Zobrazeno 1 - 10
of 155
pro vyhledávání: '"V.K. Shamardin"'
Publikováno v:
MATERIALS TRANSACTIONS. 60:1723-1731
Autor:
A.E. Fedoseev, V.K. Shamardin, Igor V. Alexandrov, Ruslan Z. Valiev, A.A. Karsakov, A.V. Obukhov, M.M. Abramova, Nariman A. Enikeev, Georgy I. Raab, T.M. Bulanova
Publikováno v:
Materials Science and Engineering: A. 712:365-372
An ultrafine-grained (UFG) austenite Cr-Ni stainless steel was produced by equal-channel angular pressing. The UFG samples were irradiated in a research nuclear reactor up to damaging doses of 12 and 15 dpa at 350 °C and 450 °C, respectively. The p
Autor:
Ruslan Z. Valiev, Alexei A. Karsakov, Nariman A. Enikeev, Ivan Smirnov, T.M. Bulanova, M.M. Abramova, A.E. Fedoseev, V.K. Shamardin
Publikováno v:
Journal of Nuclear Materials. 544:152680
Austenitic stainless steel in conventional and ultrafine-grained states is studied by impact testing in an unirradiated condition and after neutron irradiation to 12 dpa at 350°C. We show that grain refinement provided higher resistance of the steel
Publikováno v:
Materials Science Forum. :1119-1124
The initial and deformed states of austenitic stainless steel AISI 321 before and after neutron irradiation with a damage dose up to 5.3 dpa at reactor core temperature of 350 °С were comparatively investigated. Corrosion behavior, mechanical prope
Publikováno v:
Journal of Nuclear Materials. :277-280
Type 316L austenitic steels are widely used for the in-vessel internal structures of fission reactors (core, core support, etc.) and for experimental irradiation facilities. The modifications of 316L Type steel (316L, 316L(N), US 316, J 316, JPCA, et
Publikováno v:
Journal of Nuclear Materials. :54-59
Reduced activation ferritic/martensitic steels (F82H, JLF-1, 9Cr2WTaV and EUROFER-9Cr1WTaV), advanced ODS Fe–14%Cr alloys, standard and modified 9Cr1Mo conventional martensitic steels were irradiated as specimens for mechanical tests in different n
Autor:
A.I. Blokhin, V.A. Romanov, E. G. Mironova, O.V. Mishin, V.M. Chernov, B.K. Kardashev, Y. Strebkov, B.A. Vasiliev, I.R. Kirillov, Shikov Aleksandr K, N. I. Budylkin, A.B. Sivak, V.K. Shamardin, A.G. Ioltoukhovskiy, G.N. Yermolaev, A.N. Kalashnikov, V. N. Golovanov, V. A. Belyakov, M.M. Potapenko, B.V. Kuteev, Alexander N. Tyumentsev, Yu.N. Devyatko, N.I. Loginov, M.V. Leonteva-Smirnova, T.M. Bulanova
Publikováno v:
Nuclear Fusion. 47:839-848
Recent progress in the RF low activation structural materials R&D road map towards DEMO via the FBR tests (BOR-60, BN-600, BN-800) and the TBM tests in ITER is overviewed. The properties of the RAFMS RUSFER-EK-181 (Fe?12Cr?2W?Ta?V?B?C) and the V?4Ti?
Publikováno v:
Atomic Energy. 100:31-36
The results of an investigation of the material used for the VK-50 measurement channel, which showed no signs of unsealing when it was extracted after 25 years of operation, are presented. The results of metallographic and electron-microscope investi
Autor:
T.M. Bulanova, Francis A. Garner, V.M. Chernov, N. I. Budylkin, V.K. Shamardin, E. G. Mironova, S.I Porollo, N.M Mitrofanova
Publikováno v:
Journal of Nuclear Materials. :621-624
Recent irradiation experiments conducted on a variety of austenitic stainless steels have shown that void swelling appears to be increased when the dpa rate is decreased, primarily by a shortening of the transient regime of swelling. This paper prese
Publikováno v:
Journal of Nuclear Materials. :612-616
The present paper was devoted to investigation of the stress effect on swelling and microstructure evolution of the Fe–15.8Cr–15.3Ni–2.8Mo–0.6Nb steel irradiated in the BOR-60 reactor at temperatures from 395 to 410 °C and damage doses from