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公开(公告)号：US12159724B2
公开(公告)日：2024-12-03
申请号：US17443994
申请日：2021-07-29
Inventor： Franck Morin , Gilles Avakian
Abstract: A PWR includes a secondary circuit that is normally fluidly isolated from the primary circuit. The secondary circuit includes secondary fluid in a steam generator. In response to detection of a core melt, the secondary circuit is placed in fluidic communication with the primary circuit, so that secondary fluid from the steam generator can flow into the primary circuit and then into the reactor vessel.
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公开(公告)号：US20230343476A1
公开(公告)日：2023-10-26
申请号：US18024246
申请日：2021-11-09
Applicant: JOINT-STOCK COMPANY "ATOMENERGOPROEKT"
Inventor： Aleksandr Stalevich SIDOROV , Nadezhda Vasilievna SIDOROVA , Tatyana Yaropolkovna DZBANOVSKAYA , Kseniya Konstantinovna BADESHKO
Abstract: Systems for ensuring safety of nuclear power plants (NPPs). The systems enhance reliability of the corium localizing and cooling system of a nuclear reactor. The corium localizing and cooling system comprise 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. The systems 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.
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公开(公告)号：US20230268086A1
公开(公告)日：2023-08-24
申请号：US18024247
申请日：2021-11-09
Applicant: JOINT-STOCK COMPANY "ATOMENERGOPROEKT"
Inventor： Aleksandr Stalevich SIDOROV , Nadezhda Vasilievna SIDOROVA , Tatyana Yaropolkovna DZBANOVSKAYA , Kseniya Konstantinovna BADEZHKO
IPC: G21C9/016
CPC classification number: G21C9/016
Abstract: Systems ensuring safety of nuclear power plants (NPPs) 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 use of the membrane installed between the cantilever truss and the vessel, bandage plates installed on the external and internal side of the membrane, the hydraulic gas-dynamic damper installed on the internal side of the membrane in the corium localizing and cooling system of a nuclear reactor enabling to prevent any destruction within the leak-tight junction area between the multi-layered vessel and the cantilever truss under the conditions with non-axisymmetric corium flow from the reactor pressure vessel and falling of reactor pressure vessel head fragments into the vessel at the initial stage of the corium cooling with water.
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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
Inventor： Aleksandr Stalevich Sidorov , Tatyana Yaropolkovna Dzbanovskaya , Mihail Aleksandrovich Roshchin
IPC: G21C9/016
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.-
5.发明申请公开(公告)号：US20220157478A1
公开(公告)日：2022-05-19
申请号：US17665719
申请日：2022-02-07
Inventor： Yifeng Wang , David Louie , Rekha R. Rao , Jeremy A. Templeton
Abstract: Systems and methods for injecting a carbonate-based sacrificial material into a nuclear reactor containment for containment of molten corium in severe nuclear reactor accidents are disclosed. Molten corium can be quickly cooled and solidified by the endothermic decomposition of the sacrificial material.
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Patent Agency Ranking
公开(公告)号：US20210296013A1
公开(公告)日：2021-09-23
申请号：US16627744
申请日：2018-12-28
Inventor： Aleksandr Stalevich SIDOROV , Tatyana YAropolkovna DZBANOVSKAYA , Mihail Aleksandrovich ROSHCHIN
IPC: G21C9/016
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.-
公开(公告)号：US20210272710A1
公开(公告)日：2021-09-02
申请号：US17257276
申请日：2019-12-25
Applicant: JOINT-STOCK COMPANY "ATOMENERGOPROEKT"
Inventor： Aleksandr Stalevich SIDOROV , Tatyana Yaropolkovna DZBANOVSKAYA , Nadezhda Vasilievna SIDOROVA
Abstract: Systems in the field of nuclear energy, in particular, 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. In one aspect, the system can increase the safety of a nuclear power plant by excluding the release of liquid and solid radioactive materials (corium) outside the device to confine core melt in the event of a severe accident with core melt discharge out of the nuclear reactor. In a second aspect, the efficiency and reliability of the device for confining core melt can be improved by improving the corium cooling conditions. This can be achieved by the use of filler formed in upper and lower cassettes having vertical and horizontal channels that ensure uniform distribution of the melt in the cooled body.
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公开(公告)号：US10991469B2
公开(公告)日：2021-04-27
申请号：US16299330
申请日：2019-03-12
Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE
Inventor： Sung-Jae Yi , Hyun Sik Park , Rae-Joon Park , Ki Yong Choi , Kwang Soon Ha , Seong-Wan Hong
Abstract: There is provided a cooling apparatus for a molten core material, including: two or more cooling material containers disposed under a reactor vessel including a nuclear reactor core and including a cooling material therein; a first screen disposed under the two or more cooling material containers and including two or more first through-holes; and a second screen disposed under the first screen and including two or more second through-holes, wherein an average size of the two or more first through-holes is greater than an average size of the two or more second through-holes.
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公开(公告)号：US10825571B2
公开(公告)日：2020-11-03
申请号：US15675850
申请日：2017-08-14
Applicant: BWXT mPower, Inc.
Inventor： Tyler A. Edwards , Michael J. Edwards
IPC: G21C13/024 , G21C9/016 , G21C5/10 , G21C15/18
Abstract: A nuclear island includes a nuclear reactor, a lateral seismic restraint, and a reactor core retention cooling system. The lateral seismic restraint includes a vertically oriented pin attached to one of the bottom of the lower vessel head and the floor underneath the nuclear reactor, and a mating pin socket is attached to the other of the bottom of the lower vessel head and the floor. The reactor core retention cooling system includes one or more baffles, optionally thermally insulating material, disposed alongside the exterior surface of a lower portion of the reactor pressure vessel including at least the lower vessel head. A plenum is defined between the one or more baffles and the exterior surface of a lower portion of the reactor pressure vessel. The one or more baffles may define a lower plenum inlet surrounding the lateral seismic restraint.
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公开(公告)号：US10741294B2
公开(公告)日：2020-08-11
申请号：US15323416
申请日：2015-06-30
Applicant: RETECH CO., LTD.
Inventor： Ho Je Seong
Abstract: The present invention provides a porous cooling block for cooling corium, comprising: a base part that includes a plurality of pores; a plurality of porous cooling blocks that include a channel part that communicates with some of the plurality of pores of the base part; a sacrificial part that covers the exposed upper surfaces of the porous cooling blocks; and a cooling-water supply unit that supplies cooling water to the porous cooling blocks. Corium is cooled by using steam or cooling water discharged from the porous cooling blocks. Therefore, the corium can be cooled and solidified in the shape of a porous form. Further, the cooling water is uniformly supplied to one surface formed by the cooling block on the whole, thereby easily cooling the corium.
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