A5031281269- Nuclear Engineering Thermal-Hydraulics
- Nuclear Materials and Properties
- Combustion and Detonation Processes
- Nuclear reactor physics and engineering
- Fluid Dynamics and Heat Transfer
- Particle Dynamics in Fluid Flows
- Fluid Dynamics and Mixing
- Ultrasound and Cavitation Phenomena
- Heat Transfer and Boiling Studies
- Combustion and flame dynamics
- Cyclone Separators and Fluid Dynamics
- Nuclear and radioactivity studies
- Oil and Gas Production Techniques
- Graphite, nuclear technology, radiation studies
- Advanced Power Generation Technologies
- Coal Combustion and Slurry Processing
- Granular flow and fluidized beds
- Aeolian processes and effects
- Fire dynamics and safety research
- Computational Fluid Dynamics and Aerodynamics
- Gas Dynamics and Kinetic Theory
- Thermodynamic and Structural Properties of Metals and Alloys
- Nuclear Physics and Applications
- Aquatic and Environmental Studies
- Spacecraft and Cryogenic Technologies
Moscow Power Engineering Institute
2012-2024
Institute for Problems in Mechanics
2020-2021
All-Russian Scientific Research Institute for Operation of Nuclear Power Plants
2002-2015
Russian Academy of Sciences
1983
The OECD/NEA PSB-VVER project provided unique and useful experimental data for code validation from test facility. This facility represents the scaled-down layout of Russian-designed pressurized water reactor, namely, VVER-1000. Five experiments were executed, dealing with loss coolant scenarios (small, intermediate, large break accidents), a primary-to-secondary leak, parametric study (natural circulation test) aimed at characterizing VVER system reduced mass inventory conditions....
The horizontal steam generator (SG) is one of specific features Russian‐type pressurized water reactors (VVERs). main advantages are connected with low loads on evaporation surface, simple separation scheme and high circulation ratio. complex three‐dimensional steam‐water flows in the vessel influence significantly processes separation, distribution, deposition soluble nonsoluble impurities determine efficiency reliability operation. 3D code for simulation could be effective tool design...
The hydrodynamic and thermal interaction of water with the high-temperature melt a heavy metal was studied via Volume-of-Fluid (VOF) method formulated for three immiscible phases (liquid melt, water, vapor), account phase changes. VOF relies on first-principle description interactions, including drag, heat transfer, evaporation, in contrast to multifluid models relying empirical correlations. verification model implemented OpenFOAM software performed by solving one- two-dimensional reference...
In the frame of Tacis Project R2.01/99, which was running from 2003 to 2005, bubble condenser system Kola NPP (unit 3) qualified at integral test facility BC V-213. Three LB LOCA tests, two MSLB and one SB were performed. The appropriate scenarios for V-213 facility, modeling accidents in unit 3, determined with pretest calculations. Analysis results has shown that calculated initial conditions properly reproduced tests. detailed posttest analysis tests performed aimed validate COCOSYS code...
Flash evaporation of a superheated water droplet in heavy liquid metal coolant (lead) is considered, application to the analysis lead-cooled fast reactor steam generator tube rupture accident. The model based on thermodynamic equilibrium formulation for expanding water-steam mixture and inviscid compressible surrounding lead, with interface conditions determined from solution Riemann problem. Numerical performed spherically symmetric geometry using conservative numerical scheme moving sharp...