WO2020139160A2 - Устройство локализации расплава - Google Patents
Устройство локализации расплава Download PDFInfo
- Publication number
- WO2020139160A2 WO2020139160A2 PCT/RU2019/001015 RU2019001015W WO2020139160A2 WO 2020139160 A2 WO2020139160 A2 WO 2020139160A2 RU 2019001015 W RU2019001015 W RU 2019001015W WO 2020139160 A2 WO2020139160 A2 WO 2020139160A2
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- melt
- channels
- vertical
- central
- peripheral
- Prior art date
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/016—Core catchers
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/10—Means for preventing contamination in the event of leakage, e.g. double wall
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- 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 leading to the destruction of the reactor vessel and its hermetic shell.
- NPPs nuclear power plants
- the greatest radiation hazard is accidents with core melting, which can occur during multiple failure of core cooling systems.
- a device [1] for localization and cooling of the corium of an emergency water-type nuclear reactor containing a cooled trap located in the subreactor space, a protective truss located under the bottom of the reactor, and a console located above the shaft above the trap, sacrificial materials are placed in the trap - diluents of uranium-containing oxide and steel constituents of the corium melt, formed into cassettes, which are arranged in blocks.
- the disadvantage of this device is the insufficiently effective cooling of the melt associated with a divided (cellular) installation of ceramic elements, in which, when the corium of the steel frame is destroyed by the melt, ceramic elements, as lighter, float in the corium melt and practically do not interact with its oxide component passing into slag, which can lead to the release of liquid and solid radioactive materials (corium) outside the melt localization device.
- a device [2] for localization and cooling of the corium of a nuclear reactor located in the subreactor space of a concrete mine, including a vessel cooled by water in the form of a vessel, the bottom of which is deepened to the center with a slope of 10-20 degrees, and the bottom thickness is not less than 30% more than the thickness the side wall of the case, while in the case there are briquettes of the diluent material of the uranium oxide corium bound by cement and placed in steel blocks placed in several horizontal layers, the bottom of the lower block is identical in shape to the bottom of the case, the blocks above it have a central hole, and the attachment points of the blocks to the body and between each other are placed in vertical slots of the blocks, and the slots and, partially, the blocks are filled with concrete.
- a device [3] for the localization of the melt comprising a cooled case with a double wall, filled with filler arranged in blocks, each of which is divided into segments by attachment points mounted radially relative to the vertical axis of the device, while filling the segments with filler the formation of free zones in communication with the Central through hole for the passage of the melt.
- the disadvantage of this device is the insufficient cooling of the melt associated with a divided (cellular) installation of ceramic elements, in which, when the corium of the steel frame is destroyed by the melt, the ceramic elements, as lighter, float in the corium melt and practically do not interact with its oxide component passing into slag, which can lead to the release of liquid and solid radioactive materials (corium) outside the melt localization device.
- the technical result of the claimed invention is to increase the safety of a nuclear power plant by eliminating the release of liquid and solid radioactive materials (corium) beyond the melt localization device in the event of a severe accident with the core melt leaving the nuclear reactor.
- the problem to which the invention is directed is to increase the efficiency and reliability of the melt localization device by improving the conditions for cooling the corium.
- the filler consists of several upper and lower cassettes, each of which has one central and several peripheral vertical channels drives, the diameter of the central vertical storage channel exceeds the equal diameters of the vertical peripheral storage channels, the horizontal radial distribution channels connecting the vertical peripheral storage channels to the central vertical storage channel, while the horizontal radial distribution channels of the lower cassette are made with a slope, the angle which coincides with the slope of the bottom of the melt trap body, horizontal azimuth distribution channels connecting the vertical peripheral storage channels of the upper cassettes to each other, with horizontal radial and azimuth distribution channels dividers have equal diameters, with the upper and lower cassettes containing ceramic plates made with microchannels separated by horizontal and vertical slotted channels, and mounted on top of each other so that
- each peripheral vertical storage channel is located on the same axial axis with the corresponding radial rib of the cooled case.
- the depth of the central vertical channel exceeds the depth of the peripheral vertical storage channels.
- a damper is installed in the central vertical storage channel, consisting of a central shell, power ribs connected to the central shell, inclined plates located between power ribs, clamps, providing fastening of a damper to the cooled case.
- the filler consists of several upper and lower cassettes, each of which has one central and several peripheral vertical storage channels, the diameter of the central vertical channel exceeds the equal diameters of the vertical peripheral storage channels, horizontal radial channels distributors connecting the vertical peripheral storage channels to the central vertical storage channel, while the horizontal radial distribution channels of the lower cassette are made with a slope, the angle of which coincides with the slope of the bottom of the melt trap body, horizontal azimuthal distribution channels connecting the vertical peripheral storage channels the upper cassettes with each other, while the horizontal radial and azimuthal channels have equal diameters, ceramic plates in the upper and lower cassettes, made with microchannels and divided among themselves horizontal and vertical slotted channels, with all the cassettes mounted on top of each other so that the contours of their vertical central and peripheral storage channels coincide with each other.
- each peripheral vertical storage channel is located on the same axial axis with the corresponding radial rib of the cooled case.
- Another distinguishing feature of the claimed invention is that the depth of the central vertical storage channel exceeds the depth of the peripheral vertical storage channels.
- a damper is installed in the central vertical storage channel, consisting of a central shell, power ribs connected to the central shell, inclined plates located between the power ribs, clamps, which ensure the damper is attached to the cooled case.
- the central and peripheral vertical storage channels provide simultaneous reception of large masses of the core melt, as well as the distribution of the melt over the volume of the entire filler during overflow of individual storage channels, which usually occurs during non-axisymmetric outflow of the core melt from the reactor vessel;
- the central and peripheral vertical storage channels provide protection of the upstream structures from thermal radiation from the side of superheated steel at the initial stage of receipt of the core melt from the reactor vessel into the filler, since they do not allow the upper part of the trap body to be heated by direct thermal radiation (practically block the direct lumbar), and ensure that heat is retained in the liquid steel entering the filler during the two-stage process of the outflow of the core melt from the reactor vessel, in which at the initial stage of the destruction of the reactor vessel mainly superheated steel with a small amount of liquid oxides flows from it, then from 30 minutes to 3-4 hours, the main volume of liquid oxides containing a certain amount of liquid case steel flows from the reactor vessel;
- the central and peripheral vertical storage channels provide effective conditions for ensuring the operation of slotted channels in full, since the vertical arrangement of the storage channels provides mainly a vertical boundary separation upon contact of the core melt with ceramic elements, and the resulting water vapor is evacuated through slotted channels, interacting weakly with the core melt;
- these horizontal distribution channels provide a link between the central and peripheral vertical storage channels, and, therefore, the azimuthal redistribution of the melt between them, which makes it possible to efficiently equalize the melt level between the vertical storage channels with non-axisymmetric flow of the core melt from the reactor vessel, preventing overflow of the melt over their edges.
- these horizontal distribution channels make it possible to avoid overfilling of individual vertical storage channels, to ensure that the mass of the incoming melt is aligned with the volume of the filler, thereby equalizing the thermomechanical load on the filler, and, ultimately, ensure uniform heating of the melt trap body along the entire perimeter and height .
- the low melt level in the storage channels allows the filler to be used as a passive protection from the effects of thermal radiation on the structural elements of the melt trap, truss-console and guide plate in the early stages of the expiration of the core melt from the reactor vessel.
- the liquid metal melt, flowing out of the reactor vessel in a salvo mode is completely located in the lower part of the filler, not being able to form a single open radiating surface;
- microchannels located inside the ceramic elements formed during sintering provide the specified kinetics of interaction with the core melt.
- Figure 1 presents a General view of the device for localization of the melt with a filler made in accordance with the claimed invention.
- Figure 2 presents a view in section of the filler, which is made of the vertical Central and peripheral channels, drives, as well as horizontal radial and azimuthal distribution channels.
- Fig. 3 shows an enlarged view of the filler in which slotted channels and microchannels are made.
- Figure 4 presents a General view of the damper.
- the claimed invention works as follows.
- the claimed device for localization of the melt (hereinafter - ULR) is a crucible type device located in the subreactor space of a concrete mine.
- the melt localization device (1) comprises a cooled case (2), which is a steel multilayer vessel mounted on a support fixed to a concrete slab (3) of the shaft
- the ULR support (1) is made in the form of several radial bearings (5) connected to the embedded plate (6) installed in the concrete slab (3) of the shaft (4) by means of various fastening devices (for example, studs, bolts pins).
- various fastening devices for example, studs, bolts pins.
- the response ribs (7) of the body (2) of the HRM (1) are installed, while the vertical planes passing along the axis of symmetry of each rib (5) of the support and the response ribs (7) of the body (2) of the HRM (1) are symmetry planes of peripheral vertical storage channels.
- the housing (2) is designed to receive and place corium melt (8) in its volume, as well as to prevent it from going beyond the established boundaries of the localization zone.
- Corium consists of two main components: oxide (the main components of which are a mixture of oxides of uranium, zirconium, iron with a small amount of metals) and metal (the main components of which are a mixture of iron, zirconium with a certain amount of oxides of uranium, zirconium, iron).
- the housing (2) is filled with a filler, namely, a sacrificial material made of a steel composition and relatively light and fusible oxides, which, in accordance with the claimed invention, are made in the form of elements arranged in cassettes mounted on top of each other along the vertical axis of the housing (2).
- a filler namely, a sacrificial material made of a steel composition and relatively light and fusible oxides, which, in accordance with the claimed invention, are made in the form of elements arranged in cassettes mounted on top of each other along the vertical axis of the housing (2).
- the filler ensures subcriticality of the corium within the established boundaries of the localization zone for any configuration of oxide corium and any water-uranium ratio with pure unborated water.
- the filler incorporates absorbing materials co-crystallizing with uranium and plutonium oxides.
- sacrificial ceramic materials based on iron oxide BeO3 (hematite) and aluminum oxide AI 2 O 3 can be used.
- Hematite actively interacts with the oxide part of corium and molten zirconium from its metal component, but slowly with molten iron and chromium metal component of corium.
- the filler cassettes are divided into two groups according to the shape of the peripheral storage channels: upper cassettes (9), characterized by profiling along the height of the casing from each other (for example, cylindrical and torus cassettes), and the lower cassette (10).
- the housing (2) is made with internal radial bearings (11), on which the lower filler cassette (10) is mounted.
- the lower cassette (10) has a vertical central storage channel
- the peripheral storage channels (13) are made with a slope, the angle of which coincides with the angle of inclination of the bottom of the body (2) of the melt trap.
- the upper cassettes (9) are installed on the lower cassette (10).
- Each upper filler cassette (9) has a vertical central storage channel (14) and several vertical peripheral storage channels (15).
- the vertical central and peripheral storage channels (14, 15) are interconnected by horizontal radial distribution channels (16).
- the upper cassettes (9) have horizontal azimuth distribution channels (17) connecting the vertical peripheral storage channels (15) with the vertical central storage channel (14).
- the diameter of the vertical central storage channel (14) exceeds the diameter of the vertical peripheral storage channels (15).
- the vertical central storage channels (14) and the peripheral storage channels (15) for each of the upper cassettes (9) have the same dimensions, respectively.
- the horizontal radial and azimuth distribution channels (16, 17) of the upper cassettes (9) also have the same dimensions.
- Fig. 3, 5 shows a filler in which slotted channels (18) and microchannels (19) are made.
- the slotted channels (18) separating the ceramic elements (20) of the filler are initially filled with a binder to ensure the monolithicity of the filler cassettes.
- the binder In the process of heating the contact zone of the melt and the filler, the process of physico-chemical interaction at the contact boundary begins, and the binder, as the temperature rises, begins to degrade, losing water.
- the vapor released from the collapsing binder moves mainly along the vertical slotted peripheral channels (18), bypassing the zones blocked by the melt (8).
- Microchannels (19) located inside the ceramic elements (20) formed during sintering provide the specified kinetics of interaction with the core melt (8), that is, they determine the rate of interaction of the melt (8) with hematite and aluminum oxide at the boundary of the ceramic element (20) ), on which, ultimately, depends energy balance of the corium melt bath, zirconium oxidation rate and the release of unreacted oxygen to the corium melt bath.
- a damper (21) is installed inside the central vertical storage channel (14), designed to distribute the melt flows (8) in different radial directions.
- the damper (21) shown in Fig. 4 consists of a central shell (22), power ribs (23) connected to the central shell (22), inclined plates (24) located between the power ribs (23), latches (25 ) securing the damper (21) to the ULR housing (1).
- Inclined plates (24) of the damper (21) located between the power ribs (23) are installed from 1 to 5 pieces, parallel to each other in each segment between the power ribs (23).
- the number of inclined plates (24) of more than 5 does not give an additional redistributing effect due to the fact that the thickness of the inclined plates (24) must be reduced to provide the necessary angle of inclination of the plates (24), which ensures the deviation of superheated jets of the core melt towards the filler.
- the number of radial bearings (11) inside the housing (2) of the HRM (1) is set in the range from 3 to 10 pieces.
- the number of radial bearings (11) of less than 3 does not provide effective work on the absorption of the kinetic energy of the impact, since in this case the impact zone is not redistributed along the bottom of the body (2), but is concentrated in its local areas, which can lead to its destruction.
- the number of radial bearings (11) of more than 10 does not increase the redistributing effect, requires a decrease in the thickness of the power ribs (23), which negatively affects their ability to absorb and redistribute the kinetic energy of the impact from falling debris of the bottom of the reactor vessel and absorb the energy of the jets of the melt of the active zone when the melt flows from the reactor vessel.
- Redistribution of energy occurs during the first volley entry of a large volume of the melt (8), which contains mainly liquid superheated steel, due to the hydromechanical deflection of the molten metal by the damper planes (21) towards the horizontal radial distribution channels (16), which, in turn, , provide redistribution of the melt (8) between the vertical storage channels (14, 15).
- the orientation and angle of inclination of the plates (24) of the damper (21) are selected so that the melt jets deviate from the central to the end surfaces of the upper cassettes through which the horizontal radial and azimuth distribution channels (16, 17) pass.
- the survivability of the damper (21) is of the order of 10 s, but this time is sufficient to limit the first impact of molten superheated steel into the lower cassette (10) until a safe melt level is formed above it and redirect part of the kinetic energy of the melt to the upper cassettes (9), flowing out of which the melt increases its level above the lower cassette (10), protecting it from subsequent direct exposure to the kinetic energy of the melt jets and flying objects.
- the filler In the process of volley inflow of superheated steel during axisymmetric or non-axisymmetric incidence of the melt jets, the filler partially fills and enters not only the central vertical storage channel (14), but also the peripheral vertical storage channels (15) of the upper cartridges (10).
- the damper (21) performs the function of a hydrodynamic damper, providing a directed collision of the melt jets horizontally flowing from the peripheral vertical storage channels (15) into the vertical central storage channel (14) through the horizontal radial distribution channels (16), with vertical melt jets moving in the vertical central storage channel (14) and deflected by inclined plates (24) of the damper (21) in the radial direction towards the horizontal radial distribution channels (16).
- the central and peripheral vertical storage channels (12, 13) of the lower cassette (10) are designed in such a way that the corium melt entering the peripheral vertical storage channels (13) of the lower cassette (10) from the cassettes located above (9) flows down inclined peripheral storage channels (13) of the lower cassette (10) into its central vertical storage channel (12), forming a melt level above the ceramic elements (20) of the lower cassette (10) located at its base.
- Thickness of installed ceramic elements (20) located in the base and on the side the conical surface of the lower cassette (10), is selected in such a way as to provide preheating of the conical bottom of the housing (2) ULR (1), having a greater thickness than its cylindrical part, to align the temperature fields of the housing (2) ULR (1) to the moment receipt of the oxide (energy-releasing) part of the corium melt in the filler.
- Inclined peripheral vertical storage channels (13) of the lower cassette (10) provide uniform heating of the conical part of the bottom of the housing (2) of the HRM (1), and the base of the housing (2) of the HRM (1) is heated from the base of the central vertical storage channel (12) ) lower cassette (10), for which it is made somewhat deeper than the inclined vertical peripheral peripheral storage channels (13) located around.
- the melt level (8) formed in the central vertical storage channel (12) of the lower cassette (10) protects the base of the lower cassette (10) and the conical bottom of the casing (2) of the HRM (1) from impact from the core fragments and debris the bottom of the reactor vessel, the fall of which, with a different configuration of the central filler channel, could lead to damage to both the thermal protection of the conical bottom of the vessel (2) ULR (1) provided by ceramic elements (20) of the lower cassette (10), and the conical bottom itself.
- ULR (1) has the following advantages: the filler becomes homogeneous. In this case, the processes of interaction of the melt with the filler elements that occur under different conditions are excluded: the melt is ceramic elements on a cement binder and the melt is monolithic concrete.
- the heating of the conical bottom of the casing (2) of the ULR (1) cannot be synchronized with the heating of the cylindrical and torus parts of the casing (2), while the risks of local thermal shock effects of the melt on case (2) ULR (1) with a possible loss of strength due to various thermomechanical loads of the case (2): on the bottom side, heat transfer is blocked by concrete, and on the side of the torus and cylindrical parts of the case (2) ULR (1), the heating process is determined by the interaction rate ceramic elements (20) with a core melt, i.e., microporosity of ceramic elements (20) and processes occurring in slotted channels (19).
- the thickness of the conical torus and cylindrical parts of the body (2) of the HRM (1) is different, the problem of leveling the temperature fields of the body (2) of the HRM (1) is crucial in the process of maintaining the body's strength and resistance to other types of influences.
- a filler made in accordance with the claimed invention in the form of a monolithic structure having vertical central and peripheral channels, as well as horizontal channels formed by vertical central and peripheral storage channels and horizontal distribution channels in cassettes mounted on top of each other , made it possible to increase the reliability of the melt localization device by ensuring the energy distribution of the fragments of the reactor vessel and the core melt between different types of channels in the filler, by providing reliable protection of the melt trap body from overheating in the initial period of the volley flow of the core melt from the reactor body into the melt trap body, which, in turn, allows minimizing the formation of hydrogen during the interaction of the melt with steam in the filler during the interaction of the melt with a binder.
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
Claims
Priority Applications (7)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2020573142A JP7337860B2 (ja) | 2018-12-26 | 2019-12-25 | 溶融物閉込装置 |
BR112020026841A BR112020026841A2 (pt) | 2018-12-26 | 2019-12-25 | Dispositivo de confinamento de derretimento |
EP19902850.7A EP3905262A2 (en) | 2018-12-26 | 2019-12-25 | Melt confinement device |
CN201980043444.4A CN113039615A (zh) | 2018-12-26 | 2019-12-25 | 熔化物定域装置 |
CA3105182A CA3105182A1 (en) | 2018-12-26 | 2019-12-25 | Melt confinement device |
US17/257,276 US11521759B2 (en) | 2018-12-26 | 2019-12-25 | Melt confinement device |
KR1020207037557A KR20210108871A (ko) | 2018-12-26 | 2019-12-25 | 노심 용융물 국소화 장치 |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RU2018146642A RU2696612C1 (ru) | 2018-12-26 | 2018-12-26 | Устройство локализации расплава |
RU2018146642 | 2018-12-26 |
Publications (2)
Publication Number | Publication Date |
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WO2020139160A2 true WO2020139160A2 (ru) | 2020-07-02 |
WO2020139160A3 WO2020139160A3 (ru) | 2020-08-20 |
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Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
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PCT/RU2019/001015 WO2020139160A2 (ru) | 2018-12-26 | 2019-12-25 | Устройство локализации расплава |
Country Status (9)
Country | Link |
---|---|
US (1) | US11521759B2 (ru) |
EP (1) | EP3905262A2 (ru) |
JP (1) | JP7337860B2 (ru) |
KR (1) | KR20210108871A (ru) |
CN (1) | CN113039615A (ru) |
BR (1) | BR112020026841A2 (ru) |
CA (1) | CA3105182A1 (ru) |
RU (1) | RU2696612C1 (ru) |
WO (1) | WO2020139160A2 (ru) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP7490897B2 (ja) | 2020-12-29 | 2024-05-27 | ジョイント ストック カンパニー アトムエネルゴプロエクト | 原子炉の炉心からの溶融物を封じ込めて冷却するシステム |
Families Citing this family (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU2726226C1 (ru) * | 2019-12-30 | 2020-07-10 | Акционерное Общество "Научно-Исследовательский И Проектно-Конструкторский Институт Энергетических Технологий "Атомпроект" | Система удержания расплава в корпусе реактора |
RU2734734C1 (ru) * | 2020-03-13 | 2020-10-22 | Акционерное Общество "Атомэнергопроект" | Направляющее устройство системы локализации и охлаждения расплава активной зоны ядерного реактора |
RU2742583C1 (ru) * | 2020-03-18 | 2021-02-08 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
RU2736544C1 (ru) * | 2020-03-20 | 2020-11-18 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
RU2736545C1 (ru) * | 2020-03-20 | 2020-11-18 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
WO2024012675A1 (en) * | 2022-07-13 | 2024-01-18 | Framatome Gmbh | Nuclear power plant comprising a core catcher |
Family Cites Families (19)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3702802A (en) * | 1971-06-16 | 1972-11-14 | Atomic Energy Commission | Nuclear reactor incorporating means for preventing molten fuel from breaching the containment vessel thereof in the event of a core meltdown |
US4045284A (en) * | 1975-03-10 | 1977-08-30 | Rosewell Michael P | Nuclear reactor fuel containment safety structure |
US4036688A (en) * | 1975-04-09 | 1977-07-19 | The United States Of America As Represented By The United States Energy Research And Development Administration | Apparatus for controlling molten core debris |
FR2395567A1 (fr) * | 1977-06-23 | 1979-01-19 | Commissariat Energie Atomique | Dispositif recuperateur de coeur pour reacteur nucleaire a neutrons rapides |
US4442065A (en) * | 1980-12-01 | 1984-04-10 | R & D Associates | Retrofittable nuclear reactor core catcher |
RU2050022C1 (ru) * | 1988-07-26 | 1995-12-10 | Опытное Конструкторское Бюро "Гидропресс" | Устройство для улавливания и аварийного охлаждения расплава активной зоны ядерного реактора |
DE4041295A1 (de) * | 1990-12-21 | 1992-07-02 | Siemens Ag | Kernreaktor-anlage, insbesondere fuer leichtwasserreaktoren, mit einer kernrueckhaltevorrichtung, verfahren zur notkuehlung bei einer solchen kernreaktor-anlage und verwendung turbulenzerzeugender deltafluegel |
DE4322107A1 (de) * | 1993-07-02 | 1995-01-12 | Siemens Ag | Einrichtung zum Auffangen und Kühlen von Kernschmelze |
WO1998025273A1 (de) * | 1996-12-05 | 1998-06-11 | Siemens Aktiengesellschaft | Behälter zur aufnahme und ausbreitung von kernschmelze sowie kernkraftanlage mit einem solchen behälter |
RU2253914C2 (ru) * | 2003-08-18 | 2005-06-10 | Хабенский Владимир Бенцианович | Система локализации и охлаждения кориума аварийного ядерного реактора водо-водяного типа |
WO2007099698A1 (ja) * | 2006-02-22 | 2007-09-07 | Kabushiki Kaisha Toshiba | コアキャッチャーおよびその製造方法、並びに、原子炉格納容器およびその改造方法 |
US9368238B2 (en) * | 2009-12-17 | 2016-06-14 | Ge-Hitachi Nuclear Energy Americas Llc | Nuclear reactor melt arrest and coolability device |
RU100327U1 (ru) * | 2010-06-17 | 2010-12-10 | Открытое акционерное общество "Санкт-Петербургский научно-исследовательский и проектно-конструкторский институт "АТОМЭНЕРГОПРОЕКТ" (ОАО "СПбАЭП") | Устройство локализации расплава |
RU100328U1 (ru) * | 2010-06-17 | 2010-12-10 | Открытое акционерное общество "Санкт-Петербургский научно-исследовательский и проектно-конструкторский институт "АТОМЭНЕРГОПРОЕКТ" (ОАО "СПбАЭП) | Система пассивного отвода тепла от теплообменника устройства локализации расплава |
US9911514B2 (en) * | 2014-06-09 | 2018-03-06 | Bwxt Mpower, Inc. | Nuclear reactor cavity floor passive heat removal system |
KR101606872B1 (ko) | 2014-07-04 | 2016-03-28 | 주식회사 아리텍 | 노심 용융물 냉각용 다공성 냉각블록 및 이를 구비하는 노심 용융물 냉각장치 및 이들을 이용한 노심 용융물 냉각방법 |
JP6320271B2 (ja) | 2014-10-14 | 2018-05-09 | 株式会社東芝 | 炉心溶融物保持装置及び原子力施設 |
MY196713A (en) | 2014-12-16 | 2023-05-02 | Joint Stock Company Atomenergoproekt | Water-cooled water-moderated nuclear reactor core melt cooling and confinement system |
CN105551538B (zh) | 2015-12-10 | 2020-04-03 | 中国核电工程有限公司 | 具有引导熔融物分层扩展功能的堆芯熔融物捕集器 |
-
2018
- 2018-12-26 RU RU2018146642A patent/RU2696612C1/ru active
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2019
- 2019-12-25 EP EP19902850.7A patent/EP3905262A2/en not_active Ceased
- 2019-12-25 KR KR1020207037557A patent/KR20210108871A/ko unknown
- 2019-12-25 JP JP2020573142A patent/JP7337860B2/ja active Active
- 2019-12-25 BR BR112020026841A patent/BR112020026841A2/pt unknown
- 2019-12-25 US US17/257,276 patent/US11521759B2/en active Active
- 2019-12-25 CN CN201980043444.4A patent/CN113039615A/zh active Pending
- 2019-12-25 CA CA3105182A patent/CA3105182A1/en active Pending
- 2019-12-25 WO PCT/RU2019/001015 patent/WO2020139160A2/ru unknown
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP7490897B2 (ja) | 2020-12-29 | 2024-05-27 | ジョイント ストック カンパニー アトムエネルゴプロエクト | 原子炉の炉心からの溶融物を封じ込めて冷却するシステム |
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Publication number | Publication date |
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EP3905262A2 (en) | 2021-11-03 |
JP7337860B2 (ja) | 2023-09-04 |
CN113039615A (zh) | 2021-06-25 |
BR112020026841A2 (pt) | 2021-11-23 |
JP2022525566A (ja) | 2022-05-18 |
CA3105182A1 (en) | 2020-07-02 |
WO2020139160A3 (ru) | 2020-08-20 |
RU2696612C1 (ru) | 2019-08-05 |
US20210272710A1 (en) | 2021-09-02 |
KR20210108871A (ko) | 2021-09-03 |
US11521759B2 (en) | 2022-12-06 |
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