Zobrazeno 1 - 10
of 50
pro vyhledávání: '"I. G. Kudashov"'
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
Publikováno v:
High Temperature. 58:222-226
A simple theoretical model is proposed in this paper based on an analysis of the experimental data available in the available literature. It describes the rate of mass loss during the dissociation of uranium nitride in a vacuum and in a gas atmospher
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:
I. A. Klimonov, Albert Gafiyatullin, E. V. Usov, Nikolay A. Pribaturin, I. G. Kudashov, V. I. Chukhno, A. A. Butov, P. D. Lobanov
Publikováno v:
Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors.
Due to the revival of interest to the development of fast reactors cooled by liquid metals, the problem of carrying out theoretical research in support of their safety is actual. A detailed calculation of all stages of the accident from the beginning
Autor:
E. V. Usov, A. A. Butov, V. S. Zhdanov, N. A. Mosunova, Nikolay A. Pribaturin, V. I. Chukhno, I. G. Kudashov, Valery F. Strizhov, I. A. Klimonov
Publikováno v:
Atomic Energy. 124:287-291
The results of verification of the IBRAE-developed SAFR/V1 module, describing in the EVKLID/V2 integral code the thermal breakdown of fuel pins, on the basis of data obtained using experimental facilities. The experiments performed on the TREAT and D
Autor:
Valery F. Strizhov, I. A. Klimonov, Nikolay A. Pribaturin, A. A. Butov, V. I. Chukhno, I. G. Kudashov, E. V. Usov, V. S. Zhdanov, N. A. Mosunova
Publikováno v:
Atomic Energy. 124:232-237
The basic approaches used in the SAFR/V1 module of the integral code EVKLID/V2 to simulate the movement of the melt formed upon melting of fuel elements are presented. The system of mass, energy, and momentum conservation equations used to simulate t
Autor:
A. E. Kutlimetov, I. G. Kudashov, Nikolay A. Pribaturin, A. I. Svetonosov, N. A. Mosunova, P. D. Lobanov, V. I. Chukhno, E. V. Usov, O. N. Kashinsky, S. I. Lezhnin
Publikováno v:
Thermal Engineering. 65:562-567
For the confirmation of the claimed design properties of a reactor plant with a heavy liquid-metal coolant, computational and theoretical studies should be performed in order to justify its safety. As one of the basic scenarios of an accident, the le
Autor:
I. A. Klimonov, V. I. Chukhno, A. A. Butov, Nikolay A. Pribaturin, V. S. Zhdanov, N. A. Mosunova, Valery F. Strizhov, I. G. Kudashov, E. V. Usov
Publikováno v:
Atomic Energy. 124:147-153
The approaches used in the SAFR/V1 module modeling the thermal destruction of fuel pins in fast reactors for calculating in integrated code EVKLID/V2 the melting of fuel pins and solidification of the formed melt are described. The enthalpy formulati