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.

IPC Classes  ?

• E02D 27/26 - Compacting soil locally before forming foundations; Construction of foundation structures by forcing binding substances into gravel fillings
• G01N 33/24 - Earth materials

Abstract

The invention relates to electrical engineering and nanotechnology and can be used in the manufacture of a wide range of electrical products. The claimed method solves the technical problem of creating a flexible piezomaterial using conductive layers of graphene particles and silver nanorods to form electrodes. The technical result is the production of a piezomaterial with reduced electrical resistance, which contains carbon nanostructures. The technical result is a consequence of using a technique to produce said piezomaterial which consists in: obtaining a hybrid graphene-silver suspension and applying same to the surface of a piezomaterial, the surface of which has been pretreated by plasma processing and has a surface structure formed by photolithography or by another method. The suspension is applied using the Langmuir-Blodgett technique. The resulting structure is subjected to a drying process carried out in a drying oven at a temperature of 40-45°С for 30 minutes. The claimed piezomaterial has a transmittance of at least 65% in the optical range.

IPC Classes  ?

• H01L 41/00 - SEMICONDUCTOR DEVICES; ELECTRIC SOLID STATE DEVICES NOT OTHERWISE PROVIDED FOR - Details thereof
• C01B 32/15 - Nanosized carbon materials
• B82Y 40/00 - Manufacture or treatment of nanostructures

Abstract

The invention relates to a method for producing highly porous open-cell carbon material. A blank of polyurethane foam impregnated with synthetic thermosetting resin is heated to 1000°C and held at that temperature in an inert atmosphere, and the carbonized blank is saturated with pyrocarbon from the gas phase. Impregnation with synthetic thermosetting resin is carried out under the action of ultrasound for not less than 30 minutes, followed by convective drying at a temperature of not more than 80°C for 5-30 minutes. Heat treatment is performed with a constant heating rate of 3-4°C/min, with an isothermic hold time of not more than 30 minutes. Saturation with pyrocarbon is carried out at a temperature of not less than 950°C in a methane atmosphere until the increase in mass reaches not less than 150% of the mass of the blank.

IPC Classes  ?

• C01B 32/00 - Carbon; Compounds thereof
• C08G 8/00 - Condensation polymers of aldehydes or ketones with phenols only
• C04B 35/52 - Shaped ceramic products characterised by their composition; Ceramic compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on non-oxides based on carbon, e.g. graphite

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.

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 15/18 - Emergency cooling arrangements; Removing shut-down heat
• G21C 17/112 - Measuring temperature
• G21C 19/04 - Means for controlling flow of coolant over objects being handled; Means for controlling flow of coolant through channel being serviced
• G21C 17/00 - Monitoring; Testing
• G21C 9/00 - Emergency protection arrangements structurally associated with the reactor
• G21C 19/313 - Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids for molten metals using cold traps

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. Multiple pin connections ensure fixation of the adjacent metal elements without any failure to electrical insulation of each other.

IPC Classes  ?

• F16L 9/14 - Compound tubes, i.e. made of materials not wholly covered by any one of the preceding groups
• F16L 59/10 - Bandages or covers for the protection of the insulation, e.g. against the influence of the environment or against mechanical damage
• F16L 59/14 - Arrangements for the insulation of pipes or pipe systems
• G01M 3/18 - Investigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using electric detection means for valves

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.

IPC Classes  ?

• G21C 15/18 - Emergency cooling arrangements; Removing shut-down heat
• G21C 15/24 - Promoting flow of the coolant
• G21C 15/253 - Promoting flow of the coolant for gases, e.g. blowers
• G21D 3/04 - Safety arrangements

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.

IPC Classes  ?

• G21C 15/257 - Promoting flow of the coolant using heat-pipes
• G21C 1/12 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor
• G21C 5/02 - Moderator or core structure; Selection of materials for use as moderator - Details
• G21C 3/40 - Structural combination of fuel element with thermoelectric element for direct production of electric energy from fission heat
• G21C 5/12 - Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator

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.

IPC Classes  ?

• G21F 9/00 - Treating radioactively contaminated material; Decontamination arrangements therefor
• G21F 9/32 - Processing by incineration
• G21F 9/02 - Treating gases
• G21F 9/34 - Disposal of solid waste
• G21F 9/12 - Processing by ion-exchange

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.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

Decontamination method for a nuclear reactor design component, comprising treating the nuclear reactor design component with a low-temperature plasma under the flow of reactionless gas. A selected site on the surface of the design component is supplied to the electrode. Plasma discharge is ignited between the surface of the design component chosen as the cathode, and the electrode chosen as the anode. Operating parameters of the discharge effective to sputtering of the cathode are chosen. The cathode is sputtered. The electrode and a gas pipeline diverting inert gas from the discharge zone are cooled to a temperature sufficient for the precipitation of the sputtered atoms on the surface of the electrode and lines. After sputtering the cathode to the specified depth, the electrode is moved to a new area of treatment and the process steps are repeated until the complete treatment of the entire surface of the design component.

IPC Classes  ?

• G21F 9/00 - Treating radioactively contaminated material; Decontamination arrangements therefor
• G21F 9/30 - Processing

Abstract

Device for deactivating radioactive elements comprising a loading-unloading manipulator, a process chamber with a lid with a round turn-around table located inside, a waste disposal container and an exhaust ventilation unit. The process chamber is equipped with a remote handling unit mounted on its outer part, a device for a dust-free abrasive blast cleaning, a waterjet cutting unit, connected through a leak-tight installed hoses in the process chamber walls, an abrasive and slurry collection unit and at least one device for radiation control, located inside the process chamber, the solid and liquid waste separation unit and discharge liquid waste. The process chamber is equipped with a chemical-radiation-shock proof sound-absorbing coating, and the remote control unit is connected with the device for a dust-free abrasive blast cleaning, waterjet cutting unit, abrasive and slurry collection device, exhaust ventilation unit, the process chamber lid, the radiation unit and the waste separation unit.

IPC Classes  ?

• G21F 9/00 - Treating radioactively contaminated material; Decontamination arrangements therefor
• G21F 9/30 - Processing
• B24C 3/32 - Abrasive blasting machines or devices; Plants designed for abrasive blasting of particular work, e.g. the internal surfaces of cylinder blocks
• B24C 9/00 - Appurtenances of abrasive blasting machines or devices, e.g. working chambers, arrangements for handling used abrasive material

Abstract

A method of fragmentation of elements of a nuclear reactor includes placement of elements inside a cask and subsequent cutting, the cask being perforated. Each element is lowered into the cask by a full internal height of the cask using a gripper having clamping jaws. The element is intercepted at an upper edge of the cask, lifted, and positioned using video surveillance and artificial lighting so that a hydraulic cutter is directly under the clamping jaws. The element is cut at a point corresponding to a level of the upper edge of the cask, separating from the element a fragment equal to the internal height of the cask. Then the upper part of the element remaining after cutting is lowered inside the cask by the full internal height of the cask and the cutting of the element into fragments is repeated until the element is fully cut to fragments.

IPC Classes  ?

• G21C 19/36 - Mechanical means only
• G21D 1/00 - NUCLEAR POWER PLANT - Details of nuclear power plant

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. The plant is equipped with a decontamination solution preparation module connected with a pipe for decontamination solution supply and discharge, at least one pump, while the module for decontamination solution receiving is equipped with devices for cleaning and pH correction of decontamination solution, and the unit for electrochemical decontamination of metal radioactive waste, the module for decontamination solution receiving and the decontamination solution preparation module are equipped with pH measurement elements.

IPC Classes  ?

• G21F 9/00 - Treating radioactively contaminated material; Decontamination arrangements therefor
• G21F 9/34 - Disposal of solid waste

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.

IPC Classes  ?

• G21C 15/257 - Promoting flow of the coolant using heat-pipes
• G21C 1/12 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor
• G21C 5/02 - Moderator or core structure; Selection of materials for use as moderator - Details
• G21C 3/322 - Means to influence the coolant flow through or around the bundles
• G21C 3/40 - Structural combination of fuel element with thermoelectric element for direct production of electric energy from fission heat
• G21C 5/12 - Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator

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.

IPC Classes  ?

• G21D 3/00 - Control of nuclear power plant
• G01N 17/02 - Electrochemical measuring systems for weathering, corrosion or corrosion-protection measurement
• G21C 17/022 - Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
• G21D 3/04 - Safety arrangements
• G21D 3/10 - Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure

Abstract

The proposed invention relates to the field of additive techniques for use in manufacturing implants, preferably from titanium alloys. A cellular structure for implants is configured in the form of a three-dimensional lattice having an arrangement of nodes on the surface of three-dimensional figures that are connected by struts. The cellular structure is characterized in that said three-dimensional figures are hollow cylinders having a wall thickness, and the struts are regions of contact between said hollow cylinders, along the outer surface thereof, the hollow cylinders being arranged in rows, wherein in two adjacent rows, the axes of the hollow cylinders are orthogonal to each other. The regions of contact are points of contact or extend across the thickness of a wall of the hollow cylinders or across a part of the thickness of the walls of the hollow cylinders. The axes of the hollow cylinders arranged in one row coincide with the axes of the cylinders of a similar next-but-one row. The axes of the hollow cylinders arranged in one row can be offset from the axes of the cylinders of a similar next-but-one row by half the distance between the hollow cylinders. The cellular structure is made of titanium or a titanium alloy. The technical result of the proposed design of a cellular structure for medical implants is an improvement in elastic behaviour.

IPC Classes  ?

• A61L 27/56 - Porous or cellular materials

Abstract

A condensation system for recuperating energy discharge of a nuclear power plant comprises a nuclear power unit, a compressor, a condenser, a water chamber equipped with a sprinkler, an electrical current generator, a pure water pump station, a cooling water pump station, a secondary condensate pool and a turboexpander. The compressor is connected to the condenser, which is connected to the turboexpander, which is supplied with the electric current generator and is connected to the water chamber, which is connected to the secondary condensate pool, which is connected to the pure water pump station, the condenser being connected to the cooling water pump station, wherein the compressor is connected by a pressure air duct to a wastewater channel, which is connected to the nuclear power unit and is equipped with a sealing cover.

IPC Classes  ?

• G21D 1/02 - Arrangements of auxiliary equipment
• G21D 1/04 - Pumping arrangements
• E03B 3/28 - Methods or installations for obtaining or collecting drinking water or tap water from humid air

Abstract

The proposed invention relates to the field of additive techniques for use in manufacturing implants, preferably from titanium alloys. A cellular structure for implants is configured in the form of a three-dimensional lattice having an arrangement of nodes on the surface of solid figures connected by struts. The invention is characterized in that a solid figure is a hollow sphere having a wall delimited by an outer spherical surface and an inner spherical surface; a first and a second through-opening are configured in a first diametral section of the sphere, said through-openings having a first common axis; a third and a fourth through-opening are configured in a plane orthogonal to said axis and at an angle of 45º to the first diametral section, said through-openings having a second common axis; a fifth and a sixth opening are configured in the same plane, said openings having a third common axis orthogonal to the second common axis, wherein the openings form main through-channels, and eight nodes are arranged on the surface of the hollow sphere symmetrically relative to the centre thereof. Additional cells are configured in the nodes, said cells communicating with one another by additional channels. The technical result of the proposed design of a cellular structure for medical implants is an improvement in elastic behaviour.

IPC Classes  ?

• A61L 27/56 - Porous or cellular materials

Abstract

The invention relates to medicine, and more particularly to surgical dentistry and maxillofacial surgery, and can be used in the reconstruction of mandibular defects. An endoprosthesis is prepared from titanium and an alloy thereof in the form of a three-dimensional porous body which conforms to the geometry of the defect that is to be reconstructed. A mandibular resection is carried out with the disarticulation of the temporomandibular joint. Next, an incision is made in the projection of the pectoralis major, the soft tissue flap of which is separated and drawn aside. In the muscle flap, transverse to the path of the fibres thereof, a surgical pocket is created, into which the endoprosthesis is placed. After movement within the muscle flap and rotation, the endoprosthesis is positioned with one end in the region of the articular surface of the temporomandibular joint and the other end lying along the line of the osteotomy in alignment with the remaining fragment of the lower jaw, and fixation is provided by means of bone suturing. The method allows: single-stage restoration of anatomical and aesthetic balance to the facial contours; reconstruction in the case of insufficient soft tissues to cover the endoprosthesis; complete preservation of the masticatory function of the mandible; a reduction in treatment duration and post-operative recovery time.

IPC Classes  ?

• A61B 17/00 - Surgical instruments, devices or methods, e.g. tourniquets
• A61F 2/28 - Bones
• A61F 2/30 - Joints

Abstract

The invention relates to medicine, and more particularly to maxillofacial surgery, and can be used in the manufacture of implants for the combined surgical and orthopaedic rehabilitation of patients with facial bone defects. The aim and the technical result of the invention are the creation of a standard implant design for use in mandibular prosthetic reconstruction, which provides for tailored alignment with the region of the skull undergoing reconstruction and provides for the necessary elastic properties of the implant, namely a porous structure with an elasticity modulus of 1-5 hPa and a compressive strength of 50 kg/cm2. The technical result is achieved in that an implant for mandibular prosthetic reconstruction comprises a plate which is made of titanium or an alloy thereof and is provided with fastening elements having through-openings for the passage of fastening screws, wherein the plate is provided at one end with an element having a three-dimensional continuous structure which conforms to the shape of the condyloid process, the plate itself has a three-dimensional porous structure having the shape of the body of the mandible, and the plate is provided at the other end with an osseointegration element having a three-dimensional porous structure, and also with two fastening elements in the form of narrow perforated plates, wherein the cells of the porous structure are in the form of a tetrahedron, dodecahedron or an octahedron and are provided with a plurality of spacers having a circular and/or rectangular cross section.

IPC Classes  ?

• A61F 2/28 - Bones
• A61F 2/30 - Joints

Abstract

The invention relates to nuclear engineering. A method for decontaminating a structural element of a nuclear reactor involves treating a structural element of a nuclear reactor with low-temperature plasma while supplying a stream of a chemically inert gas. An electrode is applied to a selected area on a surface of the structural element, a plasma discharge is ignited between the surface of the structural element functioning as a cathode and an electrode functioning as an anode, and working parameters of the discharge are selected which are effective for sputtering the surface of the cathode. The cathode is sputtered. The electrode and a gas pipeline for removing the chemically inert gas from the discharge zone are cooled to a temperature sufficient for the sputtered atoms to be deposited on the surfaces of the electrode and the pipeline. Once the surface of the cathode has been sputtered to a given depth, the electrode is moved to a newly selected treatment area and the operations of the method are repeated until the entire surface of the structural element to be decontaminated has been fully treated. The invention makes it possible to reduce significantly the radioactivity of the power plant structures treated and to reduce the amount of radioactive waste produced.

IPC Classes  ?

• G21F 9/28 - Treating solids

Abstract

The invention relates to nuclear engineering. A method for decontaminating a structural element of a nuclear reactor involves treating a structural element of a nuclear reactor with low-temperature plasma while supplying a stream of a chemically inert gas. An electrode is applied to a selected area on a surface of the structural element, a plasma discharge is ignited between the surface of the structural element functioning as a cathode and an electrode functioning as an anode, and working parameters of the discharge are selected which are effective for sputtering the surface of the cathode. The cathode is sputtered. The electrode and a gas pipeline for removing the chemically inert gas from the discharge zone are cooled to a temperature sufficient for the sputtered atoms to be deposited on the surfaces of the electrode and the pipeline. Once the surface of the cathode has been sputtered to a given depth, the electrode is moved to a newly selected treatment area and the operations of the method are repeated until the entire surface of the structural element to be decontaminated has been fully treated. The invention makes it possible to reduce significantly the radioactivity of the power plant structures treated and to reduce the amount of radioactive waste produced.

IPC Classes  ?

• G21F 9/28 - Treating solids

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.

IPC Classes  ?

• A62C 5/02 - Making of fire-extinguishing materials immediately before use of foam
• A62C 27/00 - Fire-fighting land vehicles
• A62C 37/36 - Control of fire-fighting equipment an actuating signal being generated by a sensor separate from an outlet device
• B60L 1/00 - Supplying electric power to auxiliary equipment of electrically-propelled vehicles

Abstract

The invention relates to devices for ridding radioactive waste of radioactive contamination. A device for deactivating radioactive elements comprises a loading and unloading manipulator, a working chamber with a roof, a rotary table arranged inside said chamber, a container for collecting waste and an exhaust ventilation device. The working chamber is equipped with a remote control unit, a device for dust-free abrasive blast-cleaning, an abrasive water jet cutter, which is connected to a device for collecting abrasive and cuttings by means of hoses hermetically mounted in the walls of the working chamber, a radiation monitoring device, which is arranged inside the working chamber, a device for separating liquid and solid waste, and a liquid waste drain, an abrasive water jet cutter, a device for collecting abrasive and cuttings, an exhaust ventilation system, a roof of the working chamber, a radiation monitoring device and a device for separating liquid and solid waste. The working chamber is equipped with an impact-resistant, soundproof cover which is resistant to chemicals and radiation. The remote control unit is connected to the device for dust-free abrasive blast-cleaning. The invention makes it possible to reduce the amount of waste and also to minimize hazards and radiation exposure.

IPC Classes  ?

• G21F 9/28 - Treating solids
• G21F 9/30 - Processing

Abstract

The invention relates to devices for ridding radioactive waste of radioactive contamination. A device for deactivating radioactive elements comprises a loading and unloading manipulator, a working chamber with a roof, a rotary table arranged inside said chamber, a container for collecting waste and an exhaust ventilation device. The working chamber is equipped with a remote control unit, a device for dust-free abrasive blast-cleaning, an abrasive water jet cutter, which is connected to a device for collecting abrasive and cuttings by means of hoses hermetically mounted in the walls of the working chamber, a radiation monitoring device, which is arranged inside the working chamber, a device for separating liquid and solid waste, and a liquid waste drain, an abrasive water jet cutter, a device for collecting abrasive and cuttings, an exhaust ventilation system, a roof of the working chamber, a radiation monitoring device and a device for separating liquid and solid waste. The working chamber is equipped with an impact-resistant, soundproof cover which is resistant to chemicals and radiation. The remote control unit is connected to the device for dust-free abrasive blast-cleaning. The invention makes it possible to reduce the amount of waste and also to minimize hazards and radiation exposure.

IPC Classes  ?

• G21F 9/28 - Treating solids
• G21F 9/30 - Processing

Abstract

A nuclear reactor core relates to the field of atomic energy. A nuclear reactor core comprises at least one module, a solid neutron moderator (4) and a liquid neutron moderator. The module comprises a housing (1), at least one heat pipe, at least one fuel element and thermal insulation (5). The heat pipe is in the form of a casing (2) having a wick (6), and comprises a reactor coolant. The fuel element is made from nuclear fuel (8) arranged in the evaporation zone of the heat pipe around its casing (2) and in thermal contact therewith, and is enclosed in a shell (3). Low-melting metals with a high boiling point, for example lithium, calcium, lead and silver, are used as the heat pipe coolant. The thermal insulation (5) is placed between the shell (3) and the module housing (1). The solid neutron moderator (4) has at least one opening in which at least one module is arranged. The space between the housing (1) and the solid neutron moderator (4) is filled with the liquid neutron moderator. The technical result is to increase the efficiency of reactor plants and to broaden the field of use of a reactor core.

IPC Classes  ?

• G21C 1/12 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor

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.

IPC Classes  ?

• G21C 3/62 - Ceramic fuel
• G21C 3/04 - Constructional details

Abstract

The reactor core belongs to the field of nuclear power engineering. The reactor core includes at least one module, solid (4) and liquid neutron moderators. The module contains a casing (1), at least one heat pipe, one fuel element and thermal insulation (5). The heat pipe is made in the shape of a casing (2) with a wick (6), and contains a coolant. The fuel element is made of nuclear fuel (8), arranged in the evaporation area of the heat pipe around its casing (2) in thermal contact with it, and enclosed in a can (3). Low-melting metals with a high boiling point, for example, lithium, calcium, lead, silver are used as the coolant of the heat pipe. Thermal insulation (5) is arranged between the can (3) and the casing (1) of the module. At least one hole is made in the solid neutron moderator (4), in which at least one module is arranged. The space between the casing (1) of the module and the solid neutron moderator (4) is filled with a liquid neutron moderator. The technical result is an increase in the efficiency of reactor plants and the expansion of the scope of the core.

IPC Classes  ?

• G21C 1/14 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor

Abstract

There is disclosed herein methods of treatment of spent ion-exchange resins for disposal, and devices for implementation of the same. The disclosed methods comprise feeding a mixture of spent ion-exchange resins with transport water to a loading tank, separating ion- exchange resins from transport water by settling the mixture thereof and draining the transport water from the loading tank. The subsequent metered feed of ion-exchange resins separated from the transport water into the drying chamber, vacuum drying with simultaneous mixing of the ion-exchange resins is in the drying chamber at a temperature not exceeding 90 C and unloading the treated ion-exchange resin into a transport container.

IPC Classes  ?

• B01J 49/00 - Regeneration or reactivation of ion-exchangers; Apparatus therefor

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.

IPC Classes  ?

• H01G 11/36 - Nanostructures, e.g. nanofibres, nanotubes or fullerenes
• H01G 11/30 - Electrodes characterised by their material
• H01G 11/52 - Separators
• H01G 11/62 - Liquid electrolytes characterised by the solute, e.g. salts, anions or cations therein
• H01G 11/74 - Terminals, e.g. extensions of current collectors
• H01G 11/78 - Cases; Housings; Encapsulations; Mountings
• H01G 11/86 - Processes for the manufacture of hybrid or EDL capacitors, or components thereof specially adapted for electrodes

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.

IPC Classes  ?

• B01D 61/44 - Ion-selective electrodialysis
• C01B 35/10 - Compounds containing boron and oxygen
• C01D 1/20 - Preparation by reacting oxides or hydroxides with alkali metal salts
• G21F 9/12 - Processing by ion-exchange

Abstract

The proposed subject matter relates to the field of creating implant structures, preferably from titanium alloys, which can be made using additive techniques. The present augment for implantation is configured as a rectangular prism bounded by faces and edges, and having an internal structure in the form of a space lattice having points positioned in the vertices of elementary geometric shapes. Along the edges of the rectangular prism which connect the faces of said rectangular prism are zones of a continuous material. The zones of a continuous material are in the shape of rods having a square cross section. The augment for implantation is made of titanium or a titanium alloy.

IPC Classes  ?

• A61F 2/28 - Bones

Abstract

A method of processing spent ion-exchange resins for burial includes delivering a mixture of spent ion-exchange resins with transport water to a loading tank, separating the ion-exchange resins from the transport water by means of settling of the mixture and draining of the transport water from the loading tank, subsequent metered delivery of the ion-exchange resins separated from the transport water to a drying chamber, vacuum drying with simultaneous mixing of the ion-exchange resins in the drying chamber at a temperature of no more than 90°C and unloading the spent ion-exchange resin to the transport container. The ion-exchange resins after completion of vacuum drying in the drying chamber undergo additional heat treatment in a high-temperature furnace at a temperature of 250-300°C with simultaneous mixing and vacuum drying. The spent ion-exchange resin is unloaded into the transport container after heat treatment in the high-temperature furnace.

IPC Classes  ?

• G21F 9/16 - Processing by fixation in stable solid media

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.

IPC Classes  ?

• G05B 19/418 - Total factory control, i.e. centrally controlling a plurality of machines, e.g. direct or distributed numerical control (DNC), flexible manufacturing systems (FMS), integrated manufacturing systems (IMS), computer integrated manufacturing (CIM)
• G06F 16/93 - Document management systems
• G06F 16/9032 - Query formulation

Abstract

The invention relates to the field of nuclear technology. A method for dividing long elements of a nuclear reactor into fragments comprises placing the long elements inside a container and subsequently cutting said long elements. A long element is lowered into the container over the entire height thereof. The long element is cut level with the upper edge of the container, with a fragment equal to the height of the container being separated from said long element. The upper part of the long element that remains after cutting is again lowered inside the container over the entire height thereof and cutting of the long element into fragments is repeated until the long element is completely divided. There is also a device for dividing long elements of a nuclear reactor into fragments. The invention makes it possible to reduce the laboriousness of and timeframes involved in carrying out work to divide long elements, and also to minimize the exposure of service personnel radiation.

IPC Classes  ?

• G21F 9/28 - Treating solids
• B26D 5/00 - Arrangements for operating and controlling machines or devices for cutting, cutting-out, stamping-out, punching, perforating, or severing by means other than cutting

Abstract

The invention relates to the field of nuclear technology. A method for dividing long elements of a nuclear reactor into fragments comprises placing the long elements inside a container and subsequently cutting said long elements. A long element is lowered into the container over the entire height thereof. The long element is cut level with the upper edge of the container, with a fragment equal to the height of the container being separated from said long element. The upper part of the long element that remains after cutting is again lowered inside the container over the entire height thereof and cutting of the long element into fragments is repeated until the long element is completely divided. There is also a device for dividing long elements of a nuclear reactor into fragments. The invention makes it possible to reduce the laboriousness of and timeframes involved in carrying out work to divide long elements, and also to minimize the exposure of service personnel radiation.

IPC Classes  ?

• G21F 9/28 - Treating solids
• B26D 5/00 - Arrangements for operating and controlling machines or devices for cutting, cutting-out, stamping-out, punching, perforating, or severing by means other than cutting

Abstract

The invention relates to devices for ridding radioactive waste of radioactive contamination. An assembly for the electrochemical decontamination of metallic radioactive waste includes a pipeline equipped with a shutoff valve, and a metallic radioactive waste treatment module comprising a unit for the electrochemical decontamination of metallic radioactive waste which is connected by a ventilation channel to a ventilation module and by a decontaminating solution supply and discharge pipeline equipped with a shutoff valve to a module for receiving decontaminating solution. The installation is equipped with a module for preparing decontaminating solution connected by the decontaminating solution supply and discharge pipeline, which is equipped with at least one pump, to the unit for the electrochemical decontamination of metallic radioactive waste and to the module for receiving decontaminating solution. The module for receiving decontaminating solution is provided with purification and pH correction devices for the decontaminating solution, and the unit for the electrochemical decontamination of metallic radioactive waste, the module for receiving decontaminating solution and the module for preparing decontaminating solution are equipped with elements for measuring the pH level. The invention makes it possible to provide adaptive reprocessing of decontaminating solution for repeat use.

IPC Classes  ?

• G21F 9/34 - Disposal of solid waste

Abstract

The invention relates to devices for ridding radioactive waste of radioactive contamination. An assembly for the electrochemical decontamination of metallic radioactive waste includes a pipeline equipped with a shutoff valve, and a metallic radioactive waste treatment module comprising a unit for the electrochemical decontamination of metallic radioactive waste which is connected by a ventilation channel to a ventilation module and by a decontaminating solution supply and discharge pipeline equipped with a shutoff valve to a module for receiving decontaminating solution. The installation is equipped with a module for preparing decontaminating solution connected by the decontaminating solution supply and discharge pipeline, which is equipped with at least one pump, to the unit for the electrochemical decontamination of metallic radioactive waste and to the module for receiving decontaminating solution. The module for receiving decontaminating solution is provided with purification and pH correction devices for the decontaminating solution, and the unit for the electrochemical decontamination of metallic radioactive waste, the module for receiving decontaminating solution and the module for preparing decontaminating solution are equipped with elements for measuring the pH level. The invention makes it possible to provide adaptive reprocessing of decontaminating solution for repeat use.

IPC Classes  ?

• G21F 9/34 - Disposal of solid waste

Abstract

A nuclear reactor core relates to the field of atomic power. A nuclear reactor core comprises at least one module, a solid neutron moderator (5) and a liquid neutron moderator. The module comprises a housing (2), at least one heat pipe, at least one fuel element, a casing (1) and thermal insulation (6). The heat pipe is formed from a housing (3) and a wick (7), and contains an evaporating coolant. The fuel element consists of a shell (4) and nuclear fuel (9). An evaporation zone of the heat pipe and the fuel elements are enclosed in the casing (1) which is filled with a liquid coolant. Liquid metals having a high boiling point, for example lithium, calcium, lead and silver, are used as the heat pipe coolant and the liquid coolant in the casing (1). The thermal insulation (6) is placed in a space between the casing (1) and the module housing (2). The solid neutron moderator (5) has at least one opening in which at least one module is arranged. A space between the solid neutron moderator (5) and the module is filled with the liquid neutron moderator. The technical result is an increase in the efficiency of reactor plants and an extension of the field of use of a core.

IPC Classes  ?

• G21C 1/12 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor

Abstract

A nuclear reactor core relates to the field of atomic power. A nuclear reactor core comprises at least one module, a solid neutron moderator (5) and a liquid neutron moderator. The module comprises a housing (2), at least one heat pipe, at least one fuel element, a casing (1) and thermal insulation (6). The heat pipe is formed from a housing (3) and a wick (7), and contains an evaporating coolant. The fuel element consists of a shell (4) and nuclear fuel (9). An evaporation zone of the heat pipe and the fuel elements are enclosed in the casing (1) which is filled with a liquid coolant. Liquid metals having a high boiling point, for example lithium, calcium, lead and silver, are used as the heat pipe coolant and the liquid coolant in the casing (1). The thermal insulation (6) is placed in a space between the casing (1) and the module housing (2). The solid neutron moderator (5) has at least one opening in which at least one module is arranged. A space between the solid neutron moderator (5) and the module is filled with the liquid neutron moderator. The technical result is an increase in the efficiency of reactor plants and an extension of the field of use of a core.

IPC Classes  ?

• G21C 1/12 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor

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.

IPC Classes  ?

• G21C 9/004 - Pressure suppression
• G21C 13/10 - Means for preventing contamination in event of leakage
• G21C 13/028 - Seals, e.g. for pressure vessels or containment vessels

Abstract

The invention relates to compact mobile robotic fire-extinguishing systems for monitoring emergency situations and carrying out disaster response operations in a hazard zone under particularly dangerous conditions and/or in inaccessible locations. A compact mobile robotic fire-extinguishing system allows fire extinguishants to be delivered at a rate of from 15 to 20 l/s. The present compact mobile robotic fire-extinguishing system comprises a tracked chassis, a body mounted on said chassis, a control unit and a drive part with a rechargeable battery, which are mounted inside the body, a fire extinguishant delivery element mounted on the body such as to be remotely controllable, a video surveillance system, and also a connecting pipe, the outlet of which is connected to the inlet of the fire extinguishant delivery element. The connecting pipe is mounted inside the body with its central axis situated in the vertical plane of symmetry of the body; the axis of the inlet of the connecting pipe is situated lower than the axis of the outlet of the fire extinguishant delivery element by a distance of at least half of the height of the compact mobile robotic fire-extinguishing system, and the outlet of the connecting pipe is situated in the centre of the top surface of the body.

IPC Classes  ?

• A62C 27/00 - Fire-fighting land vehicles
• A62C 31/03 - Nozzles specially adapted for fire-extinguishing adjustable, e.g. from spray to jet or vice-versa
• A62C 37/00 - Control of fire-fighting equipment

Abstract

The proposed invention relates to the field of additive technologies used for the manufacture of implants, preferably made of titanium alloys. A porous structure for medical implants comprises a set of spheres connected to one another along the interfaces, and is characterized in that each sphere has a cavity which is not connected to the atmosphere. The cavities are spherical. The centres of the spheres and the centres of the cavities coincide. The porous structure is made of titanium or a titanium alloy. The technical effect of the proposed design of the porous structure for medical implants is to improve the elastic characteristics of implants on account of the possibility of further optimizing porosity.

IPC Classes  ?

• A61L 27/56 - Porous or cellular materials
• A61L 27/06 - Titanium or titanium alloys
• A61F 2/28 - Bones
• A61F 2/30 - Joints

Abstract

The proposed invention relates to the field of medicine, and more particularly to orthopaedic surgery and traumatology, and can be used for repairing trabecular bone defects in the epi-metaphyseal region. Proposed is an implant for repairing trabecular bone defects which is configured in the shape of a solid of revolution. The implant is characterized in that the solid of revolution is made of a porous material and is bounded by the surface of an ellipsoid. The porous material is porous titanium or a titanium alloy. The dimensions of the ellipsoid along three orthogonal axes are in a range of 5-30 mm. The dimensions of the ellipsoid are: 5-10 mm along one of the orthogonal axes, 10-20 mm along the second orthogonal axis, and 20-30 mm along the third orthogonal axis. The technical result is the improved adaptability of the shape of the implant to the dimensional characteristics of a specific bone defect. Since the implant is made of a metal material, it has improved X-ray visibility. Producing the implant from a porous material enhances the osteoconductive effect.

IPC Classes  ?

• A61F 2/28 - Bones

Abstract

The invention relates to medicine, in particular to traumatology and orthopaedics. An implant for an osteotomy is made of metal or alloy and has the shape of a prism having a base in the form of a right-angled triangle comprising a long leg, a short leg and a hypotenuse. The invention is characterized in that the prism comprises a set of main channels creating porosity, wherein the channels are elongated in a direction perpendicular to the long leg and/or hypotenuse. The prism comprises a set of additional channels perpendicular to the main channels. The intervals between the channels are formed by a sintered metallic powder. The sintered metallic powder is a sintered powder of titanium or a titanium alloy. The technical result of the proposed design of a porous structure for medical implants is to improve the elastic characteristics of implants on account of the possibility of further improving porosity.

IPC Classes  ?

• A61F 2/28 - Bones

Abstract

The invention relates to nuclear power engineering. A unit for reprocessing radioactive waste comprises a waste loading assembly, a plasma shaft furnace, a device for feeding air into the furnace and a pyrogas combustion chamber, an evaporative heat exchanger, a gas purification system comprising a bag filter, a heat-exchanger device and a scrubber, pumps and containers for reagents and reprocessing products, and fittings. The unit is equipped with at least one control module and a monitoring module of a slag drainage assembly, said monitoring module being electrically connected to said control module, a module for monitoring the state of the internal environment, a module for the state of equipment, and at least one gas-analyser module, a plasma shaft furnace, a cell for receiving slag melt, and electrical equipment of the device for feeding air into the furnace and into the pyrogas combustion chamber. The control module is electrically connected to the electrical equipment of the waste loading assembly. The monitoring module of the slag drainage assembly is electrically connected to the electrical equipment of the slag drainage assembly. The invention makes it possible to provide an adaptive operating mode of the unit in which radioactive waste of varying radioactive levels is reprocessed in automatic mode.

IPC Classes  ?

• G21F 9/32 - Processing by incineration

Abstract

The invention relates to emergency protection of nuclear power plants, particularly to technologies for mitigation of consequences or fire prevention and prevention of explosive gas accumulation, which ensure hydrogen explosion safety in premises of the containment dome (hereinafter - CNT) at nuclear power plants (hereinafter - NPP) with water-cooled power reactor (hereinafter - VVER). Moreover, the offered invention can be used at other facilities having the risk of development of potentially hazardous emergency processes, related to the emission of a large amount of light combustible gas and its localization in closed premises of a facility. The technical result attained by the declared invention consists in the reduction of the risk of gas medium inflammation in premises of NPP CNT, as well as in the provision of self-damping of weak burning waves, reduction of their intensity in case of gas medium inflammation in premises of NPP CNT and in reduction of dynamic loads on walls of premises of NPP CNT. The specified technical result is attained due to the fact that in the method for ensuring hydrogen explosion safety at nuclear power plants, comprising ventilation of premises of the nuclear reactor premises and hydrogen recombination in premises of the nuclear reactor premises by its catalytic oxidation, in accordance with the declared solution, a reflector (2, 3) is placed on the way of potentially emergency propagation of a pressure hydrogen-containing steam-gas jet, apertures are made in the walls between premises of the nuclear reactor containment dome with a size equal to minimum 35% of the surface area of the said walls, while excess heat is withdrawn in areas of potential localization of hydrogen-containing steam-gas mixture burning sources.

IPC Classes  ?

• G21C 9/06 - Means for preventing accumulation of explosives gases, e.g. recombiners
• G21C 13/02 - Pressure vessels; Containment vessels; Containment in general - Details
• G21C 19/317 - Recombination devices for radiolytic dissociation products

Abstract

ABSTRACT There is disclosed herein a radioactive waste recycling plant including a waste feed unit, a plasma shaft- type furnace with a melter in a hearth of the furnace and a slug discharge unit connected with a receiving tank for molten slug; an air supply unit; an evaporative heat exchanger; a gas purification unit; a heat- exchanger and a scrubber; pumps and tanks for agents and recycled products; fittings; one control module; an interior environment control module; an equipment status control module; and, a gas analytical module; the control module is electrically connected to a waste feed unit, a plasma shaft-type furnace, a receiving tank and the air supply unit which delivers the air to the furnace and to the combustion chamber. 14 Date Recue/Date Received 2020-09-22

IPC Classes  ?

• G21F 9/32 - Processing by incineration

Abstract

The proposed invention relates to the field of additive technologies, used for the manufacture of implants, preferably from titanium alloys. A method for processing porous metal-based implants includes preparing a model of cellular structures, and manufacturing a cellular structure by using a source of energy to act upon a fusible material. The method is characterised in that following manufacture of the cellular structure, the structure is submerged in a liquid medium, cooled to a temperature below the phase transition temperature at which the medium transitions from a liquid state to a solid state, and subjected to plastic deformation, after which the structure is heated to the phase transition temperature at which the medium transitions from a solid state to a liquid state, and the liquid medium is removed. Water, or molten salts having a transition temperature from solid to liquid state not exceeding the recrystallisation temperature of the metal material, or a molten metal or a molten alloy, are used as the liquid medium. The technical result consists of enhancing the strength characteristics of an implant.

IPC Classes  ?

• A61L 27/56 - Porous or cellular materials
• B22F 3/26 - Impregnating
• C22C 1/08 - Alloys with open or closed pores

Abstract

Corrosion rate control of nuclear plant process circuits, whereby the electrochemical potential of structural material of heat exchanging tubes and specific electrical conductivity of blowdown water in steam generators are measured, the polarization resistance of the structural material of pipelines of the condensate-feeding path and specific electrical conductivity of feed water in steam generators are measured, and these parameters are averaged and compared with rated values. The values are displayed on a two-parameter nomogram divided into areas A, B, D, and F which determine corrosion activity in relation to the material of the heat exchanging tubes, or on a two-parameter nomogram divided into areas G, Y, X, and Z which determine corrosion activity in relation to the material of pipelines in steam generators. Depending on location of the point in one of the areas, no actions are taken, coolant parameters are adjusted, or the power unit is shut down.

IPC Classes  ?

• G21D 1/00 - NUCLEAR POWER PLANT - Details of nuclear power plant
• F22B 37/00 - Component parts or details of steam boilers

Abstract

The invention relates to construction, and more particularly to stabilizing soils for bases and foundations of buildings and structures. A method for compacting bases laid using weak mineral soils includes drilling holes, feeding a packing material into each hole, and acting on the packing material with a working tool in order to form a compaction pile. First, a geotechnical survey is carried out with respect to the area of a base, and desired parameters are determined. A target modulus of deformation of the soil layer to be compacted is set. Comparative calculations of the results obtained are carried out. The placement interval of the compaction piles is set as equal to three diameters of a hollow tubular working tool, and the value of the actual mean effective modulus of deformation of the base is determined. The latter is compared with the target modulus of deformation of the mineral soil. Additional geotechnical surveys are carried out with respect to the area of the base. The actual mean effective modulus of deformation of the compacted base is calculated and compared with the target value. If the actual mean effective modulus of deformation of the base does not correspond to the target value, additional compaction piles are installed between the existing piles. The technical result is an increase in soil compacting efficiency, and a reduction in material and labour costs.

IPC Classes  ?

• E02D 27/26 - Compacting soil locally before forming foundations; Construction of foundation structures by forcing binding substances into gravel fillings

Abstract

There is disclosed herein methods for strengthening soils under bases and foundations of buildings and structures, including electric power industry facilities. The methods include compaction 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, proposes to perform preliminary geological engineering surveys of the base area and determine the values of the modulus of deformation.

IPC Classes  ?

• E02D 27/26 - Compacting soil locally before forming foundations; Construction of foundation structures by forcing binding substances into gravel fillings
• E02D 3/12 - Consolidating by placing solidifying or pore-filling substances in the soil

Abstract

A disposable emergency thermal valve comprises a body having a through channel for supplying coolant liquid through the inlet opening thereof in the direction of the outlet opening thereof, and a fuse arranged in the through channel of the body and consisting of at least two parts which fully cover the cross section of the through channel, are made of materials having different melting temperatures and which are arranged in the through channel successively with an increase in the melting temperature of each subsequent part in the direction from the inlet opening of the through channel to the outlet opening thereof, wherein the body can have transverse reinforcing ribs and/or transverse projections where the fuse is arranged.

IPC Classes  ?

• F16K 17/40 - Safety valves; Equalising valves with fracturing member, e.g. fracturing diaphragm, fusible joint

Abstract

Abstract There is disclosed herein a single-action emergency thermal valve comprising a body with a through channel for coolant supply through an inlet of the channel in the direction of an outlet of the channel, and a fuse link in the through channel of the body, the fuse link comprising at least two parts that completely overlap a section of the through channel, wherein the parts are made of materials with different melting points, and are located in the through channel in series in increasing order of the melting points of each of the parts in a direction from the through channel inlet to its outlet. Date Recue/Date Received 2020-12-17

IPC Classes  ?

• F16K 17/40 - Safety valves; Equalising valves with fracturing member, e.g. fracturing diaphragm, fusible joint
• F16K 17/00 - Safety valves; Equalising valves

Abstract

The invention relates to metallurgy and more particularly to nickel-based alloys intended for use in aggressive oxidising environments. The present nickel-based corrosion-resistant alloy contains: = 0.006 wt.% carbon, = 0.1 wt.% silicon, = 1.0 wt.% manganese, 22.8-24.0 wt.% chromium, = 0.75 wt.% iron, 12.0-14.0 wt.% molybdenum, 0.01-0.03 wt.% niobium, 0.01-0.06 wt.% titanium, 0.1-0.2 wt.% aluminium, 0.005-0.01 wt.% magnesium, = 0.015 wt.% phosphorus and < 0.012 wt.% sulphur, with the remainder being nickel and unavoidable impurities.

IPC Classes  ?

• C22C 19/05 - Alloys based on nickel or cobalt based on nickel with chromium

Abstract

The invention relates to metallurgy and more particularly to nickel-based alloys intended for use in aggressive oxidising environments. The present nickel-based corrosion-resistant alloy contains: ≤ 0.006 wt.% carbon, ≤ 0.1 wt.% silicon, ≤ 1.0 wt.% manganese, 22.8-24.0 wt.% chromium, ≤ 0.75 wt.% iron, 12.0-14.0 wt.% molybdenum, 0.01-0.03 wt.% niobium, 0.01-0.06 wt.% titanium, 0.1-0.2 wt.% aluminium, 0.005-0.01 wt.% magnesium, ≤ 0.015 wt.% phosphorus and < 0.012 wt.% sulphur, with the remainder being nickel and unavoidable impurities.

IPC Classes  ?

• C22C 19/05 - Alloys based on nickel or cobalt based on nickel with chromium

Abstract

A method for controlling the rate of corrosion of coolant loop equipment in nuclear power plants involves measuring the values of the electrochemical potential of the structural material of the heat transfer tubes and the electrical conductivity of the steam generator blowdown water, measuring the values of the polarization resistance of the structural material of the condensate and feedwater system tubes and the electrical conductivity of the steam generator feedwater, and automatically averaging said parameters and comparing them with reference values. The values of the electrochemical potential and the electrical conductivity of the steam generator blowdown water are depicted in the form of points on a two-parameter nomogram having the coordinates "electrochemical potential-electrical conductivity of an H-cationized sample" of blowdown water, which is divided into separate zones A, B, D and F characterizing the different degrees of corrosiveness of the steam generator blowdown water toward the material of the heat transfer tubes depending upon the operating mode. The values of the polarization resistance and the electrical conductivity of the steam generator feedwater are depicted in the form of points on a two-parameter nomogram having the coordinates "polarization resistance-electrical conductivity of an H-cationized sample" of feedwater, which is divided into separate zones G, Y, X and Z characterizing the different degrees of corrosiveness of the steam generator feedwater toward the material of the feedwater system tubes depending upon the operating mode. Depending upon where a point is situated in one of the zones of the two-parameter nomograms, the parameters of the coolant are adjusted or the power unit is shut down.

IPC Classes  ?

• G21C 17/022 - Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators

Abstract

The present invention pertains to the field of emergency protection systems of nuclear power plants. More particularly, the invention relates to Emergency Core Cooling System under loss-of-coolant accidents, namely, to sump protection device (SPD) in the emergency cooling system of a VVER, to the filter module and filter element of the sump protection device. The purpose of the invention is to protect sumps from accumulation of debris in case of a loss-of-coolant accident. As a solution to the problem, we claim a VVER emergency cooling system sump protection device, comprising a system of filters installed at the intake opening of the upper part of the sump located in the reactor containment bottom and connected to the intake of emergency cooling system pipeline. It consists of header-connected filter modules preventing debris from entering the intake of emergency cooling system pipelines; each filter module has slotted grates on sides and on top, and filter elements arranged inside are designed as laterally slotted filtration pipes and perforated distribution tubes (inside the pipes) the inner cavities of which are connected to headers.

IPC Classes  ?

• G21C 15/18 - Emergency cooling arrangements; Removing shut-down heat
• G21C 19/307 - Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids
• B01D 29/15 - Supported filter elements arranged for inward flow filtration
• B01D 29/52 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups ;   Filtering elements therefor with multiple filtering elements, characterised by their mutual disposition in parallel connection
• F16L 55/24 - Preventing accumulation of dirt or other matter in pipes, e.g. by traps, by strainers

Abstract

(57) A chemistry control system for a power plant includes at least one sensor (15) of an electrochemical indicator for a coolant, said sensor being electrically connected to a unit (21) for processing and transmitting measurement data, an outlet of said unit being connected to a central electronic computing machine (22) which controls actuators (23), (24) for injecting hydrogen and chemical reagents. The sensor (15) is a flow-through sensor; a hydraulic inlet of the sensor is attached via a pipe (13) for collecting samples to a process loop of the power plant, and a hydraulic outlet of the sensor (15) is hydraulically successively connected to a first heat exchanger (17) and a first throttling device (18), which is equipped with a reverse loop (19) for supplying coolant.

IPC Classes  ?

• G21C 17/022 - Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
• B08B 3/00 - Cleaning by methods involving the use or presence of liquid or steam

Abstract

The invention relates to water-cooled water-moderated power reactors (VVER), and, more particularly, to primary circuit auxiliary systems. The purpose of this invention is to provide integrity and normal operation of the T-unit, including cases when the unit operates under abnormal conditions. To address this problem in the flow mixing T-unit of reactor volume control system which includes a T-piece (1) connected with two ends to the bypass line carrying the coolant of one temperature, and with the additional opening to the makeup system pipeline carrying the coolant of a different temperature under emergency and an insert (2) which separates the coolant flows of different temperature, the insert is installed upstream the coolant flow in the bypass so that its outer part is located upstream the coolant inlet into the T-unit, and its inner part is cantilevered inside the T-unit and forms a tube with openings (5) in the area of the T-piece. The T-unit is provided with an adapter (6) mounted at its outlet and forming, together with the insert, a coaxial channel for coolant flow.

IPC Classes  ?

• G21C 15/22 - Structural association of coolant tubes with headers or other pipes, e.g. in pressure tube reactors
• B01F 5/04 - Injector mixers
• B01F 3/08 - Mixing, e.g. dispersing, emulsifying, according to the phases to be mixed liquids with liquids; Emulsifying
• F16L 41/02 - Branch units, e.g. made in one piece, welded, riveted
• G21D 1/02 - Arrangements of auxiliary equipment

Abstract

The present invention pertains to the field of emergency protection systems of nuclear power plants. More particularly, the invention relates to Emergency Core Cooling System under loss-of-coolant accidents, namely, to sump protection device (SPD) in the emergency cooling system of a VVER, to the filter module and filter element of the sump protection device. The purpose of the invention is to protect sumps from accumulation of debris in case of a loss-of-coolant accident. As a solution to the problem, we claim a VVER emergency cooling system sump protection device, comprising a system of filters installed at the intake opening of the upper part of the sump located in the reactor containment bottom and connected to the intake of emergency cooling system pipeline. It consists of header-connected filter modules preventing debris from entering the intake of emergency cooling system pipelines; each filter module has slotted grates on sides and on top, and filter elements arranged inside are designed as laterally slotted filtration pipes made of wire with slots between turns and perforated distribution tubes inside the pipes the inner cavities of which are connected to headers, the diameter of perforation holes in the tubes gets successively reduced down the flow.

IPC Classes  ?

• G21C 15/18 - Emergency cooling arrangements; Removing shut-down heat

Abstract

A power plant chemical control system, including at least one coolant electrochemical indication sensor of a flow type electrically connected to the measurement data processing and transmission unit with its output connected to a central computer controlling actuation devices for injection of hydrogen and chemical reagents; hydraulic inlet of the sensor is connected by a sampling tube to the power plant process circuit and its hydraulic outlet is connected to a first heat exchanger and a first throttling device with a coolant supply circuit in series, and is configured to pass a coolant sample to the coolant electromechanical sensor and said coolant supply circuit contains tubes and valves configured to reverse a flow of the coolant sample through the first throttling device.

IPC Classes  ?

• G21D 3/00 - Control of nuclear power plant

Abstract

The inventions relate to fire-fighting ground vehicles. A mobile fire extinguishing apparatus with pressurized foam generation comprises: a mixing chamber connected at the outlet to a device for supplying foam to the heart of a fire; and, connected by pipes to an inlet of the mixing chamber, a water supply system comprising a water supply pump with a drive, a foam-forming concentrate supply system comprising a foam pump with a drive, and also an air supply system comprising an air compressor with a drive. The apparatus is provided with a driving motor. The drives of the compressor and of the foam pump are in the form of an adjustable hydraulic transmission of the air compressor drive and an adjustable hydraulic transmission of the foam pump drive, which are kinematically connected to the driving motor. The apparatus is also provided with a water meter, a gate valve having an electric drive, and a non-return valve, which are mounted on a water supply pipe between the water supply pump and the mixing chamber, and is further provided with an electronic control unit for the gate valve. An input of the gate valve control unit is electrically connected to an output of the water meter, and an output of the gate valve control unit is electrically connected to an input of the electric drive of the gate valve. This makes it possible to produce foam having the necessary delivery pressure and density under any pump operating modes.

IPC Classes  ?

• A62C 27/00 - Fire-fighting land vehicles
• A62C 5/02 - Making of fire-extinguishing materials immediately before use of foam

Abstract

The inventions relate to fire-fighting ground vehicles. A mobile lire extinguishing apparatus with pressurized foam generation comprises: a mixing chamber connected at the outlet to a device for supplying foam to the heart of a fire; and, connected by pipes to an inlet of the mixing chamber, a water supply system comprising a water supply pump with a drive, a foam-forming concentrate supply system comprising a foam pump with a drive, and also an air supply system comprising an air compressor with a drive. The apparatus is provided with a driving motor. The drives of the compressor and of the foam pump are in the form of an adjustable hydraulic transmission of the air compressor drive and an adjustable hydraulic transmission of the foam pump drive, which are kinematically connected to the driving motor. The apparatus is also provided with a water meter, a gate valve having an electric drive, and a non-return valve, which are mounted on a water supply pipe between the water supply pump and the mixing chamber, and is further provided with an electronic control unit for the gate valve. An input of the gate valve control unit is electrically connected to an output of the water meter, and an output of the gate valve control unit is electrically connected to an input of the electric drive of the gate valve. This makes it possible to produce foam having the necessary delivery pressure and density under any pump operating modes.

IPC Classes  ?

• A62C 27/00 - Fire-fighting land vehicles
• A62C 5/02 - Making of fire-extinguishing materials immediately before use of foam

Abstract

The invention relates to nuclear engineering, specifically to a technology for the manufacture of oxide nuclear fuel for fuel elements, and can be used for the manufacture of pelletized uranium dioxide-based nuclear fuel for atomic power stations. Essence of the invention: the method for the manufacture of nuclear fuel pellets from uranium dioxide incorporates the preparation of a uranium dioxide moulding powder, with or without added uranium oxide concentrate, wherein a powder of uranium dioxide with an O/U ratio = 2.37~0.04 is used as the feed material for the preparation of the moulding powder, which uranium dioxide powder is produced beforehand using the known method of heating up ceramic-grade uranium dioxide powder with an O/U ratio = 2.01-2.15 in air. The technical result of the claimed invention is an improvement in the mechanical strength of sintered pellets and an increase in

IPC Classes  ?

• G21C 3/62 - Ceramic fuel

Abstract

The invention relates to nuclear engineering, specifically to a technology for the manufacture of oxide nuclear fuel for fuel elements, and can be used for the manufacture of pelletized uranium dioxide-based nuclear fuel for atomic power stations. Essence of the invention: the method for the manufacture of nuclear fuel pellets from uranium dioxide incorporates the preparation of a uranium dioxide moulding powder, with or without added uranium oxide concentrate, wherein a powder of uranium dioxide with an O/U ratio = 2.37±0.04 is used as the feed material for the preparation of the moulding powder, which uranium dioxide powder is produced beforehand using the known method of heating up ceramic-grade uranium dioxide powder with an O/U ratio = 2.01-2.15 in air. The technical result of the claimed invention is an improvement in the mechanical strength of sintered pellets and an increase in the grain size of a sintered pellet.

IPC Classes  ?

• G21C 3/62 - Ceramic fuel

Abstract

The invention relates to the comprehensive treatment of complex boron-containing liquid waste from a nuclear power plant. A method for treating liquid waste from a nuclear power plant with boron control includes introducing calcium nitrate into a borate solution with precipitation of calcium borate and the removal of same from the mother liquor, performing electrodialysis using an electrodialysis cell having a cation exchange membrane and an anion exchange membrane, and obtaining boric acid and a solution of the hydroxides of sodium and potassium. The initial borate solution contains salts of sodium and potassium in the form of their nitrates and sulphates. Calcium nitrate is introduced into the initial borate solution, producing a joint precipitate of borate and calcium sulphate. Boric acid is obtained by treating the joint precipitate of borate and calcium sulphate with a solution of nitric acid with separation of a calcium sulphate precipitate from a solution of calcium borate. The calcium borate solution is treated with nitric acid, forming a precipitate of boric acid and a solution of calcium nitrate. The boric acid precipitate is separated and dried. The mother liquor is subjected to electrodialysis to produce solutions of nitric acid and of the hydroxides of sodium and potassium.

IPC Classes  ?

• G21F 9/06 - Processing
• G21F 9/20 - Disposal of liquid waste

Abstract

The invention relates to the comprehensive treatment of complex boron-containing liquid waste from a nuclear power plant. A method for treating liquid waste from a nuclear power plant with boron control includes introducing calcium nitrate into a borate solution with precipitation of calcium borate and the removal of same from the mother liquor, performing electrodialysis using an electrodialysis cell having a cation exchange membrane and an anion exchange membrane, and obtaining boric acid and a solution of the hydroxides of sodium and potassium. The initial borate solution contains salts of sodium and potassium in the form of their nitrates and sulphates. Calcium nitrate is introduced into the initial borate solution, producing a joint precipitate of borate and calcium sulphate. Boric acid is obtained by treating the joint precipitate of borate and calcium sulphate with a solution of nitric acid with separation of a calcium sulphate precipitate from a solution of calcium borate. The calcium borate solution is treated with nitric acid, forming a precipitate of boric acid and a solution of calcium nitrate. The boric acid precipitate is separated and dried. The mother liquor is subjected to electrodialysis to produce solutions of nitric acid and of the hydroxides of sodium and potassium.

IPC Classes  ?

• G21F 9/06 - Processing
• G21F 9/20 - Disposal of liquid waste

Abstract

The invention relates to electronics, in particular to supercapacitors. A supercapacitor consists of a sealed protective housing, and first and second electrodes electrically insulated from one another. One or both of the electrodes are also insulated from the housing. The free volume of a cell and the space between the electrodes are filled with an electrolyte. Carbon-containing materials containing the isotope C-14 are applied to the surface of the first electrode. A method for producing a supercapacitor consists in preparing first and second electrodes, including applying a surface layer made of carbon-containing materials; arranging the first and second electrodes in a sealed housing and electrically insulating them from one another; and filling the housing with an electrolyte. Isotope C-14 is introduced into the layer of carbon-containing materials on the surface of the first electrode. This makes it possible to create a device for storing electric charge which does not need to be charged from an external source of electricity, and increases the operating life of a device which does not use an external charging power source.

IPC Classes  ?

• H01G 9/04 - Electrodes
• H01G 11/32 - Carbon-based

Abstract

The invention relates to nuclear engineering and can be used in the neutron irradiation of different materials (targets) to produce radionuclides. The essence of the invention lies in a method for producing radioactive isotopes in a fast neutron reactor which includes the following steps. Targets for the production of radioisotopes are positioned between sleeves and rods in an irradiation assembly, the rods being made of a neutron-moderating material, and the irradiation assembly is placed in a side shield of a fast neutron reactor. The irradiation assembly is surrounded with assemblies which do not contain nuclear fuel. In the irradiation assembly fast neutrons are passed through the neutron-moderating material, and the moderated neutrons are then passed through the material to be irradiated (the target) in the irradiation assembly. The characterizing features of the present invention are that radioisotopes are produced simultaneously in the irradiation assembly and the surrounding assemblies, in which the steel content is not greater than 50%. The targets in the irradiation assembly have an absorption cross section of more than 1 barn at a neutron energy of less than 0.1 MeV. The targets in the assemblies surrounding the irradiation assembly have a neutron absorption cross section of less than 1 barn at a neutron energy of more than 0.1 MeV.

IPC Classes  ?

• G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
• G21G 4/08 - Radioactive sources other than neutron sources characterised by constructional features specially adapted for medical applications
• G21C 1/02 - Fast fission reactors, i.e. reactors not using a moderator

Goods & Services

Polymer and ceramic materials for 3D-printing and additive technologies. Fine powders of metals and alloys; metallic materials for 3D-printing and additive technologies. Metal additive machines (3D printers); equipment for the application of multi-layer coatings; equipment for granulated powders of metals and alloys; devices for playback of 3D models, as well as for computer-generated designs; machines and devices for playback of additive technologies. Computer equipment; 3D scanners; lasers, not for medical purposes; software (PC platform) for converting 3D models to the physical facilities; equipment for reproducing images in additive manufacturing. Processing of materials; printing by methods of additive manufacturing technology; digital design (CAD) by additive technologies; laser forming objects. Scientific and technological services and research and design relating thereto; development of additive technologies; development of regulatory documents for additive technologies.

Abstract

The invention relates to the field of nuclear engineering and can be used as part of the fuel-handling equipment of a nuclear reactor. The technical problem addressed by the present invention is that of providing linearity of movement for a cable when an angle of inclination of an inclined shaft in an inclined elevator is increased. The solution to this problem allows a reduction in the dimensions of openings in the walls of a building of a reactor compartment and a spent fuel pool, through which a trolley passes. The present inclined elevator of a nuclear reactor comprises a trolley (1) which has a sheath (2) for a spent fuel assembly and which travels along a track (3) in an inclined shaft (4) with the aid of a cable (8). A guide pulley provided with an asymmetric groove for the cable to pass through is mounted at the entrance to the inclined shaft (4), and is mounted relative to the track at an angle β that satisfies the condition tg β= t/πD, where: β is the angle of inclination of the guide pulley relative to the track; t is the pitch of the channels for the cable on a drum; and D is the diameter of the drum, the axis of symmetry of the groove in the guide pulley lying along the motion trajectory of the cable.

IPC Classes  ?

• G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
• G21F 9/34 - Disposal of solid waste

Abstract

The invention relates to the field of nuclear engineering and can be used as part of the fuel-handling equipment of a nuclear reactor. The technical problem consists in producing a track for an inclined elevator which, by virtue of having a shorter length, allows a reduction in the time that a trolley carrying spent fuel assemblies spends in a gaseous atmosphere. The solution to this problem provides for increased safety when conveying spent fuel assemblies along an inclined elevator of a nuclear reactor. The essence of the invention is that the track of the inclined elevator of a nuclear reactor comprises alternate rectilinear and curvilinear sections, wherein the initial section and the end section are rectilinear and are arranged at the same angle of inclination α relative to a horizontal plane.

IPC Classes  ?

• E01B 23/02 - Tracks for light railways, e.g. for field, colliery, or mine use
• G21F 9/34 - Disposal of solid waste

Goods & Services

Unprocessed polymer and ceramic materials, namely, resins and powders for 3D-printing and for use as additive technologies for the further manufacture of goods Fine powders of common metals and alloys used in manufacturing; metallic materials for 3D-printing and additive technologies, namely, common metal powders for manufacturing purposes Metal additive machines, namely, 3D printers; equipment for the application of multi-layer coatings, namely, 3D printers; equipment for granulated powders of metals and alloys, namely, 3D printers; devices for playback of 3D models, as well as for computer-generated designs, namely, 3D printers; machines and devices for playback of additive technologies, namely, 3D printers Computer peripheral equipment; 3D scanners; lasers, not for medical purposes; software for converting 3D models to the physical facilities; equipment for reproducing images in additive manufacturing, namely, 3D scanners Processing of materials, namely, three dimensional printing services; printing by methods of additive manufacturing technology, namely, 3D printing; digital design (CAD) by additive technologies, namely, additive manufacturing; laser forming objects, namely, 3D printing services Scientific and technological services, namely, research and design relating to three dimensional printing and additive manufacturing; development of additive technologies in the field of three dimensional printing; development of regulatory documents for additive technologies, namely, quality control for additive manufacturing