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Sergej Ivanovich Porollo

Observed names: S. I. Porollo, S. Porollo, S.I Porollo, S.I. Porollo
OpenAlex ID: A5111902076
The microstructure and tensile properties of Fe–Cr alloys after neutron irradiation at 400°C to 5.5–7.1 dpa
1998 · S.I Porollo, A.M Dvoriashin, et al. · Journal of Nuclear Materials · 152
Swelling and microstructure of pure Fe and Fe–Cr alloys after neutron irradiation to ∼26dpa at 400°C
2006 · Yu.V. Konobeev, A.M. Dvoriashin, et al. · Journal of Nuclear Materials · 87
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
Microstructure and mechanical properties of ferritic/martensitic steel EP-823 after neutron irradiation to high doses in BOR-60
2004 · S.I Porollo, A.M Dvoriashin, et al. · Journal of Nuclear Materials · 49
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
Influence of high dose neutron irradiation on microstructure of EP-450 ferritic–martensitic steel irradiated in three Russian fast reactors
2004 · A.M Dvoriashin, S.I Porollo, et al. · Journal of Nuclear Materials · 38
Influence of silicon on swelling and microstructure in Russian austenitic stainless steel EI-847 irradiated to high neutron doses
2008 · S.I. Porollo, S.V. Shulepin, et al. · Journal of Nuclear Materials · 34
Microstructure and mechanical properties of austenitic stainless steel 12X18H9T after neutron irradiation in the pressure vessel of BR-10 fast reactor at very low dose rates
2006 · S.I. Porollo, A.M. Dvoriashin, et al. · Journal of Nuclear Materials · 29
Swelling and microstructure of austenitic stainless steel ChS-68 CW after high dose neutron irradiation
2009 · S.I. Porollo, Yu.V. Konobeev, et al. · Journal of Nuclear Materials · 27
Void swelling at low displacement rates in annealed 12X18HgT stainless steel at 4–56 dpa and 280–332 °C
2002 · S.I. Porollo, Yu.V. Konobeev, et al. · Journal of Nuclear Materials · 27
Microstructure, irradiation hardening and embrittlement of 13Cr2MoNbVB ferritic—martensitic steel after neutron irradiation at low temperatures
1996 · V.S. Khabarov, A.M. Dvoriashin, et al. · Journal of Nuclear Materials · 26
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
Microstructure and swelling of neutron irradiated nickel and binary nickel alloys
2013 · S.I. Porollo, A.M. Dvoriashin, et al. · Journal of Nuclear Materials · 24
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
Influence of cold work to increase swelling of pure iron irradiated in the BR-10 reactor to ∼6 and ∼25 dpa at ∼400°C
2000 · A.M. Dvoriashin, S.I. Porollo, et al. · Journal of Nuclear Materials · 18
Influence of operation conditions on structure and properties of 12% Cr steels as candidate structural materials for fusion reactor
1998 · A.G Ioltukhovsky, M.V Leontyeva-Smirnova, et al. · Journal of Nuclear Materials · 16
Results of Investigations of BREST-Type Reactor Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel, Irradiated in BOR-60 and BN-600
2019 · A. F. Grachev, A. A. Zherebtsov, et al. · Atomic Energy · 15
Analysis of Experimental Data on Gas Release and Swelling of Uranium Mononitride Fuel Irradiated in the BR-10 Reactor
2017 · S. I. Porollo, S. N. Ivanov, et al. · Atomic Energy · 13
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
Results of Studies of BN-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel and ChS68-ID c.d. Steel Cladding
2019 · A. F. Grachev, L. M. Zabud’ko, et al. · Atomic Energy · 12
The Influence of DPA Rate on Void Swelling of Russian Austenitic Stainless Steels
2004 · F.А. Garner, Nikolai I. Budylkin, et al. · 8
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
Fission Gas Release from Irradiated Uranium-Plutonium Nitride Fuel
2020 · A. F. Grachev, L. M. Zabud’ko, et al. · Atomic Energy · 7
High-Temperature Radiation Embrittlement of Neutron-Irradiated Austenitic Stainless Steels 08Kh18N10T, Ei-847, EP-172, and ChS-68
2020 · S. I. Porollo, A. A. Ivanov, et al. · Atomic Energy · 6
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Works count: 63
Citation count: 840
H-index: 16
I10-index: 21
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