Zobrazeno 1 - 10
of 41
pro vyhledávání: '"Yu. V. Konobeev"'
Publikováno v:
Physics of Metals and Metallography. 123:784-790
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::760667ea9f8a07d98f7be49da4c0ab12
https://doi.org/10.1134/s0031918x22080075
https://doi.org/10.1134/s0031918x22080075
Publikováno v:
Atomic Energy. 128:82-87
The results of research on the influence of the chemical composition, cold-deformation, and irradiation temperature on the short-time mechanical properties of the austenitic stainless steels 08Kh18N10T, EI-847, EP-172, and ChS-68 after neutron irradi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::30b6b336af30ce7adae127f8137242fb
https://doi.org/10.1007/s10512-020-00655-x
https://doi.org/10.1007/s10512-020-00655-x
Publikováno v:
Atomic Energy. 126:39-45
The results of investigations of the microstructure and short-time mechanical properties of EP-450 ferritic-martensitic steel and Kh13M2Yu2 + 1.5% TiO2 dispersion-hardened steel are presented. It is shown that as a result of aging for 25000 h at 400
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8109ba01217a294839fbb3b22ecc47e6
https://doi.org/10.1007/s10512-019-00511-7
https://doi.org/10.1007/s10512-019-00511-7
Publikováno v:
Atomic Energy. 124:98-104
The results of a study of the long-term strength of austenitic and ferrite-martensite steel after irradiation in the BR-10, BOR-60, BN-350, and BN-600 reactors are presented. It is shown that irradiation of austenitic-class steel (EI-847, 0Kh18N10T,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b493bd244d38d32de3cc4b5f5d832370
https://doi.org/10.1007/s10512-018-0381-x
https://doi.org/10.1007/s10512-018-0381-x
Autor:
A. A. Ivanov, S. V. Shulepin, M. V. Leont’eva-Smirnova, Yu. V. Konobeev, N. S. Nikolaeva, S. I. Porollo
Publikováno v:
Atomic Energy. 120:189-198
The results of investigations of swelling and in-reactor creep of the ferrite-martensite class steels EP-450, EP-823, and EI-852 irradiated in a BN-350 reactor at 305–700°C to damaging dose in the range 20–89 dpa are presented. The characteristi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8cc5b1e6f8f8ae1af3f602c4d08ebd4f
https://doi.org/10.1007/s10512-016-0116-9
https://doi.org/10.1007/s10512-016-0116-9
Publikováno v:
Atomic Energy. 118:389-399
The results of materials science studies of spent BN-600 fuel assemblies from a core with a type-1 load are presented. The fuel assemblies studied had depressurized and damaged fuel elements. It was determined that most of the fuel elements failed be
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f7dc288c0969d86bc7d1b61f93976320
https://doi.org/10.1007/s10512-015-0013-7
https://doi.org/10.1007/s10512-015-0013-7
Publikováno v:
Atomic Energy. 116:301-310
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0fe1609763b4458646e7f7374384951f
https://doi.org/10.1007/s10512-014-9857-5
https://doi.org/10.1007/s10512-014-9857-5
Autor:
V. I. Rachkov, V. A. Solov’ev, M. Yu. Belomyttsev, A. V. Molyarov, Yu. V. Konobeev, S. M. Obraztsov
Publikováno v:
Atomic Energy. 116:311-314
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bbd34507f945b71023ab61598a1dabc0
https://doi.org/10.1007/s10512-014-9858-4
https://doi.org/10.1007/s10512-014-9858-4
Publikováno v:
Atomic Energy. 110:248-258
The results of a study of the swelling and in-reactor creep of EI-847, EP-172, and ChS-68 austenitic steel after irradiation in materials science assemblies in the range 330‐700°C and damaging dose 20‐96 dpa are presented. The temperature depend
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::83a88ee0f887423f8863ef066bf7b97a
https://doi.org/10.1007/s10512-011-9419-z
https://doi.org/10.1007/s10512-011-9419-z
Publikováno v:
Atomic Energy. 106:238-246
Post-reactor investigations have been performed on BN-600 fuel-element cladding, made of 0Kh16N15M3BR steel, after irradiation to maximum burnup of 10% h.a. and higher. It is shown that the highest degradation of the operating properties of the fuel-
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1b62d4401cd19fa9e58c6f2f39508965
https://doi.org/10.1007/s10512-009-9158-6
https://doi.org/10.1007/s10512-009-9158-6