Zobrazeno 1 - 7
of 7
pro vyhledávání: '"M. V. Bakanov"'
Publikováno v:
IOP Conference Series: Materials Science and Engineering. 1151:012034
The article discusses the development of non-traditional adaptive control systems for such a type of vehicle as an unmanned aerial vehicle based on the concepts of inverse problems of dynamics, adjacent to the class of absolutely stable dynamic syste
Autor:
V. N. Sizykh, R. A. Daneev, M. V. Bakanov, A. V. Livshits, A. A. Aleksandrov, S. B. Antoshkin
Publikováno v:
IOP Conference Series: Materials Science and Engineering. 760:012053
Mathematical models of a three-wheeled mobile robot based on the variable state apparatus and in the operator’s form are presented. Based on these mathematical models, the synthesis of its adaptive control system is carried out according to the met
Autor:
N. N. Oshkanov, V. M. Poplavskii, O. A. Potapov, Yu. L. Kamanin, O. M. Saraev, M. V. Bakanov, Yu. M. Ashurko, B. A. Vasil’ev, P. P. Govorov, V. N. Ershov
Publikováno v:
Atomic Energy. 108:234-239
Experience in operating the BN-600 sodium-cooled fast reactor during its nominal service life as well as its service life extension period, an additional 15 years, is described. Information is presented on the performance indicators which were achiev
Autor:
N. N. Oshkanov, M. N. Svyatkin, Yu. L. Kamanin, Yu. M. Ashurko, V. N. Ershov, Yu. M. Krasheninnikov, B. A. Vasiliev, M. V. Bakanov, O. M. Saraev, A. S. Korolkov, V. M. Poplavskii, A. V. Zrodnikov
Publikováno v:
Atomic Energy. 108:240-247
The main stages of the development of sodium-cooled fast reactors in Russia are described. The statistical information on the deviations from the normal regime of functioning that occur in BOR-60 and BN-600 operation is presented. The important role
Autor:
N. V. Gorin, V. G. Kazeev, L. I. Osokin, O. V. Anfalova, G. N. Rykovanov, A. I. Vorobjov, M. V. Bakanov, S. V. Urusov, B. G. Morozov, A. N. Scherbina, V. S. Krayev
Publikováno v:
Packaging, Transport, Storage & Security of Radioactive Material. 17:203-207
One of the most complicated tasks in spent nuclear fuel (SNF) transport arises when it is necessary to transport long length SNF without fragmentation. The length of the fuel assemblies for some reactors runs up to 15 m. In these cases the technologi
Publikováno v:
Atomic Energy. 96:315-319
Data on the experience in operating the BN-600 reactor with sodium coolant in the first and second loops are presented. It is shown that the equipment and the systems in the sodium loops, which have operated for more than 23 years, are highly realiab
Publikováno v:
Atomic Energy; May2004, Vol. 96 Issue 5, p315-319, 5p