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В. С. Неустроев

Observed names: V Neustroev, V. C. Neustroev, V. S. Neustroev, V. S. Neustroyev, V.S Neustroev, V.S. Neustroev, V.S. Neustroyev, VS Neustroev, VS Neustroyev, Victor S. Neustroev, Неустроев, B. C., Неустроев, В. С., Неустроев, В.С.
OpenAlex ID: A5113832829
Severe embrittlement of neutron irradiated austenitic steels arising from high void swelling
2008 · V.S. Neustroev, F.A. Garner · Journal of Nuclear Materials · 57
Effect of neutron irradiation on tensile properties of materials for pressure vessel internals of WWER type reactors
2013 · A.A. Sorokin, B.Z. Margolin, et al. · Journal of Nuclear Materials · 41
Very high swelling and embrittlement observed in a Fe–18Cr–10Ni–Ti hexagonal fuel wrapper irradiated in the BOR-60 fast reactor
2008 · V.S. Neustroev, F.A. Garner · Journal of Nuclear Materials · 41
Analysis of the influence of type of stress state on radiation swelling and radiation creep of austenitic steels
2012 · B. Z. Margolin, A. I. Murashova, et al. · Strength of Materials · 33
Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 2. Relation between irradiation swelling and irradiation embrittlement. Physical and mechanical behavior
2010 · B. Z. Margolin, I. P. Kursevich, et al. · Strength of Materials · 27
Prolongation of the BOR-60 reactor operation
2015 · Alexey l. Izhutov, Yuri M. Krasheninnikov, et al. · Nuclear Engineering and Technology · 24
Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 1. Relation between irradiation swelling and irradiation embrittlement. Experimental results
2009 · B. Z. Margolin, I. P. Kursevich, et al. · Strength of Materials · 19
The Relationship of Radiation Embrittlement and Swelling for Austenitic Steels for WWER Internals
2009 · B. Z. Margolin, I. P. Kursevich, et al. · ASME Pressure Vessels and Piping Conference (PVP) · 12
Studying helium accumulation in austenitic steels for evaluating radiation damage in internals of water-moderated water-cooled power reactors
2008 · S. V. Belozerov, V. S. Neustroyev, et al. · The Physics of Metals and Metallography · 10
Investigation of Microstructure and Mechanical Properties of 18Cr-10Ni-Ti Steel Irradiated in the Core of VVER-1000 Reactor
2004 · VS Neustroev, VG Dvoretzky, et al. · 10
Low-temperature mechanical properties of Fe–0.06C–18Cr–10Ni–0.4Ti austenitic steel determined using ring-pull tensile tests and microhardness measurements
2007 · V.S. Neustroev, E.V. Boev, et al. · Journal of Nuclear Materials · 9
Experimental investigation of stress effect on swelling and microstructure of Fe–16Cr–15Ni–3Mo–Nb austenitic stainless steel under low-temperature irradiation up to high damage dose in the BOR-60 reactor
2004 · V.S Neustroev, Z.E Ostrovsky, et al. · Journal of Nuclear Materials · 9
The Influence of DPA Rate on Void Swelling of Russian Austenitic Stainless Steels
2004 · F.А. Garner, Nikolai I. Budylkin, et al. · 8
Change in the properties of Fe-Cr-Ni and Fe-Cr-Mn austenitic steels under mixed and fast neutron irradiation
1996 · V.K. Shamardin, T.M. Bulanova, et al. · Journal of Nuclear Materials · 8
Radiation Creep and Swelling of Austenitic 16Cr-15Ni-3Mo-Nb Steels Irradiated in the Reactor BOR-60 at 350 and 420 C
1994 · VS Neustroev, VK Shamardin · 8
Microstructure of the Kh18N10T steel irradiated in a BOR-60 reactor
1991 · O. V. Borodin, V. V. Bryk, et al. · Atomic Energy · 8
Study of Fe-12Cr-20Mn-W-C austenitic steels irradiated in the SM-2 reactor
1992 · V.K. Shamardin, T.M. Bulanova, et al. · Journal of Nuclear Materials · 6
Effect of tensile and compressive stresses on the radiation swelling and creep strain in austenitic steel Kh18N10T
2010 · V. S. Neustroev, S. V. Belozerov, et al. · The Physics of Metals and Metallography · 5
Temperature-Shift of Void Swelling Observed in Annealed Fe-18Cr-10Ni-Ti Stainless Steel Irradiated in the Reflector Region of BOR-60
2000 · VS Neustroev, VK Shamardin, et al. · 5
Effect of tensile stresses on the evolution of vacancy porosity in the Fe-18% Cr-10% Ni-Ti steel irradiated in BOR-60 reactor
2014 · V. S. Neustroev, S. V. Belozerov, et al. · The Physics of Metals and Metallography · 4
Recent Insights on the Parametric Dependence of Irradiation Creep of Austenitic Stainless Steels
2011 · F. A. Garner, E. R. Gilbert, et al. · Springer eBooks · 4
Investigations of BOR-60 Structural Materials and Prospects for Further Work
2001 · V. N. Golovanov, V. K. Shamardin, et al. · Atomic Energy · 4
Mechanical characteristics and swelling of austenitic Fe-Cr-Mn steels irradiated in the SM-2 and BOR-60 reactors
1991 · V.K. Shamardin, T.M. Bulanova, et al. · Journal of Nuclear Materials · 4
Effect of chemical composition on irradiation creep of stainless steels irradiated in the BOR-60 reactor at 420 °C
2002 · V.S. Neustroev, V.K. Shamardin · Journal of Nuclear Materials · 3
Irradiation Creep of Austenitic Steels Irradiated Up to High Damage Dose
2000 · VS Neustroev, VK Shamardin · 3
Works count: 50
Citation count: 375
H-index: 10
I10-index: 10
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