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Apparatus for collecting spills of spent nuclear fuel pellets Invention relates to means of ensuring safety when reloading spent fuel assemblies of the VVER-100 reactor from transfer baskets into storage covers, and is intended for use in water-filled spent nuclear fuel storages as an emergency tool. The apparatus for collecting spills of spent nuclear fuel pellets comprises a bar mounted on a hoisting apparatus with a protective cup mounted in the lower part of said bar. A collector, having a receiving tray and a dispensing tray, is mounted between plates of the cup such that it can be rotated by torsional springs. A scraper is mounted in the receiving tray such that it can be rotated by torsional springs, and the force of the torsional springs of the collector is greater than that of the torsional springs of the scraper. A rope is tied to the scraper, said rope being connected to a drive which is mounted in the top part of the bar. A funnel is placed on the rotation path of the dispensing tray. The drive of the scraper used is a handle - lift latch, which is movable on a longitudinal groove in the bar and fixed in transverse grooves connected to the longitudinal groove. |
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Device for storage and/or transportation of radioactive wastes and method of its production Invention relates to the system for storage and/or transportation of radioactive wastes with high level of radioactivity and to method of its production. In compliance with this invention, proposed device is composed of vented vertical container with inlet air ducts to refract the emission, back into wastes storage space. Line of straight vision through inlet air ducts does not exist, hence, the bag can stand directly on the floor. Invention covers also the method of production of variable-height vented vertical container. |
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Apparatus for foiling fuel element cladding Apparatus for foiling fuel element cladding has a foil, rollers for rolling the foil, a die, a bar with a cylinder whose diameter is equal to the diameter of pellets of fissile material, sponges surrounding the cylinder in front of a slide valve. The slide valve is spring-loaded in guides from two pipe sections with slits which restrict its movement, wherein the guides are placed at the end of the fuel element cladding, which is placed in a lodgement. On the plane of the slide valve, there are protrusions which form a radial flange of the foil at the end of the cylinder. |
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Sirota's method of nuclear or thermonuclear blast reaction Nuclear or thermonuclear reaction is initiated by charge blasting inside solid metal body arranged in solid enclosure. Note here that blast energy is higher that metal body fusion heat energy while heat generated by blast in said body is exploited via solid enclosure. Note here that as said body cools down blasts therein reiterate while every next blast occurs after body conversion into solid state. Charge blast energy should be sufficient for body melt conversion into vapour. |
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Connecting device for jar filling system for producing nuclear fuel Invention relates to a system for filling containers with powdered material, e.g. for producing nuclear fuel. The system includes a device for connecting a container and a material feed system. The device includes a stationary connection portion (I) connected to the feed system, and a moving connection portion (II) which moves relative to the stationary connection portion (I) and can be connected to the filling hole of the container (4). The moving connection portion (II) includes on the level of a downstream end at least one sealing means (30) to form a tight connection by adjoining to the contour of the filling hole. The downstream end of the moving connection portion (II) is connected to the stationary connection portion (I) by a flexible sealing means (42) to provide mechanical disengagement between the downstream end of the moving connection portion (II) and the stationary connection portion (I). |
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Production of tubular fuel elements, preferably, of hexagon shape Invention can be used in production of tubular fuel elements of teaching reactors running on fuel of high and low concentration shaped, preferably, to hexahedron. Said prefabricated blank is subjected to hot forming, drawing of formed pipe and quenched. Prior to forming, composite billet is heated in alt bath or resistance kiln to 380-440°C. Round pipe forming is performed with drawing of 7-15, preferably, 8-12. After forming, pipe is produced with wall depth at rear end equal to or higher than finished pipe wall depth by not over 0.10 mm. Drawing is made in tree steps. At first step, drawing with wall thinning is carried out while at second and third steps two-stage forming of round pipe to hexagon. At second pass, preliminary forming is made without thinning and pipe diameter reduction with forming of hexagonal pipe while at third pass final forming is performed. Heat treatment is carried out before first and second drawing passes. Before every heat treatment, pipe is subjected to chemical processing in the solution of nitric acid at 90-100°C. |
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Composition for long-term storage of transuranium elements Oxides of transuranium elements are mixed with palladium metal powder in the following ratio, wt %: oxides of transuranium elements - 30-70, palladium metal - 70-30, and the obtained mixture is pressed. As a result, a composition for long-term storage of transuranium elements is obtained, which includes oxides of transuranium elements in palladium metal, which provides high chemical stability of the material, safety during indefinite storage, while preserving the capacity to extract transplutonium elements after dissolving the disclosed composition in nitric acid. The invention proposes the use of industrial ("reactor") palladium, which is a nuclear fuel fission product, to produce the disclosed composition. |
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Method of making neutron moderator and reflector units of nuclear reactor Invention relates to nuclear engineering and can be used in making neutron moderator and reflector units containing beryllium, primarily for research reactors. The method of making neutron moderator and reflector units of a nuclear reactor includes placing beryllium in a sealed casing. The casing, which defines the shape of the unit, is hermetically connected to a bottom fitting. Beryllium granules are poured into the casing and compacted and the casing is then hermetically connected to a top fitting. When making moderator units, compacting is carried out to density of 70-85% of the theoretical value to 60-90% of the theoretical value when making reflector units. |
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Method of producing boron-11 isotope and compounds based thereon Invention relates to nuclear engineering, particularly to production of stable isotopes using neutron beams, and can be used in the electronic industry when producing semiconductor silicon structures using ion implantation techniques, as well as nuclear engineering when designing neutron retarding elements. The disclosed method includes making a starting target from a substance which contains a mixture of boron-10 and boron-11 isotopes, irradiating the target with neutron flux to the required or complete burn-off of the boron-10 isotope and extracting the 11B isotope from the substance. |
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Group of inventions relates to nuclear engineering, particularly to packing (loading) defective spent fuel elements into an ampoule (rabbit) for temporary storage in a cooling pond and subsequent transportation for processing. After loading spent fuel elements into a rabbit and pressing-in a top cover, the bottom cover of the rabbit is placed on a caisson support/locking member, the loaded rabbit is placed in the caisson, compressed air is fed into the caisson, after which the loaded rabbit is placed down on the bottom cover and the loaded rabbit is extracted from the caisson. The disclosed method is realised by an apparatus which consists of a rabbit and a caisson. The rabbit consists of a sealed housing with a top and a bottom cover. A support for loaded fuel elements is placed in the housing of the rabbit and the top and bottom covers are provided with seals. The housing of the rabbit is capable of moving vertically through a seal assembly into the caisson. The inlet pipe of the caisson is connected through a valve to a compressed air pipe and the outlet pipe is linked to the atmosphere over the pond. In the bottom part of the caisson, there is a support/locking member for mounting the bottom cover of the rabbit. A support for loaded fuel elements is placed in the housing of the rabbit and the top and bottom covers are provided with seals. |
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Device for testing materials in nuclear reactor Device for testing materials in a nuclear reactor comprises a housing in which upper inner part the cassette with sample materials is located, and in the lower - the cassette with fuel elements, at that the cassette with fuel elements is attached in the housing with the ability of longitudinal displacement. |
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Fuel element for nuclear reactor Invention relates to nuclear engineering and can be used to produce fuel elements for slow and fast neutron reactors. A fuel element for a nuclear reactor, having a sealed shell in which there is a fuel kernel and voids, further includes a working fluid with a melting point and a boiling point which correspond to the operating temperature range on the periphery of the shell and at the centre of the fuel kernel, and the fuel kernel contains nuclear fuel of a capillary structure with interconnected porosity. |
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Method of extracting radionuclides from aqueous solutions Invention relates to radio analytical chemistry and can be used to monitor content of radionuclides in fresh and sea water, in urine of individuals exposed to radiation and in samples of different process solutions. The method of extracting radionuclides from aqueous solutions includes filtering the solution through a selective sorbent placed in the drip chamber of an apparatus used for intravenous transfusion of infusion solutions and preparing an agent suitable for gamma-ray spectrometry. |
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Horizontal reactor with displacing neutron reflector and method of its operation Proposed nuclear power reactors allow compensation for reactivity lost in fuel burnup at one section of core region by displacement of reflector to core region section with "fresh" fuel. Reactor core region is arranged in horizontal body of the reactor, over its entire length. Displacing neutron reflector surrounds reactor body from above and on sides, outside the reactor body, to surround core region section inside the reactor body whereat controlled chain reaction of fission and energy release occurs. Stationary bottom reflector is arranged under reactor body. Heat carrier is forced in reactor body along core region. At decrease in reactivity margin in energy release area displacing reflector sifts to adjacent core region section with "fresh" fuel to involve said fresh fuel in energy release process. |
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Production of spacer grate of fuel assembly comprises making of elements with inner ledges, securing them between themselves and to shell and annealing. At final step, definite residual strains are created in grate elements which allow a gradual decrease in internal inscribed diameter of elements at operation of fuel assembly in nuclear reactor. |
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Nuclear reactor core and nuclear reactor Invention relates to travelling-wave (deflagration) nuclear reactors. The nuclear reactor core comprises a feed area 11 into which fresh fuel is loaded and a burning area 12 where fuel burns. Uranium-derived plutonium decays to generate output energy and the burning area 12 moves from the beginning to the end of the burning cycle. If the core, which is substantially circular when viewed from above, is divided into a central part and a peripheral part, the feed area 11 is formed such that the mass of uranium per unit volume in the central part is less than that in the peripheral part. |
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Production of tubular fuel elements Invention can be used in production of tubular fuel elements of teaching reactors running on fuel of high and low concentration shaped, preferably, to hexahedron. Proposed process comprises making of prefabricated blank. The latter is composed of front plug, fuel core with fissionable material and rear plug enclosed in shell from thermally-hardenable aluminium alloy. Said prefabricated blank is subjected to hot forming, drawing of formed pipe and quenched. Forming of said blank is performed with application of lubricant, taper female die and movable conical needle. At first drawing pass, pipe is produced with equal wall depth over its length. Every drawing pass or set of drawing passes performed before heat treatment, is executed at total reduction at pipe centre not over 10% for not over 3 hours from the end of heat treatment in direction of forming. |
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Method of extracting caesium radionuclides from aqueous solutions Invention relates to sorption extraction of caesium radionuclides from aqueous solutions. The method of extracting caesium radionuclides includes filtering an aqueous solution through a selective sorbent which is iron-potassium ferrocyanide on a support, desorption of caesium from the sorbent with an alkaline solution containing Trilon B and potassium oxalate. The eluate obtained from desorption is further filtered through a sorbent which is nickel-potassium ferrocyanide. |
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Invention relates to alumoborosilicate glasses for isolation of radioactive liquid effluents of a medium activity. Claimed is a qualitative and quantitative composition of alumosilicate glass, a glass-forming additive for its obtaining and a method of processing a radioactive liquid effluent of the medium activity with application of the claimed glass-forming additive, resulting in obtaining the said alumoborosilicate glass. |
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Nuclear reactor fuel assembly has a head, a tail, a bundle of cylindrical fuel elements and guide channels located in spacer grids, and aligning elements made in spacer grid cells. At least part of the aligning elements in contact with the spacer grid is made on casings of the fuel elements at places where the spacer grids are located. In a particular design of the fuel assembly, on at least part of the outer surface of the casings of the fuel elements there are wall-mounted heat exchange intensifiers, the projection height over the surface of the casings of which is less than the projection height of the aligning elements. |
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Method to control power plant heating Form difference of signals of the measured and given rate of temperature change of heat-carrying medium, then this difference of signals is integrated and control by heating regulator by sum of power control signal and integration result signal is performed. Characteristics of the selected power is shaped additionally, then the signal characterising the selected power is set by this characteristics. When shaping characteristics of the selected power, value and changing rate of the used medium consumption of the second circuit are taken into account additionally. |
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Apparatus for cleaning a radioactive steam-gas mixture during accidental discharge of a pressurised water reactor has a protective casing having safety valves, connected by a conduit pipe to series-arranged louvre separator and steam-jet ejector, located outside the protective casing. The separator is connected to an accumulator tank in the top part and to a container for collecting separated liquid in the lower part. The ejector is placed in a pond having perforated pipes around its periphery. The accumulator tank and the perforated pipes are connected by receivers. The pond is equipped with an air cooler and an exhaust hood over it. The exhaust hood is connected to a gas holding pipe which is fitted with aerosol filters. The gas holding pipe is connected by gas-relief lines to the separator and the conduit pipe. The accumulator tank and the pond are filled with an alkaline solution. |
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Nuclear reactor fuel element simulator Fuel element simulator has a shell in which there is a column of natural fuel tablets with a centre hole, and an electric heater placed with clearance in the holes of the tablets. The heater is in form of pipe made of heat-resistant material on the outer surface of which is formed a microrelief which varies on the length of the heater and which provides optically variable properties on the length of the surface, which correspond to the simulated temperature profile. A shielding pipe made of heat-resistant material is also placed with clearance on the outside coaxial to the shell, the inner and outer surfaces of said pipe also having a varying microrelief which provides optically variable properties on the length of the heater. |
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Device includes vacuum accelerator tube with anode and cathode with target on the internal surface, pulse voltage generator, high-voltage actuation transformer with its high-voltage winding connected to accelerator tube cathode and low-voltage winding connected to accumulation capacitor via discharger. Accelerator tube anode is made in the form of two counter-directed rods in symmetrical position, rod ends bearing heads out of deuterium-saturated metal, one of rods is connected to primary winding of high-voltage transformer, second rod is grounded, and cathode with target are made in the form of cylinder housing the anode symmetrically. |
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Invention relates to power engineering. Pressure chamber (4) comprises cylindrical case (3) with bottom (2), cylindrical shell (8) and grate (6). Cylindrical shell (8) is arranged coaxially with case (3) to divide its chamber into communicated central discharge channel (7) and lateral circular feed channel (1). Grate (6) is located in said central discharge channel (7). At porosity factor of 0.05-0.7 of grate (6) definite ratios exist for pressure chamber (4). These ratios allow for, first, correlation between maximum radius of perforated section of grate (6), height of pressure chamber (4), outer radius of cylindrical shell (8), height of inlet of said chamber (4) and case ID. Second, interrelation of pressure chamber height, cylindrical shell outer radius and pressure chamber inlet height. Third, correlation between case (3) inner radius, cylindrical shell (8) outer and inner radius and pressure chamber (4) inlet height. Fourth, correlation between pressure chamber (4) height and its inlet height. Fifth, correlation between maximum radius of perforated section of grate (6) height of inlet of said chamber (4). Invention cites relationship for selection of pressure chamber (4) flow section sizes that allows for working fluid flow hydraulic characteristics. |
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Invention relates to the field of nuclear power plants (NPP) of high power, operating with closed loop of working medium to generate electricity and produce thrust. The NPP contains electric propulsion power plant, refrigerator-emitter, reactor system with working medium, recuperative heat exchanger and compressor-turbine generator. The last one consists of turbine, compressor, electric power generator. Outlet from recuperative heat exchanger of the cooled working medium is connected to the inlet of Rank-Hilsch vortex tube. Outlet from the Rank-Hilsch vortex tube by the "hot" working medium is connected to refrigerator-emitter, and the outlet by "cold" working medium - to the compressor, in this case the outlet of refrigerator-emitter is connected to the compressor inlet. |
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Passive nuclear reactor protective system Invention relates to nuclear power engineering and can be used to improve reliability of a reactor block, increase intensity and controllability of corium cooling during accident containment at a nuclear power plant. The passive nuclear reactor protective system comprises a nuclear reactor housing; on the inner surface of the lower part of the reactor housing there are thin-wall metal blocks whose inner cavity is filled with a ceramic refractory material. In the middle part of opposite sides of the blocks there are deep recesses that are half the thickness of the block. On the inner surface of the lower part of the reactor housing there are locking members having on one side, which is mated with the deep recess, a hard groove and on the other side, which is mated with the deep recess of another mated block, a groove made on an elastic pusher plate. |
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Method of rare-earth elements extraction from liquid alloys with zinc Proposed method comprises immersion of alloy into salt melt to change rare-earth element from liquid alloy into melt by oxidation. Note here that said oxidation us performed in zinc chloride melt at 420-550°C while melt zinc ions are used as oxidiser. |
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Neutron-absorbing material based on dysprosium hafnate Invention relates to a neutron-absorbing material based on dysprosium hafnate, which contains dysprosium and hafnium oxides. The material additionally contains molybdenum trioxide, has the following component ratio, wt %: dysprosium oxide 60…70; hafnium oxide 25…35; molybdenum trioxide 3…5, and is obtained by a solid-phase synthesis at a temperature of 1500-1700°C in air. Initial components, used in dysprosium hafnate production, are in a nanostructured state with a value of coherent dispersion area less than 100 nm. |
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Composite fuel model material with inert porous metal matrix and method for production thereof Invention relates to composite fuel model material consisting of a radiation-inert matrix and particles of a material which simulates nuclear fissile material (minor actinides). The material is characterised by that the inert matrix is made of porous metallic material and particles of the material which simulates nuclear fissile material uniformly coat the inner surface of the pores of the inert porous metal matrix and are in thermal contact with said matrix. The disclosed material is characterised by use of a metal matrix material with stronger contact of oxide particles with the porous metal matrix; the possibility of obtaining a given porosity of the porous metal matrix and degree of filling thereof with a fuel oxide (model oxide); the possibility of obtaining more accurate size tolerance when producing the porous metal matrix; high technological effectiveness of a separate process of producing a porous metal matrix, which enables to vary nuclear and physical characteristics by using different metals and alloys. |
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Membrane cargo capacity for liquefied natural gas transportation and storage Invention relates to transport shipbuilding, means for marine freight and storage of liquefied natural gas (LNG) and concerns design of membrane cargo capacity for its transportation and storage. Reservoir for transportation and storage of LNG includes structured thermally insulated shell mounted on carrying structure of freight vessel or capacity. The shell consists of several layers. In this structure, one layer is metal and sealed and contacts with liquefied gas being transferred or stored. The layer contains undulating corrugations. Wave tops and troughs form zigzags. Undulating indents between corrugations on the outside are filled with porous synthetic material or paste based on chopped glass fibre and binding agent. |
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Invention relates to technology of manufacturing materials for protection against neutron radiation. A paste-like material for protection against neutron radiation includes solid grease VNIINP-293 and amorphous powder boron as a filling agent with a weight component ratio (%) 91-97 and 3-19 respectively, and a specific surface of amorphous boron powder constitutes not less than 15 m2/g. A method of preparing the claimed material includes mixing solid grease VNIINP-293 and the filling agent - amorphous powder boron in a weight ratio (%) respectively 91-97 and 3-9. |
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Method of obtaining strontium-82 Method of obtaining strontium-82 includes carrying out the following operations: irradiation in the flow of accelerated charged particles of a target, representing a steel envelope, filled with metal rubidium, opening the envelope of an irradiated target in a gas medium, which does not react with metal rubidium, melting irradiated metal rubidium in the envelope and supply of its melt into a chemical reactor, supply of nitrous oxide in portions into the chemical reactor, at least, until growth of a temperature in the chemical reactor with supply of fresh portion of nitrous oxide stops, dissolution in the chemical reactor of formed in the chemical reactor explosion-proof and fireproof rubidium salts and strontium-82 1.5÷4.5 M present in them with a nitric acid solution, separation of strontium-82 from the obtained solution by sorption. In particular cases of realisation the method includes: application of strontium-specific sorbent 4,4'(5')-di(tert-butylcyclohexano)-18-crown-6, applied on a polymer of polyacrylate structure, purification of a strontium-82 solution from traces of crown ether on a column with a cation-exchange resin, correction of the volume and acidity of strontium-82 solution. |
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Fire-resistant neutron-protective material Invention relates to materials with neutron-absorbing properties for protection against neutron radiation. Claimed is a fire-resistant neutron-protective material, consisting of a magnesium phosphate binding agent (24-33 wt %) and a powder part (76-67 wt %, with the powder part containing titanium hydride TiH2 (90.3-95.5 wt %), magnesium oxide MgO (2.7-4.5 wt %) and boron carbide B4C (1.8-5.2 wt %). Components are mixed to a homogeneous state and poured into a special cavity, and after hardening are subjected to thermal processing. |
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Method of selective extraction of radionuclides from radioactive nitric acid solutions (versions) Invention relates to radiochemical technology and can be used in production of "reactor" 99Mo as a generator of 99mTc of a biomedical purpose, as well as in an analysis of technological solutions for preliminary separation of Mo or Mo and Zr in extraction reprocessing of solutions of technology of spent nuclear fuel of nuclear power plants (NPP SNF). Described are versions of methods of selective extractive separation of a considerable part of molybdenum or together molybdenum and zirconium from radioactive solutions with obtaining an extract. A reprocessed radioactive solution is processed with an extractant, which represents poorly soluble in a water phase alcohol, in the presence of an extracted complexing agent. As the complexing agent, hydroxamic acids with a number of carbon atoms 6-12 can be used, which ensures sufficiently complete extraction of molybdenum and zirconium in an organic phase. Molybdenum or molybdenum and zirconium are separated from the extract in the compact form by sublimation or re-extraction. |
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Method for hardening liquid highly active wastes Method involves converting wastes to a gel-like state and is characterised by that solutions of highly active wastes are mixed with zirconium and iron salts and glycerine to concentration of said salts of not less than 0.12, 0.6 and 0.25 M/l respectively, holding the obtained mixture for not less than 2.5 hours, followed by adding to the mixture a solution of mono-substituted potassium phosphate in phosphoric acid to molar ratio of components Zr:Fe:K:PO4=1:3:2:5-8, drying, calcining the obtained polymer gel of zirconyl phosphate at 70-90°C and 300-400°C, respectively, and melting the obtained granules at 980-1000°C. |
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Invention relates to nuclear power engineering, specifically to nuclear reactors, and can be used to produce heat and electric power, to burn transuranium nuclides and produce nuclear fuel and radioactive preparations. The reactor assembly comprises a reactor with a core inside the reactor housing. The cooling loop includes a heat exchanger connected to a coolant circulation line and a container for emergency discharge of fuel solution connected to the core. The core is formed in the reactor housing in form of two cavities separated by a partition wall. The cavities are linked to each other in the lower part of the reactor housing by a slit formed between the lower edge of the partition wall and the bottom of the housing, and in the upper part by pipes, each fitted with a circulation pump. The assembly is equipped with at least one container placed in one of the cores and connected to the heat exchanger of the cooling loop of the core. |
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Liquid metal cooled nuclear reactor (versions) Liquid metal cooled nuclear reactor has a housing with a separating shell inside. At least one steam generator and one pump are mounted in the annular space between the housing and the separating shell. Inside the separating shell there is a core, above which there is a hot header linked to the steam generator in its middle part in order to split the stream of liquid metal coolant into an ascending stream and a descending stream, or the hot heading is linked to the steam generator at its top part to facilitate counterflow heat exchange. Under the cover of the reactor there is an upper horizontal cold header with free coolant level, and under the steam generator there is a lower collection header linked to the upper cold header. The input of the pump is connected to the upper cold header and the output of the pump is connected to a lower annular pressure header, wherein the headers are divided by a horizontal partition, wherein the lower annular pressure header is linked to the distributing header of the core. |
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Present group of inventions relates to means of studying nuclear fusion reactions involving nuclei of hydrogen isotopes. The invention involves forming a metallic crystalline body (MCB) via condensation of metal vapour and embedding atoms of hydrogen isotopes into the MCB so that at least some of the atoms with hydrogen nuclei are at the shortest possible distance from each other. Atoms of hydrogen isotopes are embedded simultaneously to form the MCB itself by condensation of metal vapour in a medium of gaseous hydrogen isotopes and by fusion of metal microcrystals obtained via condensation of metal vapour in a medium of gaseous hydrogen isotopes and annealing in a medium of gaseous hydrogen isotopes. The disclosed apparatus comprises the following units, connected by gas pipes with valves: a source of gaseous hydrogen isotopes; a reactor capable of evaporating metal and condensing metal vapour into a MCB in a medium of gaseous hydrogen isotopes; a means of controlling pressure of the gaseous medium in the source of gaseous hydrogen isotopes and in the reactor; means of monitoring pressure of said gaseous medium; and means of detecting products of nuclear reactions. |
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Method of recycling waste solutions in production of uranium tetrafluoride Invention relates to hydrometallurgy of uranium and can be used to recycle mother solutions formed when producing uranium tetrafluoride from nitrate solutions via extraction, re-extraction and heat treatment of uranium compounds obtained from re-extracts to obtain uranium dioxide and further treatment thereof with chloride and fluoride solutions. The method of recycling mother solutions from production of uranium tetrafluoride involves mixing said solutions at pH 4.0-5.2 by bubbling air until pH stabilises and treating with sodium hydroxide at pH 10.5-11.0, separating the uranium-containing residues from the solutions and return thereof to the step of leaching raw products, settling the waste solutions in a tailing pond and pumping the remaining part of the solutions into the ground. |
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Burnable absorbing materials and installations for nuclear reactors and methods of their application Invention relates to materials, suitable as burnable absorbers in nuclear reactors, to elements, which contain the said materials, as well as to methods of their application. Burnable absorbing materials in accordance with the invention can include natural iridium and enriched iridium-193. Elements in accordance with the invention can be produced, formed and placed to provide required effects of the burnable absorbers in a core of a nuclear reactor in composition of such elements as the upper and lower cover plates, a water tube, a separator and a reactor fuel channel. The burnable absorber is in fact converted only into platinum after exposure in a neuron flow in the working reactor. |
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Construction method of underground repository for radioactive wastes Claimed invention relates to a construction method of repository for radioactive wastes. The declared method involves hole drilling in permafrost rocks, descent and cementing of an intermediate casing, arrangement of containers with radioactive wastes in the hole, sealing of the upper part of the hole. In the declared method, the intermediate casing is cemented in the range from the calculated boundary of the thawing zone up to the surface, and the containers with radioactive wastes are mounted on the hollow liner, perforated in the lower part, at a distance h 1 = h о m ⋅ m ⋅ ( R o m 2 − R c 2 ) R c 2 from the hole bottom, where hom - interval height within which thawing of permafrost rocks happens; m - porosity of permafrost rocks; Rom - calculated radius of thawing; Rc - inner hole radius. |
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Invention relates to aerospace engineering, particularly to nuclear rocket engines intended for long-term non-stop flights in atmosphere stratosphere and near earth space. Proposed engine comprises nuclear reactor, heat exchange chamber with radiation-protection bottom where through heat ducts are passed. Nuclear reactor heat exchange chamber represents a sectionalised design with heating channels separated by section walls and communicated by chambers to allow working body flow through all channels of all sections to supersonic nozzle or set of nozzles. |
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Method of measuring energy spectra of polarised slow neutrons Method comprises modulating intensity of a beam of polarised neutrons by transmitting direct current pulses to a foil to form a sharp boundary of the direction of magnetic fields upstream and downstream the foil; simultaneously downstream the foil, exposing the transmitted neutrons to an additional magnetic field to facilitate adiabatic polarisation change by 180 degrees; measuring the time of flight of each modulated neutron over a fixed foil-to-detector distance, from which the velocity or energy of said neutrons is determined. |
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Method of recovery of secondary platinum with radioactive plutonium contamination Invention relates to processing of radioactive wastes and can be used for cleaning of secondary platinum with radioactive plutonium contamination. Proposed method comprises heating of secondary platinum scrap contaminated with plutonium over its entire volume and with metallic impurities in surface layer in amount larger than that of plutonium. Prior to scrap heating, impurities are removed by hydrometallurgy processes, not destructing the platinum surface. Scrap is heated to its fusion with formation of radioactive condensed plutonium oxide and subjected to inductive melting of the platinum to its separation from plutonium oxide. Melting is carried out in the presence of fluxing additives with the formation of melt and slag containing plutonium oxide at melt heel area-to-melt volume ratio of 0.20-0.50, electromagnetic field frequency of 20-66 kHz and air blowing to melt surface at 2049-2073 K for 1.0-1.3 h. Then, slag is removed from platinum. |
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Nuclear power station auxiliaries redundancy At complete blackout, steam generated at steam generator is directed to extra steam turbine plant owing to reactor core residual heat generation. Extra steam turbine plant generates required electric power for supply of the station auxiliaries during time required for recover of the station standard operating conditions. Extra steam turbine plant is connected to heat recovery boiler and to steam distribution device arranged upstream of high-pressure cylinder of the main turbine via pipeline. Steam hydrogen superheater is connected with system for production of hydrogen and oxygen. Equipment incorporated with steam gas plant is located outside the nuclear power station site. |
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Method of dry storage of spent nuclear fuel and device for its implementation Invention relates to dry storage of spent nuclear fuel from reactors LWGR-1000 and WWER-1000, and are intended for use in dry storage of spent nuclear fuel (SNF). The method for the dry storage of SNF provides for the restoration of tightness of bodies instead of decommissioning the storage cells with nonpressurised bodies. The nonpressurised bodies are removed by the refuelling machine from the storage chamber and placed on the roller bearings of the device for tilting the bodies. In the body the places of leak are determined and the defects are eliminated, then using the fuelling machine and the device for tilting the body is converted into the vertical position and place it in its previous place in the storage chamber. The refuelling machine is equipped with an additional electric winch and a removable jib. On the rope the traverse is attached in which centre and on the edges the loading grippers are mounted to install two grips on them. The device for tilting the bodies comprises a trolley with a rocking bar and a clamp and two movable roller bearings connected to a trolley and to each other with the couplers. The lodgements of the movable roller bearings are mounted on the trunnions in the bearings. |
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Carbon-containing formula for radioprotective materials Formula contains 5-16 wt % of ultradisperse active carbon with an average size of particles of 5-100 nm and specific surface are of 16-320 m2/g, a dispersing agent in the form of soda glass aqueous solution and a stabilising agent in the form of a saturated solution of . Finely-dispersed colloidal graphite can be introduced into the formula additionally. The invention uses the formula property to absorb radio-wave electromagnetic radiation at its equal distribution inside the hard matrix of a constructional material or at its application onto the surface of radar absorbent structures or constructional materials. |
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Titanium-based alloy for absorption of heat neutrons Proposed alloy comprises the following elements, in wt %: carbon - 0.03-0.10; iron - 0.15-0.25; silicon - 0.05-0.12; nitrogen - 0.01-0.04; aluminium - 1.8-2.5; zirconium - 2.0-3.0; samarium - 0.5-5.0, titanium and impurities making the rest. |
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Transportation packaging set for transporting radioactive materials Invention relates to atomic engineering, particularly to transportation of highly radioactive materials, including nuclear materials, and can be used in transporting irradiated nuclear fuel by air. The transportation packaging set for transporting radioactive materials includes a protective container with a sealing system. The container, at least its lateral part, is made of layers of ductile radiation-protective materials, wherein the layers are separated from each other by a distance which allows formation of cross-folds in layers when damping emergency impacts on the end faces of the container. |
Another patent 2513515.