fast Reactor at 305–335°C
2004 · YV Konobeev, AM Dvoriashin, et al. · 2
Irradiation Creep and Stress-Affected Swelling in Austenitic Stainless Steel 16Cr-15Ni-3Mo-Nb-B Irradiated in the BN-350 Reactor
2000 · SI Porollo, AN Vorobjev, et al. · 2
Neutron‐Induced Swelling and Embrittlement Behavior of Two Russian Stainless Steels at PWR‐Relevant Temperatures and 65‐85 DPA
1999 · S. I. Porollo, A. M. Dvoriashin, et al. · Wiley eBooks · 1
Распухание И Радиационная Ползучесть Аустенитной Коррозионно-стойкой Стали, Облученной Нейтронами В Широком Диапазоне Дозы И Температуры
2019 · Поролло, С. И., Шулепин, С. В., et al. · Атомная энергия
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Works count: 20
Citation count: 314
H-index: 8
I10-index: 7
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