| Issue |
Title |
File |
| Vol 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.V., Petkevich I.G., Artemov V.G.
|
| Vol 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.V., Petkevich I.G., Artemov V.G., Kasterin D.S., Rumyantsev S.N.
|
| Vol 66, No 8 (2019) |
Physical Modeling of Hydrodynamic and Heat Transfer Processes in Liquid-Metal Cooled Nuclear Power Facilities |
(Eng)
|
|
Sorokin A.P., Kuzina Y.A.
|
| Vol 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.S., Savikhin O.G., Ovchinnikov V.F., Kiryushina E.V.
|
| Vol 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.I., Perevezentsev V.V.
|
| Vol 66, No 7 (2019) |
Achieving More Efficient Removal of α-Emitting Radionuclides from the Primary Coolant in Propulsion Reactors |
(Eng)
|
|
Orlov S.N., Zmitrodan A.A., Mysik S.G.
|
| Vol 66, No 7 (2019) |
Verification of the TIGRSP Computer Code as Applied to a 19-Rod Fuel Assembly Using CFD Computations |
(Eng)
|
|
Stepanov O.E., Galkin I.Y., Melekh S.S., Kurnosov M.M., Pronin A.A.
|
| Vol 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.G., Yeghoyan E.A., Grigoryan A.D., Martirosyan M.V.
|
| Vol 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.A., Popova T.V., Supotnitskaya O.V., Sergeev V.V., Bulynin V.D., Semashko S.E., Krylov Y.V.
|
| Vol 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.A., Zhdanov V.S., Klimonov I.A., Kudashov I.G., Kutlimetov A.E., Mosunova N.A., Strizhov V.F., Sorokin A.A., Frolov S.A., Usov E.V., Chukhno V.I.
|
| Vol 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.A., Zhdanov V.S., Klimonov I.A., Kudashov I.G., Kutlimetov A.E., Lobanov P.D., Mosunova N.A., Sorokin A.A., Strizhov V.F., Usov E.V., Chukhno V.I.
|
| Vol 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.S., Migrov Y.A.
|
| Vol 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.S., Merinov I.G., Kharitonov V.S., Bayaskhalanov M.V., Chudanov V.V., Aksenova A.E., Pervichko V.A.
|
| Vol 66, No 4 (2019) |
Topical Problems Concerned with the Thermophysical Characteristics of New-Generation Light Water Reactors: Comprehensive Study Results |
(Eng)
|
|
Sorokin A.P., Kuzina Y.A., Trufanov A.A., Loshchinin V.M., Levchenko Y.D., Morozov A.V.
|
| Vol 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.B., Noskov A.S., Shipov D.L., Dmitriev S.M., Dobrov A.A., Doronkov D.V., Legchanov M.A., Pronin A.N., Solntsev D.N., Sorokin V.D., Khrobostov A.E.
|
| Vol 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.A., Luzakov A.V., Urtenov D.S., Katanova E.A., Gasai I.A., Verkhovskii A.E.
|
| Vol 66, No 1 (2019) |
Correcting the Semi-Implicit Numerical Scheme Incorporated in the KORSAR Code Two-Liquid Model |
(Eng)
|
|
Yudov Y.V.
|
| Vol 65, No 10 (2018) |
The Challenging Thermophysical Issues of Fast Reactors |
(Eng)
|
|
Sorokin A.P., Kuzina Y.A., Trufanov A.A., Kamaev A.A., Orlov Y.I., Alekseev V.V., Grabezhnaya V.A., Zagorul’ko Y.I.
|
| Vol 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.M., Boldyrev A.V., Veprev D.P., Zeigarnik Y.A., Kolobaeva P.V., Moiseenko E.V., Mosunova N.A., Seleznev E.F., Strizhov V.F., Usov E.V., Osipov S.L., Gorbunov V.S., Afremov D.A., Semchenkov A.A.
|
| Vol 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.G., Berezina I.G., Gavrilov A.V., Motkova E.A., Prokhorov N.A.
|
| Vol 65, No 7 (2018) |
Mechanisms Governing Fine Fragmentation of Hot Melt Immersed in Cold Water |
(Eng)
|
|
Ivochkin Y.P., Zeigarnik Y.A., Kubrikov K.G.
|
| Vol 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.A.
|
| Vol 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.H.
|
| Vol 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.A., Chugunov A.S., Nechaev A.F.
|
| Vol 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.N., Zmitrodan A.A., Mysik S.G.
|
| 1 - 25 of 30 Items |
1 2 > >>
|
