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A.S. Frolov
Researcher at Kurchatov Institute
Publications - 39
Citations - 257
A.S. Frolov is an academic researcher from Kurchatov Institute. The author has contributed to research in topics: Irradiation & Embrittlement. The author has an hindex of 8, co-authored 31 publications receiving 169 citations.
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Journal ArticleDOI
Influence of structural parameters on the tendency of VVER-1000 reactor pressure vessel steel to temper embrittlement
B. A. Gurovich,Evgenia Kuleshova,O. O. Zabusov,S.V. Fedotova,A.S. Frolov,M.A. Saltykov,D.A. Maltsev +6 more
TL;DR: In this paper, the influence of structural parameters on the tendency of steels to reversible temper embrittlement was studied for assessment of performance properties of reactor pressure vessel steels with extended service life.
Journal ArticleDOI
Evolution of structure and properties of VVER-1000 RPV steels under accelerated irradiation up to beyond design fluences
B. A. Gurovich,Evgenia Kuleshova,Ya. I. Shtrombakh,S.V. Fedotova,D.A. Maltsev,A.S. Frolov,O. O. Zabusov,D. Erak,D. A. Zhurko +8 more
TL;DR: In this article, a comprehensive study of structure and properties of VVER-1000 RPV steels after the accelerated irradiation to fluences corresponding to extended lifetime up to 60 years or more was carried out.
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Investigation of high temperature annealing effectiveness for recovery of radiation-induced structural changes and properties of 18Cr–10Ni–Ti austenitic stainless steels
B. A. Gurovich,Evgenia Kuleshova,A.S. Frolov,D.A. Maltsev,K. E. Prikhod’ko,S.V. Fedotova,Boris Margolin,A. A. Sorokin +7 more
TL;DR: In this article, a complex study of structural state and properties of 18Cr-10Ni-Ti austenitic stainless steel after irradiation in BOR-60 fast research reactor (in the temperature range 330-400° up to damaging doses of 145-dpa) and in VVER-1000 light water reactor (at temperature ∼320-°С and damaging doses ∼12-14 dpa) was performed and the possibility of recovery of structural phase state and mechanical properties to the level almost corresponding to the initial state by the recovery annealing was studied.
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Mechanisms of radiation embrittlement of VVER-1000 RPV steel at irradiation temperatures of (50–400)°C
Evgenia Kuleshova,Evgenia Kuleshova,B. A. Gurovich,Z.V. Bukina,A.S. Frolov,D.A. Maltsev,E. V. Krikun,D. A. Zhurko,G.M. Zhuchkov +8 more
TL;DR: In this paper, the effect of irradiation temperature within the range of (50-400)°C on microstructure and properties of 15Kh2NMFAA class 1 steel (VVER-1000 reactor pressure vessel (RPV) base metal).
Journal ArticleDOI
Effect of Ni content on thermal and radiation resistance of VVER RPV steel
Ya. I. Shtrombakh,B. A. Gurovich,Evgenia Kuleshova,A.S. Frolov,S.V. Fedotova,D. A. Zhurko,E. V. Krikun +6 more
TL;DR: In this article, thermal stability and radiation resistance of VVER-type RPV steels for pressure vessels of advanced reactors with different nickel content were studied, and a complex of microstructural studies and mechanical tests of the steels in different states (after long thermal exposures, provoking embrittling heat treatment and accelerated neutron irradiation) was carried out.