Zobrazeno 1 - 10
of 55
pro vyhledávání: '"Valery F. Strizhov"'
Publikováno v:
Nuclear Energy and Technology, Vol 6, Iss 3, Pp 203-214 (2020)
The article describes the status of development of codes of new generation for the “PRORYV” Project by the end of 2019: twenty-five commercial-grade software products to justify design solutions and safety of power units with fast neutron reactor
Externí odkaz:
https://doaj.org/article/d4cd4d0367564e219fff182149c1bb9d
Autor:
T. V. Sycheva, Valery F. Strizhov, A. A. Butov, Vladimir Igorevich Chukhno, E. V. Usov, I. G. Kudashov, N. A. Mosunova, I. A. Kliminov
Publikováno v:
Thermal Engineering. 68:841-847
Autor:
Valery F. Strizhov, Aleksei S. Kiselev, M. I. Skorikova, V. N. Medvedev, Aleksandr S. Kiselev, A. N. Ul’yanov
Publikováno v:
Atomic Energy. 130:20-24
In connection with the use of the SPZO-M modernized system for prestressing the NPP containment, it became necessary to determine the effect of loads inside the containment wall on the stress-strain state of the containment. Because of the particular
Publikováno v:
Thermal Engineering. 68:152-158
Accident scenarios implying the failure of the active and passive reactor protection system are the most severe in their consequences since they are accompanied by the melting of fuel elements, fuel assemblies, and the entire core and, as a consequen
Publikováno v:
Nuclear Energy and Technology, Vol 6, Iss 3, Pp 203-214 (2020)
Nuclear Energy and Technology 6(3): 203-214
Nuclear Energy and Technology 6(3): 203-214
The article describes the status of development of codes of new generation for the “PRORYV” Project by the end of 2019: twenty-five commercial-grade software products to justify design solutions and safety of power units with fast neutron reactor
Autor:
E. V. Usov, Valery F. Strizhov, V. I. Chukhno, Nikolay A. Pribaturin, V. S. Zhdanov, N. A. Mosunova, I. G. Kudashov, A. A. Butov, I. A. Klimonov
Publikováno v:
Atomic Energy. 127:1-7
When fuel rods melt during a severe accident, the movement of the structural and fuel materials along fuel assemblies can be spatially non-uniform, so that a three-dimensional thermohydraulic model is implemented in the EVKLID/V2 code as part of the
Autor:
Valery F. Strizhov, I. A. Klimonov, I. G. Kudashov, S. A. Frolov, A. E. Kutlimetov, A. A. Sorokin, V. I. Chukhno, A. A. Butov, V. S. Zhdanov, N. A. Mosunova, E. V. Usov
Publikováno v:
Thermal Engineering. 66:293-301
The article describes the basic models laid down in the second version of the EUCLID/V2 integrated code developed for carrying out end-to-end analysis of severe accidents in liquid metal cooled reactors. Brief information about the basic analogs of t
Autor:
Valery F. Strizhov, V. S. Zhdanov, N. A. Mosunova, P. D. Lobanov, A. A. Sorokin, V. I. Chukhno, I. A. Klimonov, A. A. Butov, I. G. Kudashov, E. V. Usov, A. E. Kutlimetov
Publikováno v:
Thermal Engineering. 66:302-309
The article presents the results obtained from verification of the EUCLID/V2 coupled code developed at the Nuclear Safety Institute of the Russian Academy of Sciences, which is intended for analysis of accident conditions in liquid metal cooled fast
Autor:
V. N. Medvedev, A. N. Ul’yanov, Valery F. Strizhov, Aleksei S. Kiselev, Aleksandr S. Kiselev, M. I. Skorikova
Publikováno v:
Global Nuclear Safety. 14:25-38
Publikováno v:
Nuclear Engineering and Design. 341:326-345
After Fukushima Daiichi accident the importance of software tools that enable the NPP safety assessment for the overall sequence of severe accident processes has revived. In accordance with this issue Nuclear Safety Institute of the Russian Academy o