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公开(公告)号：US11015615B2
公开(公告)日：2021-05-25
申请号：US15741087
申请日：2016-06-20
申请人： JOINT STOCK COMPANY “CENTRAL DESIGN BUREAU OF MACHINE BUILDING” , JOINT STOCK COMPANY “SCIENCE AND INNOVATIONS” (“SCIENCE AND INNOVATIONS”, JSC)
发明人： Vladimir Sergeevich Gerasimov , Andrey Vladimirovich Goronkov , Aleksandr Sergeevich Vasil'ev , Rodion Petrovich Kazantsev , Sergey Yur'evich Shchutskiy
IPC分类号： F04D29/58 , F04D29/047 , F04D13/02 , F04D13/06
摘要： Non-Volume displacement pumps used at nuclear power plants (NPP) in reactor coolant pump sets for the primary coolant circuit of the nuclear power system. The reactor coolant pump set comprising a vertical vane-type single-stage pump with bottom arrangement of the impeller, the pump shaft is connected to the electric motor shaft by a rigid coupling, the radial-axial bearing, installed in the electric motor upper chamber, is made of two main elements: a radial bearing made in the form of a rotor metallic bushing installed on the cylindrical part of the collar and an axial bearing consisting of two stator lever-type balance arm systems with cover plates of antifriction material and rotor cover plates of antifriction material. The radial-axial bearing is cooled by water from the NPP system, pressure head whereof is increased by the screw-type pump located on the upper butt of the radial-axial bearing collar.
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公开(公告)号：US10822241B2
公开(公告)日：2020-11-03
申请号：US16311560
申请日：2018-03-22
发明人： Vladimir Ivanovich Ivanenko , Tat'yana Andreevna Sedneva , Efroim Pinkhusovich Lokshin , Roman Ivanovich Korneikov
摘要： 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.
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公开(公告)号：US10815558B2
公开(公告)日：2020-10-27
申请号：US16065401
申请日：2015-12-22
申请人： STOCK COMPANY “CHEPETSKY MECHANICAL PLANT” (SC CMP) , JOINT STOCK COMPANY “SCIENCE AND INNOVATIONS”
发明人： Andrej Vladimirovich Voloshin , Aleksandr Yevgenyevich Moskalev , Dmitrij Alekseevich Negodin , Dmitrij Valerievich Nikulin , Iurij Panteleevich Samoilov
摘要： The invention relates to the pressure processing of metals, and specifically to methods for preparing rods and workpieces from titanium alloys, with applications as a structural material in nuclear reactor cores, in the chemical and petrochemical industries, and in medicine. The invention solves the problem of producing rods from high-quality titanium alloys while simultaneously ensuring the high efficiency of the process. A method for preparing rods or workpieces from titanium alloys includes the hot forging of an initial workpiece and subsequent hot deformation, the hot forging of an ingot is carried out following heating, with shear deformations primarily in the longitudinal direction and a reduction ratio of k=(1.2−2.5), and then performing hot rolling forging, without cooling, changing the direction of shear deformations to being primarily transverse and with a reduction ratio of up to 7.0, and conducting subsequent hot deformation by heating deformed workpieces.
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公开(公告)号：US20200058413A1
公开(公告)日：2020-02-20
申请号：US16309317
申请日：2017-12-08
申请人： Joint Stock Company "Scientific-research institute of chemical technology" , JOINT STOCK COMPANY "SCIENCE AND INNOVATIONS"
摘要： 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. 3 appendices, 1 diagram, 2 figures
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公开(公告)号：US20190066856A1
公开(公告)日：2019-02-28
申请号：US16081648
申请日：2017-03-29
申请人： JOINT STOCK COMPANY "ROSENERGOATOM" , JOINT STOCK COMPANY "AFRIKANTOV OKB MECHANICAL ENGINEERING" , JOINT STOCK COMPANY "SCIENCE AND INNOVATIONS"
发明人： Yuriy Vladimirovich VORONIN , Sergey Sergeevich RUSAKOV , Mikhail Anatol'evich LYUBIMOV , Aleksandr Vladimirovich TIMOFEEV
IPC分类号： G21C19/10
摘要： The inclined hoist of a nuclear reactor comprising a trolley 1 with a sleeve 2 for SFA, which moves along a rail track 3 in an inclined corridor 4 by means of a cable 8. At the entry into the inclined corridor 4, a guide block is installed, equipped with an asymmetric channel for routing the cable and installed at an angle β relative to the track, satisfying the condition: tgβ=t/πD where β is an angle of inclination of the guide block to the track; t is a pitch of cable grooves on the drum; D is a diameter of the drum, wherein the guide block channel symmetry axis is located along the cable movement trajectory.
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公开(公告)号：US20180195925A1
公开(公告)日：2018-07-12
申请号：US15579464
申请日：2016-05-25
发明人： Boris Alekseevich POSTNIKOV , Zinaida Semyonovna KAZACHKOVA , Yevgeniy Borisovich MISHIN , Yelena Aleksandrovna NIKITINA
摘要： The sphere of main pipelines used for hot water supply, specifically devices for electric surveillance control and water heat carrier leakage detection on atomic electric power station pipelines applied for operation of heat insulated pipes with a protective casing. Such pipeline leakage detection device uses a metal protective casing installed coaxially on a metal pipe with a radial clearance, where the casing performs as a joint of, for example, four arch shaped metal sheets bent across the pipe. Sheets straight line edges are joined by a dielectric washer, and sheets arch shaped edges are joined by a dielectric ring. Ring flanks have ring grooves on them for sheets arch shaped edges installation. Across each sheet arch shaped edge there are lamels shaped electric connectors installed in ring grooves for sheet arch shaped edge fixation. Electric connector terminals are fastened on the ring external surface and separately connected to each lamel.
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公开(公告)号：US11773998B2
公开(公告)日：2023-10-03
申请号：US16081639
申请日：2017-10-24
申请人： Joint-Stock Company Engineering company ASE , Joint Stock company ATOMENERGOPROEKT , Joint Stock Company «Science and Innovations»
CPC分类号： F16K17/40 , F16K17/00 , F16K17/383
摘要： The single-action emergency thermal valve comprises a body with a through channel for coolant supply through its inlet in the direction of its outlet, and a fuse link in the through channel of the body; the fuse link consists of at least two parts, each of the two parts completely overlaps the section of the through channel, the parts are made of materials with different melting points, and are located in the through channel in series with the increase of the melting temperature of each successive part in the direction from the through channel inlet to its outlet, wherein the body can have transverse ribs and/or transverse ridges at the location of the fuse link.
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公开(公告)号：US11610693B2
公开(公告)日：2023-03-21
申请号：US16627744
申请日：2018-12-28
发明人： Aleksandr Stalevich Sidorov , Tatyana Yaropolkovna Dzbanovskaya , Mihail Aleksandrovich Roshchin
IPC分类号： G21C9/016
摘要： 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.-
公开(公告)号：US20210296013A1
公开(公告)日：2021-09-23
申请号：US16627744
申请日：2018-12-28
发明人： Aleksandr Stalevich SIDOROV , Tatyana YAropolkovna DZBANOVSKAYA , Mihail Aleksandrovich ROSHCHIN
IPC分类号： G21C9/016
摘要： 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.-
公开(公告)号：US20210272715A1
公开(公告)日：2021-09-02
申请号：US17257275
申请日：2019-11-14
申请人： JOINT STOCK COMPANY "ROSENERGOATOM" , LIMITED LIABILITY COMPANY "INTRO-MICRO" , JOINT STOCK COMPANY "SCIENCE AND INNOVATIONS"
摘要： 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.
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