Výsledky vyhledávání - "I. G. Kudashov"

Model for the Calculation of the Dissociation Rate of Nitride Fuel at High Temperatures

Autor: T. V. Sycheva, V. I. Chukhno, I. G. Kudashov, E. V. Usov

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

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::3a10d735b9f2868b7d1846310ba2e67b
https://doi.org/10.1134/s0018151x20020194

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3D EVKLID/V2 Code Aided Simulation of Severe Accidents

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

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::49b5adb8ad8988ebc64fb4065595ae84
https://doi.org/10.1007/s10512-019-00575-5

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The EUCLID/V2 Code Physical Models for Calculating Fuel Rod and Core Failures in a Liquid Metal Cooled Reactor

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

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5f6922276b1236ea40c34c5aa2d7904d
https://doi.org/10.1134/s0040601519050021

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Verification of the EUCLID/V2 Code Based on Experiments Involving Destruction of a Liquid Metal Cooled Reactor’s Core Components

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

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::c9b51974bfe3459f30641136863b323c
https://doi.org/10.1134/s0040601519050033

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Development of Approaches to Simulate Fuel Rod Destruction With Different Fuel Type

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

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::ff63a2081c7ae3c992fb97579abf00ba
https://doi.org/10.1115/icone2020-16326

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Experiment-Based Verification of the SAFR/V1 Module of the EVKLID/V2 Integral Code for Thermal Breakdown of Fuel Pins in a Fast Reactor

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

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::44bb457e0101c596eb63ffaac9f774b7
https://doi.org/10.1007/s10512-018-0412-7

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SAFR/V1 (EVKLID/V2 Integral Code Module) Aided Simulation of Melt Movement Along the Surface of a Fuel Element in a Fast Reactor During a Serious Accident

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

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::a0c62cc4e6dd24a7029007754e8d1639
https://doi.org/10.1007/s10512-018-0403-8

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Experimental Simulation of Hydrodynamics and Heat Transfer in Bubble and Slug Flow Regimes in a Heavy Liquid Metal

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

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::6a4dfacbe3b8263bd260492816eeef93
https://doi.org/10.1134/s0040601518080086

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Fuel Pin Melting in a Fast Reactor and Melt Solidification: Simulation Using the SAFR/V1 Module of the EVKLID/V2 Integral Code

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

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::9bc63df7fe7dfdf52f4424a820e32ad0
https://doi.org/10.1007/s10512-018-0389-2

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