Zobrazeno 1 - 10
of 69
pro vyhledávání: '"A.V. Boldyrev"'
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
Publikováno v:
Atomic Energy. 127:356-361
An advanced version of the BERKUT-U/V2.1 code intended for modeling the behavior of fuel rods with oxide or nitride fuel in standard and emergency operating regimes of fast reactors with liquid-metal coolant is being developed at the Nuclear Safety I
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9a1addc9a947883c84ba7f86ddaa197a
https://doi.org/10.1007/s10512-020-00636-0
https://doi.org/10.1007/s10512-020-00636-0
Publikováno v:
Nuclear Engineering and Design. 399:112039
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::990de2ccc401f6d56131d834066ff385
https://doi.org/10.1016/j.nucengdes.2022.112039
https://doi.org/10.1016/j.nucengdes.2022.112039
Autor:
A.V. Boldyrev
Publikováno v:
Russian Studies in History. 57:162-180
The article deals with the main geopolitical problem in Russian—Ottoman relations at the turn of the twentieth century. Using ample archive sources the author shows the course of Russia’s struggle ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9eb016930bf2252dd5daa950f84e034e
https://doi.org/10.1080/10611983.2018.1586391
https://doi.org/10.1080/10611983.2018.1586391
Publikováno v:
Annals of Nuclear Energy. 113:237-245
The EUCLID/V1 integrated computer code has been developed for the safety analysis and justification of reactor facilities with fast reactors under normal operating conditions and design basis accidents. The EUCLID/V1 code uses the BERKUT module to de
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4364fb226d652b3d211262aace17cfcc
https://doi.org/10.1016/j.anucene.2017.11.038
https://doi.org/10.1016/j.anucene.2017.11.038
Publikováno v:
Nuclear Engineering and Design. 320:153-164
The model for U-Zr-O molten pool oxidation under non-equilibrium conditions is further extended to consideration of the vessel steel corrosion by the oxidized corium melt. The heat and mass exchange processes between various interaction layers, inclu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cfb562de7055a80ad61b251706ae263f
https://doi.org/10.1016/j.nucengdes.2017.05.026
https://doi.org/10.1016/j.nucengdes.2017.05.026
Autor:
M.V. Pavelchuk, A.V. Boldyrev
Publikováno v:
Ontology of Designing. 6:501-513
The article describes the training principles for topological structures designing. The ontology of subject area "The structural load-carrying layout designing" is given. The training technique of automated designing structural layouts using deformed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::33f3164c52745252ed0f0eaef5643df9
https://doi.org/10.18287/2223-9537-2016-6-4-501-513
https://doi.org/10.18287/2223-9537-2016-6-4-501-513
Autor:
V.D. Ozrin, V. V. Pisarev, V.I. Tarasov, Vladimir V. Stegailov, Alexey Yanilkin, A.V. Kuznetsov, Sergey Starikov, M.S. Veshchunov, M.S. Seryi, V.E. Shestak, A.V. Boldyrev, D.E. Smirnova, A. Yu. Kuksin, Genri E. Norman
Publikováno v:
Nuclear Engineering and Design. 295:116-126
The SFPR code designed for mechanistic modeling of single fuel rod behavior under various regimes of LWR reactor operation (normal and off-normal, including severe accidents), is under development at IBRAE during the last two decades and currently, b
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3c503912cffbfdecf3256df1a6e497cb
https://doi.org/10.1016/j.nucengdes.2015.09.035
https://doi.org/10.1016/j.nucengdes.2015.09.035
Publikováno v:
Annals of Nuclear Energy. 135:106963
The BERKUT module of the EUCLID/V1 integrated computer code has been developed for the performance analysis of fuel rods with nitride or oxide fuels of fast reactors using the quasi two dimensional approach. As far as the uranium-plutonium mixed nitr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0ac3dbd562c257d3d561238f6b0dfd77
https://doi.org/10.1016/j.anucene.2019.106963
https://doi.org/10.1016/j.anucene.2019.106963
Publikováno v:
Annals of Nuclear Energy. 61:54-62
One of the main findings of the Phebus FP bundle melt down tests is that in the bundle, at the end of the test, just below the lower spacer grid a pool of molten materials forms and the rod-like geometry is completely lost. The computer simulations c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::995839cac4237f369212f28b833b204b
https://doi.org/10.1016/j.anucene.2013.03.046
https://doi.org/10.1016/j.anucene.2013.03.046