Zobrazeno 1 - 10
of 18
pro vyhledávání: '"M V Shchurovskaya"'
Publikováno v:
Âderna Fìzika ta Energetika, Vol 14, Iss 4, Pp 350-355 (2013)
IRT MEPhI reactor is equipped with a number of facilities at horizontal experimental channels (HEC). Knowing of parameters influencing spatio-angular distribution of irradiation fields is essential for each application area. The research for neutron
Externí odkaz:
https://doaj.org/article/4a1a9276dfbc4b299a7c1ed1ec17e047
Publikováno v:
Atomic Energy. 123:81-86
The results of an analysis of the radiological consequences of a beyond design basis accident for IRT MEPhI with high-enrichment uranium fuel and conversion to IRT-3M fuel assemblies with fuel kernel based the alloy U–9% Mo in an aluminum matrix wi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2b182db7104974ab16968009062135f1
https://doi.org/10.1007/s10512-017-0305-1
https://doi.org/10.1007/s10512-017-0305-1
Autor:
V. P. Alferov, M.N. Anikin, I.I. Lebedev, A. Naymushin, A.I. Radaev, M. V. Shchurovskaya, N. I. Geraskin, Yu.B. Chertkov
Publikováno v:
Annals of Nuclear Energy. 96:332-343
This paper presents the results of the validation of a research reactor calculation using Monte Carlo code against experimental data. Validation efforts are carried out for two university-based research reactors in Russia: the IRT MEPhI reactor at th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::44160a66f89676f7f4678c57d8f09c6f
https://doi.org/10.1016/j.anucene.2016.06.015
https://doi.org/10.1016/j.anucene.2016.06.015
Publikováno v:
Atomic Energy. 120:15-21
The results of calculations of emergency situations for the IRT MIFI [Moscow Engineering Physics Institute] reactor with high-enrichment uranium fuel and with conversion to IRT-3M fuel assemblies with fuel cores based on the alloy U–9%Mo in an alum
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9c1dcd8123231915af48926ebafe777f
https://doi.org/10.1007/s10512-016-0089-8
https://doi.org/10.1007/s10512-016-0089-8
Autor:
L. I. Yakovlev, A. B. Gaiduchenko, A. A. Serebryakov, A. E. Kruglikov, N. I. Geraskin, T. B. Aleeva, D. V. Andreev, S. A. Ozherelev, A. F. Kozhin, M. V. Shchurovskaya, V. P. Alferov
Publikováno v:
Journal of Physics: Conference Series. 1689:012024
Life cycle extension practices for U–Al fuel in Al cladding used at the OR and the IRT MEPhI research reactors are discussed. The IRT MEPhI reactor uses tube type IRT-3M FA with dispersed UO2–Al fuel meat and SAV–1 aluminum alloy as cladding. T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f05bc65335ee434c7e8abf3b3cf6593f
https://doi.org/10.1088/1742-6596/1689/1/012024
https://doi.org/10.1088/1742-6596/1689/1/012024
Autor:
P. A. Fomichenko, Yu. N. Volkov, A E Kruglikov, V. A. Nevinitsa, M V Shchurovskaya, M N Zizin
Publikováno v:
Journal of Physics: Conference Series. 1689:012026
This study is focused on the development of homogenization technique for the ASTRA pebble bed critical facility. The methods of generating homogenized few-group cross sections using continuous energy Monte Carlo codes MCU-PTR and Serpent 2.1.29 for f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ed621909a1725f1627504b87ef74efb8
https://doi.org/10.1088/1742-6596/1689/1/012026
https://doi.org/10.1088/1742-6596/1689/1/012026
Publikováno v:
Annals of Nuclear Energy. 141:107361
In this study, we analyze different methods for the generation of homogenized few-group cross sections (XS) using continuous-energy Monte Carlo codes Serpent 2.1.29 and MCU–PTR for full-core diffusion calculation of small-size light water research
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9d4afcaf27d37d22f9575e997a4948f4
https://doi.org/10.1016/j.anucene.2020.107361
https://doi.org/10.1016/j.anucene.2020.107361
Autor:
M. V. Shchurovskaya, F.A. van Heerden, Georgy Tikhomirov, N.A. Hanan, V. P. Alferov, A.I. Radaev
Publikováno v:
Annals of Nuclear Energy. 77:273-280
This paper presents the calculation results of the set of test problems for a research reactor with a tube-type low enriched uranium (LEU, 19.7 w/o, U-9%Mo) fuel and oxide high enriched uranium (HEU, 90 w/o) fuel, a light water moderator, and a beryl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a9a44dd36e5520a32b5e8de14cf3dc26
Publikováno v:
Atomic Energy. 117:77-84
The results of emergency-incident calculations for the IRT reactor at MEPhI with high-enrichment uranium fuel and with conversion to IRT-3M fuel assemblies with fuel kernels based on the alloy U–9% Mo in an aluminum matrix with 19.7% enrichment are
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e81e9fa65face8a31e1ac01f14b75ca4
https://doi.org/10.1007/s10512-014-9892-2
https://doi.org/10.1007/s10512-014-9892-2
Publikováno v:
Journal of Physics: Conference Series. 1133:012002
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f1e8b36c6ac3b2ad2b8ecd140b9c96c0
https://doi.org/10.1088/1742-6596/1133/1/012002
https://doi.org/10.1088/1742-6596/1133/1/012002