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公开(公告)号：EP4246532A1
公开(公告)日：2023-09-20
申请号：EP21892432.2
申请日：2021-11-09
申请人： Joint Stock Company "Atomenergoproekt" , Science and Innovations - Nuclear Industry Scientific Development, Private Enterprise
发明人： SIDOROV, Aleksandr Stalevich , SIDOROVA, Nadezhda Vasilievna , DZBANOVSKAYA, Tatyana Yaropolkovna , BADESHKO, Kseniya Konstantinovna
摘要： The invention relates to the field of nuclear energy, in particular, to the systems 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 technical result of the claimed invention is to enhance reliability of the corium localizing and cooling system of a nuclear reactor.
The objective, which the claimed invention is intended to achieve, is to prevent destruction of the corium localizing and cooling system within the junction area between the vessel for the corium receipt and distribution and the cantilever truss under the conditions on non-axisymmetric corium escape from the reactor pressure vessel and falling of the reactor pressure vessel head fragments into the vessel at the initial stage of the corium cooling with water, and consequently to prevent any ingress of water intended for external cooling of the vessel into the vessel.
The set objective is achieved due to the fact that the corium localizing and cooling system of a nuclear reactor additionally comprises thermal protection suspended to the cantilever truss, the membrane installed between the cantilever truss and the vessel, and the bandage plates installed on the external and internal side of the membrane.-
公开(公告)号：EP3859748A1
公开(公告)日：2021-08-04
申请号：EP18935165.3
申请日：2018-12-28
申请人： Joint Stock Company "Atomenergoproekt" , Science and Innovations - Nuclear Industry Scientific Development, Private Enterprise
发明人： SIDOROV, Aleksandr Stalevich , DZBANOVSKAYA, Tatyana Yaropolkovna , ROSHCHIN, Mihail Aleksandrovich
IPC分类号： G21C9/016
摘要： The invention relates to nuclear engineering, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to the core meltdown, nuclear reactor pressure vessel destruction and the release of the melt into the space of the NPP containment.
The technical result of the claimed invention is to increase the reliability of the device for confining nuclear reactor core melt.
The objects to be solved by the claimed invention are to eliminate the overturning of the melt trap of the device for confining nuclear reactor core melt when exposed to non-axisymmetric shock loads and the melt releases out of the body.
The objects are solved due to the fact that the device for confining nuclear reactor core melt comprising a melt trap, which is installed in the reactor vessel bottom and provided with a cooled containment as the multilayer vessel, a filler for the melt dilution, placed in the specified multi-layered vessel, the upper support, the bottom support consisting of horizontal, sectional, solid or split, embedded plate mounted on a multilayer vessel in the concrete of the reactor pit, according to the invention, the horizontal sectional, solid or split embedded plate comprises radial supports, the melt trap comprising radial supports, based on the radial support of the horizontal sectional, solid or split embedded plate, the radial supports of the horizontal radial section, solid or split embedded plate and the radial supports of the melt trap body are connected through fasteners, while 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 installed tangentially to the melt trap body and connecting the melt trap body with the reactor pit vertical wall, while the fasteners have holes made in the form of hyperbolic surfaces.-
公开(公告)号：EP3905262A2
公开(公告)日：2021-11-03
申请号：EP19902850.7
申请日：2019-12-25
申请人： Joint Stock Company "Atomenergoproekt" , Science and Innovations - Nuclear Industry Scientific Development, Private Enterprise
发明人： SIDOROV, Aleksandr Stalevich , DZBANOVSKAYA, Tatyana Yaropolkovna , SIDOROVA, Nadezhda Vasilievna
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 (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction.
The technical result of the claimed invention is to increase the safety of a nuclear power plant by excluding the release of liquid and solid radioactive materials (corium) outside the device for confining core melt in the event of a severe accident with the core melt discharge out of the nuclear reactor.
The object of the current invention is to improve the efficiency and reliability of the the device for confining core melt by improving the corium cooling conditions.
The set object is solved based on the use of the filler formed in the cassettes, the upper and the lower ones. The cassettes have vertical and horizontal channels that ensure uniform distribution of the melt in the cooled body.-
4.发明公开
公开(公告)号：EP3846179A1
公开(公告)日：2021-07-07
申请号：EP18931944.5
申请日：2018-12-28
申请人： Joint Stock Company "Atomenergoproekt" , Science and Innovations - Nuclear Industry Scientific Development, Private Enterprise
发明人： SIDOROV, Aleksandr Stalevich , DZBANOVSKAYA, Tatyana Yaropolkovna , ROSHCHIN, Mihail Aleksandrovich
IPC分类号： G21C9/016
摘要： The invention relates to nuclear engineering, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to the core meltdown, nuclear reactor pressure vessel destruction and the release of the melt into the space of the NPP containment.
The technical result is the increase of the reliability of the water-cooled water-moderated nuclear reactor core melt cooling and confinement system.
The object to be solved by the claimed invention is to increase the efficiency of heat removal from the melt and increase the structure reliability.
The designated object is solved by using the damper installed inside the melt trap body as part of the water-cooled water-moderated nuclear reactor core melt cooling and confinement system.-
公开(公告)号：EP4273883A1
公开(公告)日：2023-11-08
申请号：EP21915934.0
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： SIDOROV, Aleksandr Stalevich , SIDOROVA, Nadezhda Vasilievna , CHIKAN, Kristin Aleksandrovich , BADESHKO, Kseniya Konstantinovna
IPC分类号： G21C9/016
摘要： The invention relates to systems which provide for the safety of nuclear power plants, and can be used in the event of accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. 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, said 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 mounted on the flange of said housing and being configured in the form of a casing with reinforcing ribs mounted around its perimeter on the inner side, said reinforcing ribs bearing against a cover and a bottom, wherein said drum has tensioning elements connecting the drum, via a support flange welded thereto, to the flange of the housing, and spacing elements. Provided in the drum are 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：EP4246534A1
公开(公告)日：2023-09-20
申请号：EP21892434.8
申请日：2021-11-09
申请人： Joint Stock Company "Atomenergoproekt" , Science and Innovations - Nuclear Industry Scientific Development, Private Enterprise
发明人： SIDOROV, Aleksandr Stalevich , SIDOROVA, Nadezhda Vasilievna , DZBANOVSKAYA, Tatyana Yaropolkovna , BADESHKO, Kseniya Konstantinovna
IPC分类号： G21C9/016
摘要： The invention relates to the field of nuclear energy, in particular, to the systems 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 technical result of the claimed invention is to 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.-
公开(公告)号：EP3236474A1
公开(公告)日：2017-10-25
申请号：EP15870436.1
申请日：2015-11-16
摘要： The invention relates to nuclear power industry, namely to systems providing safety of 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 h fil meets the following criterion: 1.2h ext fil ext , where h ext is vessel external wall thickness. The technical result of the invention is the increased efficiency of heat removal from the melt and improved structural reliability
摘要翻译： 本发明涉及核电工业，即提供核电站（NPP）安全的系统，并且可用于导致反应堆容器的严重事故和NPP遏制故障。 熔体冷却和约束系统包括安装在反应堆容器底部下面的锥形导向板，安装在导向板下面并支撑导向板的悬臂梁，安装在悬臂梁下方并且装有冷却覆层的多臂形式的冷却覆层， 用于保护外部热交换壁免受动态，热和化学冲击，以及用于在多层容器内部进行熔体稀释的填充材料。 所述多层容器具有外部和内部金属壁，所述金属壁具有相对于其间的壁材料高度导热的填料，其中填料厚度hfil满足以下标准：其中hext是 血管外壁厚度。 本发明的技术结果是提高了从熔体除热的效率并改善了结构可靠性
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8.发明公开
公开(公告)号：EP3236473A1
公开(公告)日：2017-10-25
申请号：EP15870435.3
申请日：2015-11-16
摘要： The invention relates to nuclear power industry, namely to systems providing safety of 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 contains external and internal metal walls with filler of poorly heat-conductive in relation to the wall material in between. Filler thickness h fil shall meet the following requirement: 0.8h ext fil ext , where h ext is vessel external wall thickness. The technical result of the invention is the increased efficiency of heat removal from the melt and improved structural reliability.
摘要翻译： 本发明涉及核电工业，即提供核电站（NPP）安全的系统，并且可用于导致反应堆容器的严重事故和NPP遏制故障。 熔体冷却和约束系统包括安装在反应堆容器底部下面的锥形导向板，安装在导向板下面并支撑导向板的悬臂梁，安装在悬臂梁下方并且装有冷却覆层的多臂形式的冷却覆层， 用于保护外部热交换壁免受动态，热和化学冲击，以及用于在多层容器内部进行熔体稀释的填充材料。 所述多层容器包含具有相对于其间的壁材料导热性差的填料的外部和内部金属壁。 填料厚度hfil应符合下列要求：0.8hext
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公开(公告)号：EP4273884A1
公开(公告)日：2023-11-08
申请号：EP21915935.7
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： SIDOROV, Aleksandr Stalevich , SIDOROVA, Nadezhda Vasilievna , CHIKAN, Kristin Aleksandrovich , BADESHKO, Kseniya Konstantinovna
IPC分类号： G21C9/016
摘要： The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. 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, said 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 mounted on the flange of said housing and being configured in the form of a casing with reinforcing ribs mounted around its perimeter on the inner side, said reinforcing ribs bearing against a cover and a bottom, wherein said drum has tensioning elements connecting the drum, via a support flange welded thereto, to the flange of the housing, and spacing elements providing an adjustment gap between the drum and the flange of the housing. Provided in the drum are nozzles equipped with heat reflectors and cooling ribs and having water supply valves mounted therein, 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：EP4273427A1
公开(公告)日：2023-11-08
申请号：EP21915933.2
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： SIDOROV, Aleksandr Stalevich , SIDOROVA, Nadezhda Vasilievna , CHIKAN, Kristin Aleksandrovich , NEDOREZOV, Andrej Borisovich
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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