Abstract: Methods for strengthening soils under bases and foundations of buildings and structures with compaction of the base composed of weak mineral soils by determining the optimal design process parameters of the ground piles over the entire area of the base. The essence of the invention is that the method of compaction of bases composed of weak mineral soils that includes formation of a well, filling each well with the compacting material, and creation of a compacting effect on the compacting material by the hollow tubular working tool to form a ground pile. Preliminary engineering and geological surveys of the base area is performed to determine the values of the modulus of deformation, the Poisson's ratio, the internal friction angle, the specific cohesion, the specific gravity, and the initial void ratio of the weak mineral soil.

Abstract: The single-action emergency thermal valve comprises a body with a through channel for coolant supply through its inlet in the direction of its outlet, and a fuse link in the through channel of the body; the fuse link consists of at least two parts, each of the two parts completely overlaps the section of the through channel, the parts are made of materials with different melting points, and are located in the through channel in series with the increase of the melting temperature of each successive part in the direction from the through channel inlet to its outlet, wherein the body can have transverse ribs and/or transverse ridges at the location of the fuse link.

Abstract: The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPPs), and can be used in severe accidents resulting in molten core, destruction of the reactor vessel and molten metal output into the containment volume of NPP. The technical result of the claimed invention is to increase the reliability of the reactor molten core localization device. The technical result of reactor molten core localization device is achieved due to the lower support consisting of radial supports of a horizontal embedded slab and radial supports installed in the lower part of the molten metal trap casing joined together by clamps, while the radial supports and the fasteners have oval shaped openings.

Abstract: A mobile compressed foam firefighting unit comprising a mixing chamber connected at the outlet to the foam feeder, and the following systems connected to the mixing chamber inlet: a water supply system comprising a water pump and a water pump drive, a foam concentrate supply system comprising a foam pump and a foam pump drive, and an air supply system comprising an air compressor and an air pump drive. The system includes a drive motor, and drives of the air compressor and the foam pump comprise variable hydraulic transmissions kinetically connected to the drive motor, and the system is equipped with a water flow meter, a throttle valve with an electric drive and a check valve, and an electronic control unit of the throttle valve installed in the water supply pipe between the water pump and the mixing chamber.

Abstract: A method for managing a life cycle of a complex engineering facility, comprising several steps. The steps include forming a facility structure of the facility; selecting constituent elements of the facility structure and the relationships between the constituent elements and a location of each of the constituent elements in a decomposition structure of the facility; forming a linked array of requirements related to the facility and to processes of implementation of the requirement for the facility; planning and accounting for the requirements in accordance with the structural decomposition of the facility, the requirements being assigned a certain status; and forming databases intended for storing an associated array of information about the constituent elements of the facility, the associated array of information comprising at least a plurality of documents related to design data and/or to supply and procurement data and/or to pre-commissioning data and/or operation data and/or facility configuration data.

Abstract: The invention relates to pipelines and equipment useful in nuclear power plants, heat power engineering, manufacturing engineering, petrochemistry, water supply, chemical and aerospace industries, and other fields. The invention relates to a pipe heat insulation casing consisted of metal elements and assembly method ensuring reliable electrical insulation of all elements. The connection of the metal elements is with lapping, the elements are with openings in the lapping area where the electrically-insulating spacers are set made of resilient, elastic-plastic, plastic, fully viscous or partially solidified material ensuring electrical insulation between the adjacent elements. The electrically-insulating spacers are applied to the lapping areas of the metal elements to fill the openings of the lapping areas thus arranging reliable pin connections between the spacer and adjacent casing elements.

Abstract: A method for treatment of spent ion-exchange resins for disposal includes feeding a mixture of spent ion-exchange resins to the a loading tank, separating the ion-exchange resins, feeding separated ion-exchange resins into the a drying chamber, vacuum drying the ion-exchange resins and subjecting the resins to additional heat treatment in a high-temperature furnace, and unloading the treated ion-exchange resins into a transport container. A device for treatment of spent ion-exchange resins includes a loading tank, a metering device connected to a drying chamber, an inclined feed screw located between the loading tank and the metering device, a vacuum pump, a heated gas filter, a high-temperature furnace equipped with a vacuum drying and gas purification system, and a feeding device located between the drying chamber and the high-temperature furnace. A docking unit is connected to a lower part of the high-temperature furnace.

Abstract: The method and system for bringing a nuclear power plant to a safe state after extreme effect reduce the temperature of the coolant after extreme effect. The system includes inlet and outlet pipelines, a steam generator, a storage tank and a heat exchanger, a separation tank above the steam generator and connected by two pipelines to a storage tank, a pump, a control unit. The method involves filling the system with coolant, feeding the coolant from the steam generator through the inlet pipeline and the storage tank to the heat exchanger, and feeding the coolant through the outlet pipeline back to the steam generator, wherein the pump is turned on for feeding the coolant and subsequent operation of the system. The first air valve is used to maintain pressure in the system, ensuring the absence of boiling of the coolant.

Abstract: Devices for eliminating radioactive contamination of radioactive waste by providing adaptive processing of the decontamination solution for reuse. The plant for electrochemical decontamination of metal radioactive waste includes a pipe equipped with shut-off valves, a radioactive waste processing module that comprises a unit for electrochemical decontamination connected by a ventilation channel to the ventilation module and pipe for decontamination solution supply and discharge equipped with shut-off valves.

Abstract: The invention relates to safe operation support systems of nuclear power plants (NPPs) at severe accidents, including methods and systems for cooling and cooling control of the reactors molten core. The invention increases safety of NPP and cooling efficiency of the molten core of a reactor. The invention increases the efficiency of cooling the molten core of a reactor by safely removing the heat load from the molten metal mirror, ensuring the elimination of vapor explosions. The invention changes the principle of cooling the reactor molten core, in that after the molten core destroys the reactor vessel, the conditions for subsequent cooling of the molten metal are determined by the characteristics of the trap casing, but not of the reactor.

Abstract: The reactor core includes at least one module, a solid neutron moderator, and a liquid neutron moderators. Each module contains a casing, at least one heat pipe, one fuel element and thermal insulation. The heat pipe comprises a casing, a wick, and a coolant. The fuel element is made of nuclear fuel, arranged along an evaporation area of the heat pipe, around the heat pipe casing, in thermal contact with the heat pipe casing, and enclosed in a can. Liquid metals are used as the coolant of the heat pipe. Thermal insulation is arranged between the can and the module casing. At least one hole is made in the solid neutron moderator. Each module is arranged within a respective hole of the solid neutron moderator. The space between the module casing and the solid neutron moderator is filled with a liquid neutron moderator.

Abstract: A nuclear reactor core includes at least one module, a solid neutron moderator, and liquid neutron moderator. Each module comprises a housing, at least one heat pipe, at least one fuel element, casing, and thermal insulation. The heat pipe comprises a housing, wick, and evaporating coolant. The fuel element includes a shell and nuclear fuel. An evaporation zone of the heat pipe and the fuel elements are enclosed by the casing. The casing is filled with a liquid coolant. Liquid metal, for example, lithium, calcium, lead, and/or silver, is used as the heat pipe coolant and the liquid coolant. The thermal insulation is arranged in a space between the casing and module housing. The solid neutron moderator has at least one hole, wherein at least one module is located. A space between the solid neutron moderator and module is filled with the liquid neutron moderator.

Abstract: A supercapacitor consisting of a tight protective housing, first and second electrodes, which are electrically insulated from each other. One or both electrodes are also insulated from the housing. Free volume of the cell and the space between the electrodes are filled with electrolyte fluid. On the surface of the first electrode there are applied carbonaceous materials comprising C-14 isotope. Method of supercapacitor construction lies in the preparation of the first and second electrodes with application of the surface layer made of carbonaceous materials, allocation of the first and second electrodes inside the tight housing and their electric insulation from each other, filling of the housing with electrolyte fluid. Into the layer of carbonaceous materials onto the surface of the first electrode the C-14 isotope is introduced.

Abstract: Chemical control system for a power plant including at least one coolant electrochemical indication sensor of a flow type electrically connected to the measurement data processing and transmission unit with its outlet connected to a central computer (CPC) controlling the actuator for injection of hydrogen and chemical reagents. The hydraulic inlet of the electrochemical sensor in use of the system is connected by a sampling tube to the power plant process circuit and its hydraulic outlet is hydraulically connected to the first heat exchanger and the first throttling device with a coolant supply circuit in series. The sampling tube is configured to pass a coolant sample to the coolant electromechanical sensor and the coolant supply circuit contains tubes and valves configured to reverse the flow of the coolant sample through the first throttling device.

Abstract: Modular heat insulation, manufactured as separate welded blocks of stainless corrosion-resistant steel, arranged on the pipeline outer surface. The boxes are filled with heat-insulating material and interconnected with quick-acting tension locks. The cover plates shield the block joints. A heat-insulating material being a set of minimum three corrugated or blistered shields is used. These shields are manufactured of stainless corrosion-resistant steel forming enclosed air cavities. The external lining sheets of the adjacent blocks are shorter than the blocks themselves by the size of the cover plates and are installed with a lateral ventilated gap from the external surface of the shield set. The cover plates shall have the shape of mated sections with a multilayer set of corrugated stainless corrosion-resistant steel sheets. The mated sections are quick-acting tension locks, and their cover plates have width overlapping the area of blocks' increased temperature within their joints.

Abstract: A bath electrical heating device for deactivation designed to provide heating of bath deactivation and the deactivating solution in it before deactivation of reactor facility equipment and ensuring the removal of excess heat in the process of deactivation. The invention improves reliability, reduces the material consumption of the device and simplifies the structure installation and repair. The device performs at least from three heat insulation blocks in the form of coaxial metal screens, installed with an air gap from the heater. The heater with current leads is made in hermetic perform, each heat insulation blocks supplemented with an air-gap coaxial metal protective casing. The air gap of which in the upper part is covered with a cap with a visor whose diameter exceeds the external diameter of the protective casing, wherein solid cover of the upper protective casing install a sealed coupling.

Abstract: Nuclear power plant (NPP) containment building separation system dividing the NPP containment building into isolated containment building rooms. The system includes containment building separation shutters located in the circular gap which divides the containment building rooms and the containment building walls; an air supply unit connected to a manifold ring which, in turn, is connected to the air-inflated shutters designed to ensure insulation of the airspace inside the containment building rooms when inflated and to connect the airspace when deflated. In emergency mode the air supply to the air-inflated shutters is terminated, and the shutters get deflated and fully open the circular gap which ensures convection process throughout the whole area of containment building.

Abstract: Non-Volume displacement pumps used at nuclear power plants (NPP) in reactor coolant pump sets for the primary coolant circuit of the nuclear power system. The reactor coolant pump set comprising a vertical vane-type single-stage pump with bottom arrangement of the impeller, the pump shaft is connected to the electric motor shaft by a rigid coupling, the radial-axial bearing, installed in the electric motor upper chamber, is made of two main elements: a radial bearing made in the form of a rotor metallic bushing installed on the cylindrical part of the collar and an axial bearing consisting of two stator lever-type balance arm systems with cover plates of antifriction material and rotor cover plates of antifriction material. The radial-axial bearing is cooled by water from the NPP system, pressure head whereof is increased by the screw-type pump located on the upper butt of the radial-axial bearing collar.

Abstract: The invention is related to nuclear technologies, in particular, to the technology of producing nuclear oxide fuel for fuel elements, this oxide fuel can be used for manufacturing palletized nuclear fuel from uranium dioxide to be consumed by NPPs. The essence of the invention: this method of producing palletized nuclear fuel from uranium dioxide involves preparation of uranium dioxide moulding powder with/without uranium oxide, at this point powdered uranium dioxide is used as a raw material for preparation of moulding powder. Powdered uranium dioxide should be in the following proportion: O/U=2.37±0.04, it is obtained using a renowned method—by air heating of powdered uranium dioxide (ceramic grade) with the following proportion O/U=2.01?2.15. The technical result of the invention is increased mechanical strength of sintered pellets and a larger grain size of sintered pellets.

Abstract: The invention relates to the complex processing of a nuclear power plant's NPP's liquid, boron-containing waste with a complex composition, being generated during the operation of NPPs, including of ones VVER-type, and can be used to isolate boric and nitric acids and hydroxides of sodium and potassium for their reuse in the NPP process cycle. The invention allows to obtain crystalline boric acid and highly concentrated solutions of nitric acid and hydroxides of sodium and potassium, suitable for reuse in the NPP process cycle and for general industrial use. Conducting electrodialysis at low values of current and voltage provides a reduction of the method's energy intensity. The involvement of all major components of waste mother liquors into the processing reduces the amount of stored and disposed hazardous waste.