Zobrazeno 1 - 10
of 13
pro vyhledávání: '"E. N. Mikheev"'
Autor:
E. N. Mikheev, A. V. Fedotov, N. M. Rysev, V. V. Novikov, O. A. Bakhteev, A. L. Izhutov, A. V. Burukin, S. V. Seredkin, G. A. Ilyinykh
Publikováno v:
Physics of Atomic Nuclei. 85:S59-S72
Autor:
A. A. Plyasov, A. V. Fedotov, N. S. Saburov, E. N. Mikheev, A. V. Tenishev, M. G. Isaenkova, V. V. Mikhalchik
Publikováno v:
Physics of Atomic Nuclei. 85:1808-1815
Publikováno v:
Atomic Energy. 132:238-244
Autor:
L. A. Karpyuk, V. V. Novikov, E. N. Mikheev, A. V. Lysikov, R. B. Sivov, A. V. Fedotov, N. A. Degtyarev, D. S. Missorin, O. A. Bakhteev
Publikováno v:
Atomic Energy. 132:8-13
Publikováno v:
Atomic Energy. 130:339-343
Autor:
A. A. Maslov, L. A. Karpyuk, E. N. Mikheev, V. V. Novikov, V. K. Orlov, A. O. Titov, A. V. Lysikov
Publikováno v:
Atomic Energy. 130:156-160
Autor:
E. N. Mikheev, A. V. Lysikov, D. S. Missorin, R. B. Sivov, L. A. Karpyuk, O. A. Bakhteev, N. A. Degtyarev
Publikováno v:
Atomic Energy. 127:324-327
It is shown that the technological scheme for fabricating uranium dioxide pellets is suitable for fabricating uranium-molybdenum pellets. It permits using the standard powder metallurgy methods to fabricate pellets from uranium-molybdenum powder obta
Publikováno v:
Atomic energy. 2022. Vol. 131, № 3. P. 131-134
An engineering model for sintering of fuel pellets is presented. The model is based on a previous, fully developed, mathematical model, which was implemented by the method of finite volumes, for the process of heat-and-mass transfer of a fuel pellet
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8d9f2753de6ba13e0bc6c61baed6aa3a
https://vital.lib.tsu.ru/vital/access/manager/Repository/koha:001003466
https://vital.lib.tsu.ru/vital/access/manager/Repository/koha:001003466
Publikováno v:
Atomic Energy. 118:117-123
The results of experimental studies of crack formation and fracture toughness of VVER and PWR uranium dioxide fuel pellets with different grain size are presented for the purpose of making a comparative analysis of their strength properties. It is fo
Autor:
V. B. Malygin, V. V. Novikov, A. L. Izhutov, A. V. Fedotov, A. Ya. Rogozyanov, E. N. Mikheev, G. A. Il’inykh
Publikováno v:
Atomic Energy. 116:20-26
were conducted, using methods and experimental means developed in this work, for reactor conditions at fission density 1.2·10 13 sec ‐1 ·cm ‐3 . Diagrams of radiation creep in the stress interval 10‐40 MPa were obtained for three temperatures