A5017436591- Nuclear Engineering Thermal-Hydraulics
- Nuclear Materials and Properties
- Fluid Dynamics and Mixing
- Nuclear reactor physics and engineering
- Heat Transfer and Boiling Studies
- nanoparticles nucleation surface interactions
- Advanced Power Generation Technologies
- Graphite, nuclear technology, radiation studies
- Nuclear and radioactivity studies
- Metallurgical Processes and Thermodynamics
- Oil and Gas Production Techniques
- Heat transfer and supercritical fluids
- Spacecraft and Cryogenic Technologies
- Lattice Boltzmann Simulation Studies
- Particle Dynamics in Fluid Flows
- Aquatic and Environmental Studies
- Advanced Thermodynamics and Statistical Mechanics
- Fluid Dynamics and Heat Transfer
- Solidification and crystal growth phenomena
- Combustion and Detonation Processes
- Rocket and propulsion systems research
- Cyclone Separators and Fluid Dynamics
- Aerosol Filtration and Electrostatic Precipitation
- Hydraulic and Pneumatic Systems
- Educational Innovations and Challenges
All-Russian Scientific Research Institute for Operation of Nuclear Power Plants
2003-2015
Moscow Power Engineering Institute
2014
National Aerospace University – Kharkiv Aviation Institute
1993-1997
Moscow Aviation Institute
1987
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...
Thermal control systems of space vehicles, being developed and prospective, including heavy weight orbital stations, platforms, interplanetary missions, lunar villages modules, will be most likely based on two-phase heat transport loops. The paper presents complex program fundamental applied studies hydrodynamics transfer in microgravity. is performed by four Russian organizations under financial support NASA. It directed towards solution practical problems arising when International Space...
A quasi-one-dimensional, five-equation model has been developed on a microcomputer to calculate the behavior of flowing, initially subcooled, flashing liquids. Equations for mixture and vapor mass conservation, momentum liquid energy bubble transport were discretized linearized semi-implicitly, solved using successive iteration Newton method. Closure was obtained through simple constitutive equations friction spherical growth, new nucleation wall in small nozzles combined with an existing...
The EREC-STRESA web-based database contains a large scope of experimental data. It is the unique most complete resulted from thermohydraulic experiments dedicated to analysis Russian LWR NPPs safety. This paper presents description further evolution Database.
There is a considerable amount of resources devoted to experimental databases in the field NPPs safety at international level. Most them have no data concerning light water reactors Russian type. EREC has gained large scope for such reactors. This paper presents EREC-STRESA web-based database. It unique most complete database resulted from thermohydraulic experiments dedicated analysis LWR safety.
New design of nuclear power plant with pressurized water reactor entitled “NPP-2006” is under progress in Russia. It evolutionary type based on existing NPP VVER-1000 reactors. Intensive thermal-hydraulic experimental activities support development. They are aimed at increasing safety and efficiency. Integral test facility PSB-VVER, modeling main components primary system VVERs, the tool for studies. Volumetric-power scale 1:300, elevations 1:1. A core model an assembly 168 fuel rod...
Abstract During a severe accident in nuclear reactor, an ex-vessel steam explosion may occur when the molten core come into contact with liquid coolant, crucial factor fuel-coolant interaction is fragmentation of melt small droplets, which rapidly increase heat transfer to and could lead formation pressure wave disastrous consequence for surrounding components. In this research numerical simulation was performed using VAPEX-D code being developed at Department NPP “Moscow Power Engineering...