Zobrazeno 1 - 8
of 8
pro vyhledávání: '"E. A. Sukhino-Khomenko"'
Publikováno v:
Kerntechnik. 80:408-411
Jacketless fuel assemblies change their form in the course of operation. Often they bow lengthwise. Primarily, these fuel assembly (FA) bows threaten to reduce the control rods' fall rate, but at the same time they change (e. g. increase) the amount
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9d876a65a48bd77bfe6c164b7c731e24
https://doi.org/10.3139/124.110518
https://doi.org/10.3139/124.110518
Autor:
M. A. Kalugin, S. N. Bol’shagin, S. S. Aleshin, A. V. Pryanichnikov, Anastasia I. Shcherenko, E. K. Kosourov, E. A. Sukhino-Khomenko, A. M. Pavlovichev, D. A. Shkarovskiy, A. S. Bikeev, A. I. Shcherenko
Publikováno v:
Scopus-Elsevier
Two types of calculations were made to compare BIPR-7A and MCU results for 3D full-scale models. First EPS (emergency protection system) efficiency and in-core power distributions were analyzed for an equilibrium fuel load of VVER-1000 assuming its o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::18ec65174a00e17bef567dbbe51ea0c8
https://doi.org/10.3139/124.110505
https://doi.org/10.3139/124.110505
Publikováno v:
Kerntechnik. 78:330-338
Full-scale three-dimensional computer model describing neutron-physical processes that occur in the VVER-1200 reactor core involves detailed FA geometry description. However, the detailed description significantly complicates input data, increases ca
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3530d3a5b2babf82025b4e3f6b1f4f2b
https://doi.org/10.3139/124.110386
https://doi.org/10.3139/124.110386
Publikováno v:
Kerntechnik. 78:280-284
The isotopic composition of the control rods absorber changes under the neutron flux influence, so the control rods efficiency can decrease. In the VVER-1000 control rods boron carbide and dysprosium titanate are used as absorbing materials. In boric
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4e20b4b1e9a159064bc7357c8ec776f9
https://doi.org/10.3139/124.110373
https://doi.org/10.3139/124.110373
Autor:
S. V. Marin, A. S. Kulakov, A. P. Novosel’tsev, E. A. Sukhino-Khomenko, S. N. Bol’shagin, N. I. Alekseev, M. A. Kalugin, M. S. Yudkevich, D. S. Oleynik, M. I. Gurevich, E. A. Gomin, A. V. Pryanichnikov, S. S. Gorodkov, D. A. Shkarovskiy
Publikováno v:
Physics of Atomic Nuclei. 75:1634-1646
The software developed within the framework of the MCU project which implements the Monte Carlo method for solving the transport equations for various kinds of radiation is widely used for calculating nuclear reactors of different types. The final ve
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9decee700535f89722ec8906b571d9f2
https://doi.org/10.1134/s1063778812140025
https://doi.org/10.1134/s1063778812140025
Publikováno v:
Physics of Atomic Nuclei. 75:1669-1674
The algorithms of estimation of the time series correlation functions in nuclear reactor calculations using the Monte Carlo method are described. Correlation functions are used for the estimation of biases, for calculations of variance taking into ac
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::11894871c599e220548fb1cdfc1be565
https://doi.org/10.1134/s1063778812140074
https://doi.org/10.1134/s1063778812140074
Publikováno v:
Physics of Atomic Nuclei. 74:1871-1877
Algorithms for calculating the statistical error with allowance for intergenerational correlations are described. The algorithms are constructed on the basis of statistical analysis of the results of computations by the Monte Carlo method. As a resul
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::be1f3da2dc0b60b00e24dcd9d608c8d6
https://doi.org/10.1134/s1063778811140043
https://doi.org/10.1134/s1063778811140043
Publikováno v:
ResearcherID
Algorithms for evaluating the systematic error of Monte Carlo calculations performed using different variants of an approximate solution of a homogeneous neutron transport equation (the method of a constant number of points of division and augmentati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6ba813142205dee6b9cd22181b05ea01
https://doi.org/10.1007/s10512-011-9457-6
https://doi.org/10.1007/s10512-011-9457-6