fast reactor

A Method to Calculate the Stress-Strain State of a Cylinder Using Quadratic Radius Functions for Approximation of Stress and Displacement Rates

3/28/2023 2023 - #01 Modelling processes at nuclear facilities

Ganina S.M. Zabud‘ko L.M. Marinenko E.E. Folomeev V.I.

Experimental Study of a Microwave Reflex-Radar Level Gauge of a Liquid-Metal Coolant

1/20/2022 2022 - #01 Global safety, reliability and diagnostics of nuclear power installations

Melnikov V.I. Bokova T.A. Ivanov V. V. Marov A.P. Lobaeva N.A. Kvashennikov A.S. Bokov P.A. Volkov N.S.

Modelling of Closed Fuel Cycle of the Lead-Cooled Fast Reactor

12/08/2021 2021 - #04 Fuel cycle and nuclear waste management

Balovnev A.V. Davydov V.K. Zhirnov A.P. Moiseev A.V. Soldatov E.O.

On a significant deceleration of the kinetics of fast transient processes in a fast reactor

9/16/2020 2020 - #03 Nuclear power plants

Kulikov G.G. Shmelev A.N. Apse V.A. Kulikov E.G.

Safety of a fast reactor with a reflector containing a moderator with heavy atomic weight and weak neutron absorption

12/05/2019 2019 - #04 Global safety, reliability and diagnostics of nuclear power installations

Kulikov G.G. Shmelev A.N. Apse V.A. Kulikov E.G.

Small power lead fast reactor with metallic fuel

3/23/2018 2018 - #01 Physics and technology of nuclear reactors

Khorasanov G.L. Samokhin D.S. Zevyakin A.S. Zemskov E.A. Blokhin A.I.

Features of technology of purification from impurities of high-temperature sodium coolant in a fast reactor for hydrogen production and other innovative applications

12/25/2016 2016 - #04 Nuclear materials

Kozlov F.A. Kalyakin S.G. Sorokin A.P. Alekseev V.V. Trufanov A.A. Konovalov M.A. Orlova E.A.

Investigations for the substantiation of high-temperature nuclear power generation technology using fast sodiumcooled reactor for hydrogen production and other innovative applications (part 1)

10/02/2016 2016 - #03 Physics and technology of nuclear reactors

Kalyakin S.G. Kozlov F.A. Sorokin A.P. Bogoslovskaya G.P. Ivanov A.P. Konovalov M.A. Morozov A.V. Stogov V.Yu.

Modeling of natural circulation for the inherent safety analysis of sodium cooled fast reactors

10/02/2016 2016 - #03 Physics and technology of nuclear reactors

Bochkarev A.S. Alekseev P.N. Korsun A.S. Kharitonov V.S.

Development of the code CYCLE for nuclear fuel cycle analysis

3/28/2016 2016 - #01 Fuel cycle and nuclear waste management

Kalashnikov A.G. Moseev A. L. Dekusar V.M. Korobeynikov V.V. Moseev P.A.

Nodal SN method for HEX-Z-geometry

10/23/2015 2015 - #03 Modelling processes at nuclear facilities

Bereznev V.P.

Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety justification

10/23/2015 2015 - #03 Thermal physics and thermal hydraulics

Khafizov R.R. Poplavsky V.M. Rachkov V.I. Sorokin A.P. Ashurko Yu.M. Volkov A.V. Ivanov E.F. Privezentsev V.V.

Prospects of VVER-SKD in a closed fuel cycle

4/04/2015 2015 - #01 Current issues in nuclear energy

Glebov A.P. Klushin A.V. Baranayev Yu.D.

Swelling of guide tubes for safety rods in nonuniform fields of temperature and irradiation

4/04/2015 2015 - #01 Nuclear materials

Porollo S.I. Konobeev Yu.V. Garner F.A.

The «CORNER» neutronics calculation code

4/04/2015 2015 - #01 Physics and technology of nuclear reactors

Bereznev V.P. Seleznyov E.F. Asatrian D.S.

Innovative nuclear power technology – the basis of large-scale nuclear power engineering

5/29/2014 2014 - #01 Current issues in nuclear energy

Rachkov V.I. Kalyakin S.G.

Research on the possibility of melted fuel containment in a fast reactor at a severe accident

5/29/2014 2014 - #01 Global safety, reliability and diagnostics of nuclear power installations

Kascheev M.V. Ashurko Yu.M.

The UNICO multi-physics code to analyze transients in sodium fast reactors

5/29/2014 2014 - #01 Modelling processes at nuclear facilities

Shvetsov Yu. E. Ashurko Yu.M. Suslov I.R. Raskach K.F. Zabud‘ko L.M. Marinenko E.E.

Experimental researches of thermal hydraulic characteristics in the model of sodium-air heat exchanger for fast reactor emergency cooling system

5/29/2014 2014 - #01 Thermal physics and thermal hydraulics

Sorokin A.P. Ivanov E.F. Bogoslovskaya G.P. Levchenko Yu. D. Privezentsev V.V. Rymkevich K.S. Zueva I.R.

Experimental study on hydraulic resistance of finned tube assembly of the air heat exchangers in fast reactors

5/29/2014 2014 - #01 Thermal physics and thermal hydraulics

Kolomiyets D.О. Levchenko Yu. D.