Zobrazeno 1 - 10 of 13 pro vyhledávání: '"G. P. Kobylyansky"'
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The effect of long-term annealing simulating the parameters of dry storage of VVER-1000 fuel rods on the mechanical properties of E110 alloy shells in the longitudinal direction
Autor: А. V. Obukhov, S. G. Eremin, Е. V. Chertopyatov, G. P. Kobylyansky, А. О. Mazaev, Е. А. Zvir
Publikováno v: Physics and Chemistry of Materials Treatment. 4:42-49
Presented are the results of mechanical tensile tests of longitudinal (segmental) samples cut from the midsection of claddings spent as VVER-1000 FA during one- and six-year campaigns and subject to thermal tests in helium at 480 °С during 468 full
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5ba2c30cf923eb594bae90a14bdd8e5e
https://doi.org/10.30791/0015-3214-2021-4-42-49
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3
Peculiarities of Application of the Gas Extraction Method for Determination of Hydrogen Content in Samples of Irradiated Zirconium Materials
Autor: A. A. Shel’dyakov, A. M. Novikov, V. Yu. Shishin, G. V. Shishalova, G. P. Kobylyansky
Publikováno v: Inorganic Materials: Applied Research. 10:737-743
Results of multiyear research of zirconium materials from nuclear reactors show that the hydrogen content measured by a high-temperature extraction method does not always correlate with the number and size of zirconium hydrides measured by metallogra
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::ede6d4ebb915b3143d4a36f49947cacb
https://doi.org/10.1134/s2075113319030390
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4
Impact of Thermal Tests Simulating Dry Storage of VVER-1000 Fuel on the Hydride Phase Morphology in Fuel Element Claddings
Autor: G. P. Kobylyansky, I. A. Minduksheva, G. V. Shishalova, A. O. Mazaev, E. A. Zvir
Publikováno v: Inorganic Materials: Applied Research. 10:749-756
In this work, we carried out metallographic studies of the lateral and longitudinal sections of the fuel element claddings used in the fuel assemblies of VVER-1000 reactors. The average fuel burnup in these fuel elements during one and six annual cam
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::0af96b133655f5d7bfdc5f7509190a5c
https://doi.org/10.1134/s2075113319030250
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5
Microstructure and Mechanical Properties of the Fuel Cladding in VVER-1000 after the Thermal Tests That Model Dry Storage Conditions
Autor: E. A. Zvir, A. O. Mazaev, A. V. Obukhov, D. E. Markelov, G. P. Kobylyansky, P. A. Ilyin
Publikováno v: Russian Metallurgy (Metally). 2019:421-426
The mechanical properties, the dislocation structure, and the morphology of phase precipitates in the E110 alloy fuel claddings worked in the fuel assemblies of a VVER-1000 reactor to a fuel burn-out of 20 and 70 (MW day)/kgU are studied. The influen
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::635fe6ef1936b704c26af00af0f278b5
https://doi.org/10.1134/s0036029519040190
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10
Radiation Damage of E635 Alloy Under High Dose Irradiation in the VVER-1000 and BOR-60 Reactors
Autor: G. P. Kobylyansky, A. E. Novoselov, A. V. Obukhov, Z. E. Ostrovsky, V. N. Shishov, M. M. Peregud, V. A. Markelov, P. Barberis, S. W. Dean
Publikováno v: Journal of ASTM International. 8:102941
Alloy E635 is used as a material for some parts of the water-water energy reactor (VVER)-1000 fuel assemblies (FAs). The evolution of structural components and redistribution of the elementary composition that occurred between the solid solution and
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::f3b87197fcfacaeb1abc2924cbb00807
https://doi.org/10.1520/jai102941
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