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1.发明申请公开(公告)号：US20210358648A1
公开(公告)日：2021-11-18
申请号：US16627741
申请日：2018-12-28
IPC分类号： G21C15/18 , G21C19/04 , G21C17/112
摘要： 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.
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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：US20210210226A1
公开(公告)日：2021-07-08
申请号：US17256578
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： Device for confining nuclear reactor core melt comprising a melt trap, installed in a reactor vessel bottom and provided with a cooled containment, a filler for melt dilution in the multi-layered vessel, an upper support, a bottom support consisting of a horizontal, sectional, solid or split, embedded plate mounted on the multilayer vessel in the concrete of a reactor pit. The plate and melt trap comprise radial supports connected through fasteners. The radial supports and the clamps have oval holes. The upper support comprises lanyards, mounted in pairs on the upper part of the melt trap body so that the longitudinal axis of each radial support of the melt trap bottom support passes in projection at an equispaced distance from the fitting location of the paired lanyards and connecting the melt trap body with the reactor pit vertical wall. The fasteners have hyperbolic-surface-shaped holes.
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公开(公告)号：US20210202118A1
公开(公告)日：2021-07-01
申请号：US17256575
申请日：2018-12-28
发明人： Aleksandr Stalevich SIDOROV , Tatyana Yaropolkovna DZBANOVSKAYA , Mihail Aleksandrovich ROSHCHIN
摘要： System for confining and cooling melt from the core of a water-moderated nuclear reactor comprising a melt trap. The melt trap is installed in the reactor vessel bottom and provided with a cooled containment, consisting of outer and inner housings between which there is a sealant, and the filler for the melt dilution placed in the melt trap inner body. The melt trap inner body has a damper consisting of a central mantle, bearing ribs connected with the central mantle, titled plates, placed between the bearing ribs, the stops providing fastening of the damper to the melt trap body.
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公开(公告)号：US20240055143A1
公开(公告)日：2024-02-15
申请号：US18269673
申请日：2021-12-15
申请人： JOINT-STOCK COMPANY "ATOMENERGOPROEKT" , SCIENCE AND INNOVATIONS - NUCLEAR INDUSTRY SCIENTIFIC DEVELOPMENT, PRIVATE ENTERPRISE
发明人： Aleksandr Stalevich SIDOROV , Nadezhda Vasilievna SIDOROVA , Kristin Aleksandrovich CHIKAN , Kseniya Konstantinovna BADESHKO
摘要： A system for confining and cooling melt from the core of a nuclear reactor comprises a guide device, a cantilever truss, a filler for receiving and distributing melt. The filler being disposed in a housing having water supply valves mounted around its perimeter and having a flange with a thermal shield mounted thereon. A drum is mounted on the flange and comprises reinforcing ribs mounted bearing against a cover and a bottom. The drum comprises tensioning elements connecting the drum, via a support flange, to the flange of the housing, and spacing elements. The drum comprises nozzles having water supply valves mounted therein with sealed covers, and hydraulic dampers connected to external sources of water and to the water supply valves by feed pipes, pressure pipes, compensating pipes and equalizing pipes, for increasing the reliability of the system for confining and cooling melt from the core of a nuclear reactor.
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公开(公告)号：US20170323695A1
公开(公告)日：2017-11-09
申请号：US15536987
申请日：2015-11-16
摘要： The invention relates to safety systems for nuclear power plants (NPP), and can be used during severe accidents leading to reactor vessel and NPP containment failure. The melt cooling and confinement system includes a cone-shaped guide plate installed under the reactor vessel bottom, cantilever girder installed under the guide plate and supporting the same, core catcher installed under the cantilever girder and equipped with cooled cladding in form of a multi-layer vessel for protection of the external heat-exchange wall from dynamic, thermal and chemical impacts, and filler material for melt dilution inside the multi-layer vessel. The said multi-layer vessel has external and internal metal walls with a filler that is highly heat-conductive in relation to wall material in between, where filler material thickness hfil meets the following criterion: 1.2hext
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公开(公告)号：US20170323693A1
公开(公告)日：2017-11-09
申请号：US15536968
申请日：2015-11-16
CPC分类号： G21C9/016 , G21C13/024 , G21C13/10 , G21C15/18 , Y02E30/40
摘要： The invention relates to safety systems for nuclear power plants (NPP), and can be used in the event of reactor vessel and NPP containment failure. The melt cooling and confinement system includes a cone-shaped guide plate installed under the reactor vessel bottom, cantilever girder installed under the guide plate and supporting the same, core catcher installed under the cantilever girder and equipped with cooled cladding in form of a multi-layer vessel for protection of the external heat-exchange wall from dynamic, thermal and chemical impacts, and filler material for melt dilution inside the multi-layer vessel. The said multi-layer vessel contains internal and external metal layers with an intermediate layer in the form of a non-metal filler located in between. Bearing ribs are installed between the internal and external layers at an azimuth pitch (Spitch) that meets the following criterion: dext/15
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公开(公告)号：US20240321470A1
公开(公告)日：2024-09-26
申请号：US18269674
申请日：2021-12-15
申请人： JOINT-STOCK COMPANY "ATOMENERGOPROEKT" , SCIENCE AND INNOVATIONS - NUCLEAR INDUSTRY SCIENTIFIC DEVELOPMENT, PRIVATE ENTERPRISE
发明人： Aleksandr Stalevich SIDOROV , Nadezhda Vasilievna SIDOROVA , Kristin Aleksandrovich CHIKAN , Kseniya Konstantinovna BADESHKO
摘要： A system for confining and cooling melt from the core of a nuclear reactor comprises a guide device, a cantilever truss, a filler for receiving and distributing melt. The filler being disposed in a housing having water supply valves mounted around its perimeter and having a flange with a thermal shield mounted thereon. A drum is mounted on the flange and comprises reinforcing ribs mounted around its perimeter on the inner side. The reinforcing ribs bear against a cover and a bottom. The drum comprises tensioning elements connecting the drum, via a support flange, to the flange of the housing, and spacing elements providing an adjustment gap between the drum and the flange of the housing. The drum comprises nozzles equipped with heat reflectors, cooling ribs, and water supply valves mounted for increasing the reliability of the system for confining and cooling melt from the core of a nuclear reactor.
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公开(公告)号：US20240052939A1
公开(公告)日：2024-02-15
申请号：US18269672
申请日：2021-12-15
申请人： JOINT-STOCK COMPANY "ATOMENERGOPROEKT" , SCIENCE AND INNOVATIONS - NUCLEAR INDUSTRY SCIENTIFIC DEVELOPMENT, PRIVATE ENTERPRISE
发明人： Aleksandr Stalevich SIDOROV , Nadezhda Vasilievna SIDOROVA , Kristin Aleksandrovich CHIKAN , Andrej Borisovich NEDOREZOV
IPC分类号： F16K17/38
CPC分类号： F16K17/383 , G21C15/18
摘要： A water supply valve comprises an actuating sleeve inserted in an intermediate sleeve and bearing on said intermediate sleeve by means of flanged stops, an actuating rod with a piston, said actuating rod being mounted inside the actuating sleeve and the intermediate sleeve so that the actuating rod bears, via the piston, on a thermomechanical element which bears, via a pressure mechanism, on a protective membrane fastened in the end of the actuating sleeve, an actuating spring mounted on the actuating rod so that one end of the spring bears on the piston and the other end bears on the flanged stops of the actuating sleeve, a rolling bearing mounted on the end of the actuating rod which projects from the actuating sleeve, a flanged cylinder in which is inserted a flanged sleeve with a rod-type sleeve mounted therein, the latter receiving a stem with a thread and with a control valve, said stem being rollably mounted, and a thrust sleeve in which are mounted a flanged thrust rod and a working spring, one end of which bears on the flanges of the thrust rod and the other end of which bears on the thrust sleeve, wherein mounted between the control valve and the thrust rod is a ball bearing.
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公开(公告)号：US20230268087A1
公开(公告)日：2023-08-24
申请号：US18024248
申请日：2021-11-09
发明人： Aleksandr Stalevich SIDOROV , Nadezhda Vasilievna SIDOROVA , Tatyana Yaropolkovna DZBANOVSKAYA , Kseniya Konstantinovna BADESHKO
IPC分类号： G21C9/016
CPC分类号： G21C9/016
摘要： Systems for ensuring safety of nuclear power plants (NPPs), and can be used in severe accidents resulting in destruction of the reactor pressure vessel and containment. The systems enhance reliability of the corium localizing and cooling system of a nuclear reactor. The technical result is achieved due to prevention of the corium localizing and cooling system destruction in the junction area between the vessel and the cantilever truss by use of a membrane with bandage plates installed on the drum within the system.
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