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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
Chistov A., Savikhin O., Ovchinnikov V., Kiryushina E.
PDF
(Eng)
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
Kabakchi S., Luzakov A., Urtenov D., Katanova E., Gasai I., Verkhovskii A.
PDF
(Eng)
Volume 63, Nº 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)
Volume 65, Nº 11 (2018)
Comparative Estimation of the Effect from Using Different Coolants in Panel-Type Radiators of Spacecrafts
Volkov N., Volkova L., Grigor’ev A., Il’mov D., Karevskii A., Mamontov Y., Mironov V., Sobolev V., Filatov N.
PDF
(Eng)
Volume 63, Nº 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)
Volume 65, Nº 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)
Volume 63, Nº 2 (2016)
Correct numerical simulation of a two-phase coolant
Kroshilin A., Kroshilin V.
PDF
(Eng)
Volume 66, Nº 10 (2019)
Water Chemistry Development for a Thermal Power Plant Circulating Cooling System Using the VTIAMIN EKO-1 Chemical Agent
Kirilina A., Suslov S., Kozlovskii V., Larin A.
PDF
(Eng)
Volume 65, Nº 5 (2018)
The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 1: Basic Models
Mosunova N.
PDF
(Eng)
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
Orlov S., Zmitrodan A., Mysik S.
PDF
(Eng)
Volume 66, Nº 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)
Volume 64, Nº 10 (2017)
Experimental investigation of the impulse gas injection into liquid and the use of experimental data for verification of the HYDRA-IBRAE/LM thermohydraulic code
Lobanov P., Usov E., Butov A., Pribaturin N., Mosunova N., Strizhov V., Chukhno V., Kutlimetov A.
PDF
(Eng)
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
Butov A., Zhdanov V., Klimonov I., Kudashov I., Kutlimetov A., Lobanov P., Mosunova N., Sorokin A., Strizhov V., Usov E., Chukhno V.
PDF
(Eng)
Volume 64, Nº 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)
Volume 66, Nº 4 (2019)
Hydrodynamic Features of the Flow Downstream from the Mixing Spacer Grid in a Kvadrat Fuel Assembly in PWRs
Samoilov O., Noskov A., Shipov D., Dmitriev S., Dobrov A., Doronkov D., Legchanov M., Pronin A., Solntsev D., Sorokin V., Khrobostov A.
PDF
(Eng)
Volume 63, Nº 8 (2016)
Definition of hydraulic stability of KVGM-100 hot-water boiler and minimum water flow rate
Belov A., Ozerov A., Usikov N., Shkondin I.
PDF
(Eng)
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