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卷 66, 编号 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.
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(Eng)
卷 64, 编号 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)
卷 64, 编号 5 (2017)
Fast reactor: an experimental study of thermohydraulic processes in different operating regimes
Opanasenko A., Sorokin A., Zaryugin D., Trufanov A.
PDF
(Eng)
卷 66, 编号 5 (2019)
The EUCLID/V2 Code Physical Models for Calculating Fuel Rod and Core Failures in a Liquid Metal Cooled Reactor
Butov A., Zhdanov V., Klimonov I., Kudashov I., Kutlimetov A., Mosunova N., Strizhov V., Sorokin A., Frolov S., Usov E., Chukhno V.
PDF
(Eng)
卷 64, 编号 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)
卷 63, 编号 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)
卷 65, 编号 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)
卷 63, 编号 5 (2016)
Purification of liquid metal systems with sodium coolant from oxygen using getters
Kozlov F., Konovalov M., Sorokin A.
PDF
(Eng)
卷 65, 编号 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)
卷 63, 编号 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)
卷 65, 编号 5 (2018)
The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 1: Basic Models
Mosunova N.
PDF
(Eng)
卷 64, 编号 13 (2017)
New Technological Platform for the National Nuclear Energy Strategy Development
Adamov E., Rachkov V.
PDF
(Eng)
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