| Edição |
Título |
Arquivo |
| Volume 66, Nº 12 (2019) |
Cross-Verification of 1D and 3D Models for a VVER-1000 Reactor’s Pressure Chamber Simulated by the KORSAR/CFD Computation Code in the Modes with Asymmetric Loop Operation |
(Eng)
|
|
Yudov Y., Petkevich I., Artemov V.
|
| Volume 66, Nº 11 (2019) |
Three-Dimensional Simulation of a VVER-1000 Reactor’s Pressure Chamber in the Modes with Asymmetrical Loop Operation Using a KORSAR/CFD Computation Code |
(Eng)
|
|
Yudov Y., Petkevich I., Artemov V., Kasterin D., Rumyantsev S.
|
| Volume 66, Nº 8 (2019) |
Physical Modeling of Hydrodynamic and Heat Transfer Processes in Liquid-Metal Cooled Nuclear Power Facilities |
(Eng)
|
|
Sorokin A., Kuzina Y.
|
| Volume 66, Nº 8 (2019) |
Numerical Investigation of a Class of Accidents in the Generation IV Brest Reactor Involving the Formation of a Solid Phase in the Lead Coolant |
(Eng)
|
|
Chistov A., Savikhin O., Ovchinnikov V., Kiryushina E.
|
| Volume 66, Nº 7 (2019) |
Verification of the TIGRSP Computer Code as Applied to a 19-Rod Fuel Assembly Using CFD Computations |
(Eng)
|
|
Stepanov O., Galkin I., Melekh S., Kurnosov M., Pronin A.
|
| Volume 66, Nº 7 (2019) |
Longitudinal Displacement of a Fuel Rod Nonfixed in the Support Grid under the Conditions of Hydromechanical Vibration of VVER-440 Reactor Fuel Assemblies |
(Eng)
|
|
Solonin V., Perevezentsev V.
|
| Volume 66, Nº 7 (2019) |
Achieving More Efficient Removal of α-Emitting Radionuclides from the Primary Coolant in Propulsion Reactors |
(Eng)
|
|
Orlov S., Zmitrodan A., Mysik S.
|
| Volume 66, Nº 6 (2019) |
Threat of Combustible Mixture Formation in Small Rooms of an NPP’s Unit Containment during a Severe Accident |
(Eng)
|
|
Petrosyan V., Yeghoyan E., Grigoryan A., Martirosyan M.
|
| Volume 66, Nº 6 (2019) |
Simulating the Operation of the Jet-Vortex Condenser Used in the VVER-440 Reactor Plant’s Confinement System |
(Eng)
|
|
Kazantsev A., Popova T., Supotnitskaya O., Sergeev V., Bulynin V., Semashko S., Krylov Y.
|
| Volume 66, Nº 5 (2019) |
The Development of a Method for Validation of the Uncertainties of the Models Used in Thermal-Hydraulic Codes |
(Eng)
|
|
Gritsai A., Migrov Y.
|
| Volume 66, Nº 5 (2019) |
The EUCLID/V2 Code Physical Models for Calculating Fuel Rod and Core Failures in a Liquid Metal Cooled Reactor |
(Eng)
|
|
Butov A., Zhdanov V., Klimonov I., Kudashov I., Kutlimetov A., Mosunova N., Strizhov V., Sorokin A., Frolov S., Usov E., Chukhno V.
|
| Volume 66, Nº 5 (2019) |
Verification of the EUCLID/V2 Code Based on Experiments Involving Destruction of a Liquid Metal Cooled Reactor’s Core Components |
(Eng)
|
|
Butov A., Zhdanov V., Klimonov I., Kudashov I., Kutlimetov A., Lobanov P., Mosunova N., Sorokin A., Strizhov V., Usov E., Chukhno V.
|
| Volume 66, Nº 4 (2019) |
Numerical Simulation of Thermal–Hydraulic Processes in Liquid-Metal Cooled Fuel Assemblies in the Anisotropic Porous Body Approximation |
(Eng)
|
|
Korsun A., Merinov I., Kharitonov V., Bayaskhalanov M., Chudanov V., Aksenova A., Pervichko V.
|
| Volume 66, Nº 4 (2019) |
Topical Problems Concerned with the Thermophysical Characteristics of New-Generation Light Water Reactors: Comprehensive Study Results |
(Eng)
|
|
Sorokin A., Kuzina Y., Trufanov A., Loshchinin V., Levchenko Y., Morozov A.
|
| Volume 66, Nº 4 (2019) |
Hydrodynamic Features of the Flow Downstream from the Mixing Spacer Grid in a Kvadrat Fuel Assembly in PWRs |
(Eng)
|
|
Samoilov O., Noskov A., Shipov D., Dmitriev S., Dobrov A., Doronkov D., Legchanov M., Pronin A., Solntsev D., Sorokin V., Khrobostov A.
|
| Volume 66, Nº 3 (2019) |
Evaluation of the Corrosion State of Equipment of the First Circuit of Transport Nuclear Reactors Using the Parameters of Water Chemistry |
(Eng)
|
|
Kabakchi S., Luzakov A., Urtenov D., Katanova E., Gasai I., Verkhovskii A.
|
| Volume 66, Nº 1 (2019) |
Correcting the Semi-Implicit Numerical Scheme Incorporated in the KORSAR Code Two-Liquid Model |
(Eng)
|
|
Yudov Y.
|
| Volume 65, Nº 10 (2018) |
The Challenging Thermophysical Issues of Fast Reactors |
(Eng)
|
|
Sorokin A., Kuzina Y., Trufanov A., Kamaev A., Orlov Y., Alekseev V., Grabezhnaya V., Zagorul’ko Y.
|
| Volume 65, Nº 9 (2018) |
The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 2: Validation and Verification |
(Eng)
|
|
Alipchenkov V., Boldyrev A., Veprev D., Zeigarnik Y., Kolobaeva P., Moiseenko E., Mosunova N., Seleznev E., Strizhov V., Usov E., Osipov S., Gorbunov V., Afremov D., Semchenkov A.
|
| Volume 65, Nº 9 (2018) |
Treatment of the Equations of Metal Oxidation Rates at Nuclear Power Plants and Thermal Power Plants in Terms of Thermodynamics |
(Eng)
|
|
Kritskii V., Berezina I., Gavrilov A., Motkova E., Prokhorov N.
|
| Volume 65, Nº 7 (2018) |
Mechanisms Governing Fine Fragmentation of Hot Melt Immersed in Cold Water |
(Eng)
|
|
Ivochkin Y., Zeigarnik Y., Kubrikov K.
|
| Volume 65, Nº 5 (2018) |
The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 1: Basic Models |
(Eng)
|
|
Mosunova N.
|
| Volume 65, Nº 4 (2018) |
Graphical Toolkit for Easy and Rapid Evaluation of the Residual Heat Generation at Cyclic Operation of a Pool Type Research Reactor |
(Eng)
|
|
Kadalev S.
|
| Volume 65, Nº 4 (2018) |
Prospects for Using Weakly Dissociated Ion Exchange Resins in Special Water Treatment Systems at VVER-Based Nuclear Power Plants for Reducing the Volume of Radioactive Waste Generated |
(Eng)
|
|
Vinnitskii V., Chugunov A., Nechaev A.
|
| Volume 65, Nº 4 (2018) |
Effect of Hydrazine on Redistribution of Corrosion Product Deposits in the Primary Circuit of a Shutdown Reactor in Propulsion-Type Nuclear Power Plants |
(Eng)
|
|
Orlov S., Zmitrodan A., Mysik S.
|
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