Nuclear Power Stations

Выпуск Название Файл
Том 65, № 1 (2018) Investigation into Behavior of a Steam-Water Mixture Flow Through Holes in a Submerged Perforated Sheet at High Void Fractions PDF
(Eng)
Melikhov O., Nerovnov A., Nikonov S., Melikhov V.
Том 65, № 1 (2018) Thermodynamic Simulation of Equilibrium Composition of Reaction Products at Dehydration of a Technological Channel in a Uranium-Graphite Reactor PDF
(Eng)
Pavliuk A., Zagumennov V., Kotlyarevskiy S., Bespala E.
Том 64, № 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 PDF
(Eng)
Lobanov P., Usov E., Butov A., Pribaturin N., Mosunova N., Strizhov V., Chukhno V., Kutlimetov A.
Том 64, № 10 (2017) Application of synthetic fire-resistant oils in oil systems of turbine equipment for NPPs PDF
(Eng)
Galimova L.
Том 64, № 7 (2017) Effect of boric acid mass transfer on the accumulation thereof in a fuel core under emergency modes at NPPs with WMR PDF
(Eng)
Morozov A., Sorokin A., Ragulin S., Pityk A., Sahipgareev A., Soshkina A., Shlepkin A.
Том 64, № 7 (2017) Experimental investigation of a new method for advanced fast reactor shutdown cooling PDF
(Eng)
Pakholkov V., Kandaurov A., Potseluev A., Rogozhkin S., Sergeev D., Troitskaya Y., Shepelev S.
Том 64, № 7 (2017) System of closing relations of a two-fluid model for the HYDRA-IBRAE/LM/V1 code for calculation of sodium boiling in channels of power equipment PDF
(Eng)
Usov E., Butov A., Dugarov G., Kudasov I., Lezhnin S., Mosunova N., Pribaturin N.
Том 64, № 1 (2017) Experimental facility for the study of acoustic emission registered in the primary circuit components of WWER power units PDF
(Eng)
Petrosyan V., Hovakimyan T., Yeghoyan E., Hovhannisyan H., Mayilyan D., Petrosyan A.
Том 64, № 1 (2017) Experimental studies of heat exchange for sodium boiling in the fuel assembly model: Safety substantiation of a promising fast reactor PDF
(Eng)
Khafizov R., Poplavskii V., Rachkov V., Sorokin A., Trufanov A., Ashurko Y., Volkov A., Ivanov E., Privezentsev V.
Том 64, № 1 (2017) Determination of the steam volume fraction in the event of loss of cooling of the spent fuel storage pool PDF
(Eng)
Sledkov R., Galkin I., Stepanov O., Strebnev N.
Том 64, № 1 (2017) Prediction and modeling of the two-dimensional separation characteristic of a steam generator at a nuclear power station with VVER-1000 reactors PDF
(Eng)
Parchevsky V., Guryanova V.
Том 63, № 11 (2016) Design of high-pressure direct contact heater for promising power supply units: Experimental substantiation PDF
(Eng)
Somova E., Shvarts A., Turkin A.
Том 63, № 8 (2016) Experimental studies of local coolant hydrodynamics using a scaled model of cassette-type fuel assembly of a KLT-40S reactor PDF
(Eng)
Dmitriev S., Barinov A., Varentsov A., Doronkov D., Solntsev D., Khrobostov A.
Том 63, № 8 (2016) Procedure of calculation of the spatial distribution of temperatures and heat fluxes in the steam generator of a nuclear power installation with an RBEC fast-neutron reactor PDF
(Eng)
Frolov A., Sedov A.
Том 63, № 7 (2016) Modeling the transport of nitrogen in an NPP-2006 reactor circuit PDF
(Eng)
Stepanov O., Galkin I., Sledkov R., Melekh S., Strebnev N.
Том 63, № 5 (2016) Purification of liquid metal systems with sodium coolant from oxygen using getters PDF
(Eng)
Kozlov F., Konovalov M., Sorokin A.
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 PDF
(Eng)
Alipchenkov V., Anfimov A., Afremov D., Gorbunov V., Zeigarnik Y., Kudryavtsev A., Osipov S., Mosunova N., Strizhov V., Usov E.
Том 63, № 1 (2016) Influence of nonuniformity of the submerged perforated sheet on steam demand leveling on the evaporation surface of a VVER steam generator PDF
(Eng)
Blinkov V., Elkin I., Emelianov D., Melikhov V., Melikhov O., Nerovnov A., Nikonov S., Parfenov Y.
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