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Том 66, № 4 (2019)
Topical Problems Concerned with the Thermophysical Characteristics of New-Generation Light Water Reactors: Comprehensive Study Results
Sorokin A., Kuzina Y., Trufanov A., Loshchinin V., Levchenko Y., Morozov A.
PDF
(Eng)
Том 63, № 9 (2016)
Estimation of thermal loads on the VVER vessel under conditions of inversion of the stratified molten pool in a severe accident
Loktionov V., Mukhtarov E.
PDF
(Eng)
Том 66, № 5 (2019)
Verification of the EUCLID/V2 Code Based on Experiments Involving Destruction of a Liquid Metal Cooled Reactor’s Core Components
Butov A., Zhdanov V., Klimonov I., Kudashov I., Kutlimetov A., Lobanov P., Mosunova N., Sorokin A., Strizhov V., Usov E., Chukhno V.
PDF
(Eng)
Том 66, № 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
Yudov Y., Petkevich I., Artemov V.
PDF
(Eng)
Том 64, № 7 (2017)
Experimental investigation of a new method for advanced fast reactor shutdown cooling
Pakholkov V., Kandaurov A., Potseluev A., Rogozhkin S., Sergeev D., Troitskaya Y., Shepelev S.
PDF
(Eng)
Том 63, № 8 (2016)
Experimental studies of local coolant hydrodynamics using a scaled model of cassette-type fuel assembly of a KLT-40S reactor
Dmitriev S., Barinov A., Varentsov A., Doronkov D., Solntsev D., Khrobostov A.
PDF
(Eng)
Том 66, № 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
Yudov Y., Petkevich I., Artemov V., Kasterin D., Rumyantsev S.
PDF
(Eng)
Том 65, № 13 (2018)
On the Question of “Decisive Advantages” of Thermionic Conversion for Space Power Systems
Koroteev A.
PDF
(Eng)
Том 64, № 5 (2017)
Fast reactor: an experimental study of thermohydraulic processes in different operating regimes
Opanasenko A., Sorokin A., Zaryugin D., Trufanov A.
PDF
(Eng)
Том 63, № 7 (2016)
Modeling the transport of nitrogen in an NPP-2006 reactor circuit
Stepanov O., Galkin I., Sledkov R., Melekh S., Strebnev N.
PDF
(Eng)
Том 66, № 10 (2019)
Simulation of Heat and Mass Transfer in an Organic Compound Pyrolysis Reactor
Zroichikov N., Fadeev S., Kaverin A., Pai A.
PDF
(Eng)
Том 65, № 10 (2018)
The Challenging Thermophysical Issues of Fast Reactors
Sorokin A., Kuzina Y., Trufanov A., Kamaev A., Orlov Y., Alekseev V., Grabezhnaya V., Zagorul’ko Y.
PDF
(Eng)
Том 64, № 2 (2017)
Development of a thermal scheme for a cogeneration combined-cycle unit with an SVBR-100 reactor
Kasilov V., Dudolin A., Krasheninnikov S.
PDF
(Eng)
Том 63, № 5 (2016)
Purification of liquid metal systems with sodium coolant from oxygen using getters
Kozlov F., Konovalov M., Sorokin A.
PDF
(Eng)
Том 66, № 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
Chistov A., Savikhin O., Ovchinnikov V., Kiryushina E.
PDF
(Eng)
Том 65, № 9 (2018)
The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 2: Validation and Verification
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.
PDF
(Eng)
Том 64, № 1 (2017)
Experimental studies of heat exchange for sodium boiling in the fuel assembly model: Safety substantiation of a promising fast reactor
Khafizov R., Poplavskii V., Rachkov V., Sorokin A., Trufanov A., Ashurko Y., Volkov A., Ivanov E., Privezentsev V.
PDF
(Eng)
Том 63, № 4 (2016)
Modeling of corrosion product migration in the secondary circuit of nuclear power plants with WWER-1200
Kritskii V., Berezina I., Gavrilov A., Motkova E., Zelenina E., Prokhorov N., Gorbatenko S., Tsitser A.
PDF
(Eng)
Том 66, № 7 (2019)
Achieving More Efficient Removal of α-Emitting Radionuclides from the Primary Coolant in Propulsion Reactors
Orlov S., Zmitrodan A., Mysik S.
PDF
(Eng)
Том 65, № 9 (2018)
The Impact of Design Deviations on Dynamic Characteristics of a Flexible Multispan Rotor on Complete Electromagnetic Suspension
Ovchinnikov V., Nikolaev M., Litvinov V., Kodochigov N., Drumov I.
PDF
(Eng)
Том 63, № 13 (2016)
Comparison of the technical and economic parameters of different variants of the nuclear fuel cycle reactors of the nuclear power plants
Tolstoukhov D., Panov S., Adamov E., Rachkov V.
PDF
(Eng)
Том 63, № 2 (2016)
Fundamentals, current state of the development of, and prospects for further improvement of the new-generation thermal-hydraulic computational HYDRA-IBRAE/LM code for simulation of fast reactor systems
Alipchenkov V., Anfimov A., Afremov D., Gorbunov V., Zeigarnik Y., Kudryavtsev A., Osipov S., Mosunova N., Strizhov V., Usov E.
PDF
(Eng)
Том 66, № 7 (2019)
Verification of the TIGRSP Computer Code as Applied to a 19-Rod Fuel Assembly Using CFD Computations
Stepanov O., Galkin I., Melekh S., Kurnosov M., Pronin A.
PDF
(Eng)
Том 65, № 5 (2018)
The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 1: Basic Models
Mosunova N.
PDF
(Eng)
Том 65, № 1 (2018)
Thermodynamic Simulation of Equilibrium Composition of Reaction Products at Dehydration of a Technological Channel in a Uranium-Graphite Reactor
Pavliuk A., Zagumennov V., Kotlyarevskiy S., Bespala E.
PDF
(Eng)
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