Main activities of the laboratory:
- homogenizing inserts for eliminating vibrations in pipelines with two phase flow (vaporing);
- inserts for limiting the two-phase and one-phase flows and other non-standard equipment for nuclear power plant pipelines;
- highly efficient heat exchangers with heat-transmitting surface, shaped with dimples;
- condensing systems for confinement systems in NPP failure case;
- equipment element tests at extremely low temperatures;
- complex solution to scientific problems related to storage and transportation of used nuclear fuel and fissile material;
- research related to modernization of operating equipment, such as moisture separators-reheaters (MSR) of units with RBMK reactors (High Power Channel-Type Reactors), as well as acceptance tests of modernized equipment at the site;
- research of aerosol transport processes in power-generating equipment of nuclear power plants in case of severe accidents;
- thermal hydraulics of elements of the International Thermonuclear Experimental Reactor (ITER); test research of liquid metal coolers; protective coatings of turbine condenser tube bundles; modelling of transition on low-boiling coolants.
Main work completed by the laboratory
The laboratory has developed a device that eliminates vibrations in pipelines that transport boiling liquids to the nuclear and thermal power plants. The device allows rearranging a structure of a two-phase flow – it eliminates a slug flow, which is dangerous due to vibrations created by it. Industrial tests of inserts on condensate drain pipelines at stages I and II of SMR to the deaerator at Khmelnitskiy, Kalininskiy, Smolenskiy and Kurskiy nuclear power plants, as well as Kozloduy nuclear power plant in Bulgaria allowed lowering the vibration amplitude by 3÷5 times, making the vibration level safe.
Homogenizing inserts for eliminating vibrations in pipelines with two phase vaporing flow
Inserts for limiting the two-phase and one-phase flows and other non-standard equipment for nuclear power plant pipelines
The dimpled pipe production technology has been developed. Currently, tubular plate-type heat exchanger with dimpled plates are undergoing preparations for testing.
The laboratory has designed a new injection condenser for SOVA-TK system (radioactive release limitation system for the event of pressure channel rupture) at the Kurskaya nuclear power plant.
Highly efficient heat exchangers with heat-transmitting surface, shaped with dimples
Condensing systems for confinement systems for PPT failure case
The laboratory has a 15-cubic meter cooling chamber. Refrigeration capacity – 12 kW at the temperature inside the chamber – negative 58 °C. The chamber is designed for determining the operating performance and life tests of heating equipment elements.
The laboratory has conducted a large experimental research thermal hydraulic features of Russian Fissile Material Storage Facility and ISFSI (Independent Spent Fuel Storage Installation, see the figure).
Equipment element tests at extremely low temperatures
Storage of used nuclear fuel and fissile material
- The laboratory has conducted a research of heat removal from spent fuel elements placed for transportation and storage in vertical and horizontal protective containers; the laboratory has developed their thermal and strength design methods that comply with IAEA requirements.
- The laboratory has completed thermal (and strength) design of the transport package TUK-6 for 30 spent fuel assemblies (SFA) of VVER-440 reactor, at well as TUK-10 and two types of TUK-13 for 6 and 12 assemblies of VVER-1000 reactor accordingly. The specified transport packages are still in operation and ensure uninterrupted work of domestic nuclear power plants with water-water reactors.
- In cooperation with the State Research Center CNIITMASH and Petrozavodskmash plant, the laboratory conducted a research of ductile iron with spherical graphite aimed to determine its suitability for casting TUK shells (a 40-ton container shell was cast and specifications were released for ductile iron with spherical graphite).
- The laboratory conducts complex research of performance characteristics of heat exchanging equipment at nuclear power plants. When measuring temperature and flow characteristics the laboratory uses standard equipment (thermocouples, resistance thermometer, ultrasonic flowmeter, etc.).
- To measure humidity of steam flows the laboratory developed a small-size throttling calorimeter (see the figure), which allows determining humidity of saturated steam with minimum consumption of measured medium (less than 15 kg/h).
- The aerosol deposition and entrainment processes are studied on a special test bed using generators of liquid and hard aerosol. Air velocity in deposition experiments reaches 40 m/s; in entrainment experiments – more than 100 m/s.
- The research conducted at the remote control section allowed developing the coolant flow measurement using a thermal imaging camera.
Work performed at nuclear power plants
Research of aerosol transport processes in power-generating equipment of nuclear power plants in cause of severe accidents
Thermal hydraulics of elements of the International Thermonuclear Experimental Reactor (ITER)
Protective coatings of turbine condenser tube bundles
- Protective coatings allow preventing corrosion, restore damaged tubes, extend service life of low-pressure condensers, prevent emergency shutdowns of power units caused by tube damage.
- In cooperation with coatings designer NPO ROCOR the laboratory conducted a comprehensive research aimed to solve thermophysical problems that occur when protective polymeric coatings are applied to the inner surfaces of low pressure condenser tubes. In particular, heat conductivity of coating material was increased.
- The laboratory has completed a huge volume of research on natrium, lead-bismuth alloys and indium-gallium-stannum alloys.
- The laboratory has completed a huge volume of research on natrium, lead-bismuth alloys and indium-gallium-stannum alloys.
Test research of liquid metal coolers
