WO2021188005A1 - Направляющее устройство системы локализации и охлаждения расплава активной зоны ядерного реактора - Google Patents
Направляющее устройство системы локализации и охлаждения расплава активной зоны ядерного реактора Download PDFInfo
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- WO2021188005A1 WO2021188005A1 PCT/RU2020/000763 RU2020000763W WO2021188005A1 WO 2021188005 A1 WO2021188005 A1 WO 2021188005A1 RU 2020000763 W RU2020000763 W RU 2020000763W WO 2021188005 A1 WO2021188005 A1 WO 2021188005A1
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- Prior art keywords
- melt
- core
- load
- shell
- ribs
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Classifications
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- 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
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- 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 systems for localization and cooling of the core melt of a nuclear reactor, designed to localize severe beyond design basis accidents, in particular, to devices for directing the core melt of a nuclear reactor into a melt trap. multiple failure of core cooling systems.
- melt trap which, after the core melt enters it, prevents damage to the hermetic shell of the nuclear power plant and, thereby, protects the population and the environment from radiation exposure in severe accidents of nuclear reactors by cooling and subsequent crystallization of the melt.
- the core melt After the reactor vessel is melted, the core melt enters a guiding device, which is usually made in the form of a funnel mounted on a console truss, and is designed to change the direction of the melt flow from the place of its outflow from the reactor vessel towards the axis reactor mines, in order to ensure the flow of the melt to the service site. Burning through the service platform, the melt enters the melt trap, where it interacts with the filler, gradually heating the body of the melt trap. In this case, when the reactor vessel melts, a complete separation of the vessel bottom can occur, as a result of which the reactor vessel bottom falls onto the guide device, significantly reducing or completely blocking the flow of the melt into the melt trap.
- a guiding device which is usually made in the form of a funnel mounted on a console truss, and is designed to change the direction of the melt flow from the place of its outflow from the reactor vessel towards the axis reactor mines, in order to ensure the flow of the melt to the service site. Burning through the service platform
- Known guiding device [1] (RF Patent N ° 2253914, priority from 18.08.2003) system for localization and cooling of the core melt of a nuclear reactor, installed under the bottom of the reactor vessel and resting on a truss-console, made in the form of a funnel, consisting of cylindrical and conical parts, the surfaces of which are covered with heat-resistant concrete, holes made in the center of the conical part.
- One disadvantage of the guiding device is the insufficient thermal insulation of the walls of the conical and cylindrical parts.
- the guiding device taking into account the acceleration created by the residual pressure inside the reactor vessel, and taking into account the rotation of the detached bottom during movement, it is possible to block the hole made in the center of the conical part. This can lead to the accumulation of core melt in the area of the conical part of the guide device and, consequently, to an increase in temperature in this area.
- Another disadvantage of the guiding device is the absence of a mechanism for redistributing (Aligning) the jet streams of the core melt. This leads to the fact that shock thermal and mechanical loads are concentrated in the upper and middle zones of the cylindrical part. The concentration of shock thermal and mechanical loads can lead to the destruction of the guiding device and the ingress of the core melt onto the building and serpentinite concrete, followed by their destruction and the formation of hydrogen and non-condensable gases, resulting in the risk of hydrogen explosions and over-design pressure rise in the containment. This can lead to the destruction of the containment and the release of non-design amount of radioactive fission products outside the containment.
- Known guiding device [2] (Device for localization of the melt, 7th International Scientific and Practical Conference “Ensuring the safety of nuclear power plants with VVER”, OKB “Gidropress”, Podolsk, Russia, May 17-20 2011) of the system for localization and cooling of the melt of the core of a nuclear reactor, consisting of a cylindrical part and a conical part, in the center of which a hole is made, force ribs passing from the central hole to the boundary of the cylindrical part.
- One disadvantage of the guiding device is the insufficient thermal insulation of the walls of the conical and cylindrical parts.
- Another disadvantage of the guiding device is the absence of a mechanism for redistributing (leveling) the jet streams of the core melt. This leads to the fact that shock thermal and mechanical loads are concentrated in the upper and middle zones of the cylindrical part. The concentration of shock thermal and mechanical loads can lead to the destruction of the guiding device and the ingress of the core melt onto the building concrete and serpentinite concrete, followed by their destruction and the formation of hydrogen and non-condensable gases, as a result of which there are risks of hydrogen explosions and over-design pressure rise in the containment. This can lead to the destruction of the containment and the release of non-design amount of radioactive fission products outside the containment.
- the guiding device [3, 4, 5] [RF Patent N ° 2576516, priority from 16.12.2014; RF patent N22576517, priority from 16.12.2014; RF patent JN22575878, priority from 16.12.2014] a system for localizing and cooling the melt of the core of a nuclear reactor, consisting of a cylindrical part and a conical part, in the center of which there is a hole, force ribs passing from the central hole to the upper edge of the cylindrical part, and dividing the cylindrical and conical parts into sectors covered with layers of sacrificial and heat-resistant concrete.
- Such a guiding device is intended to direct the corium (melt) after the destruction or penetration of the reactor into the melt trap, to hold large-sized fragments of the internals, fuel assemblies and the bottom of the reactor vessel from radiance into the melt trap, to protect the console truss and its communications from destruction when melt flows from the reactor vessel into a melt trap, protecting the concrete shaft from direct contact with the core melt.
- the force ribs hold the bottom of the reactor vessel with the melt, which does not allow the bottom, in the process of its destruction or strong plastic deformation, to overlap the flow sections of the sectors and disrupt the process of melt drainage.
- Sacrificial concrete dissolving in the core melt, provides an increase in the flow area in the sectors of the guide plate during the formation of blockages (when the melt solidifies in one or several sectors), which prevents overheating and destruction of the load-bearing ribs, that is, complete blocking of the flow area and, how the consequence of this is the destruction of the guide plate.
- Heat-resistant heat-resistant concrete provides structural strength while reducing the thickness of the sacrificial concrete. This concrete protects the underlying equipment from melt attack, preventing the melt from melting or destroying the baffle plate.
- One drawback of the guiding device is the inability of the two-layer sacrificial concrete to provide an increase in the flow area in the sectors of the guide plate while simultaneously entering a large volume of melt of metals and oxides, for example, when the bottom of the reactor vessel is torn off by a full cross-section or when it is sectorially destroyed.
- the simultaneous interaction of two types of overheated melt (metallic and oxide) with sacrificial concrete (based on aluminum and iron oxides) will lead to rapid oxygen evolution, violent oxidation, aerosol and slag formation with complete overlap of the flow area.
- Another disadvantage of the guiding device is the insufficient thermal insulation of the walls of the conical and cylindrical parts.
- a rapid flow of core melt from the reactor vessel when the bottom is torn off by its full cross-section taking into account the acceleration created by the residual pressure inside the reactor vessel, and taking into account the rotation of the torn-off bottom during movement, it is possible to block the hole made in the center of the conical part. This can lead to the accumulation of core melt in the area of the conical part of the guiding device and, consequently, to an increase in temperature in the area.
- Another disadvantage of the guiding device is the absence of a mechanism for redistributing (leveling) the jet streams of the core melt. This leads to the fact that shock thermal and mechanical loads are concentrated in the upper and middle zones of the cylindrical part. , Concentration shock thermal and mechanical stresses can cause fracture of the track and the ingress of the core melt in structural concrete and serpentine concrete with subsequent destruction and form hydrogen and non-condensable gases, thereby causing risks of hydrogen explosions and sverhproektnogo rise of pressure in the containment. This can lead to the destruction of the containment and the release of non-design amount of radioactive fission products outside the containment.
- the technical result of the claimed invention is to improve the safety of a nuclear power plant by increasing the reliability of the system for localizing and cooling the core melt of a nuclear reactor.
- the tasks to be solved by the invention are to ensure the following conditions for the operation of the system for localization and cooling of the core melt of a nuclear reactor:
- the guiding device (1) of the system for localizing and cooling the melt of the core of a nuclear reactor containing a cylindrical part (2) and a conical part (3), with a hole (4) made in it, force ribs (5) located radially relative to the hole (4), and dividing the walls of the cylindrical (2) and conical (3) parts into sectors (7), installed under the reactor vessel and supported by the nd “truss-console, according to the invention, additionally contains a load-bearing frame consisting of the outer upper power ring (8), the outer lower power ring (9), the inner central power ring (10), the outer upper power shell (11), the middle power shell (12), divided into sectors by force ribs (5) and having a hole (14) in the upper part, the outer lower load-bearing shell (15), the base (16), the support ribs (17), the upper inclined plate (18) connecting the conical bottom (19), the load-bearing ribs (5) and the middle load-bearing both gull (12), the lower inclined
- One distinctive feature of the claimed invention is the presence in the guide device (1) of a system for localizing and cooling the melt of a load-bearing frame, consisting of an external upper load-bearing ring (8), an external lower load-bearing ring (9), an internal central load-bearing ring (10), an external upper load-bearing shell (11), middle load shell (12), divided into sectors by force ribs (5) and having a hole (14) in the upper part, outer lower load shell (15), base (16), support ribs (17), upper inclined plate (18) connecting the conical bottom (19), force ribs (5) and the middle force shell (12), the lower inclined plate (20) connecting the conical bottom (19), force ribs (5), middle force shell ( 12) and the outer upper power shell (11).
- the presence of a load-bearing frame makes it possible to ensure the retention of large-sized debris of the internals and the bottom of the reactor vessel from falling into melt trap, which protects the body of the melt trap from damage.
- thermal plate metal screens (23) installed on the supporting ribs (17) and installed with a gap (22) along the inner surface of the middle power shell (12) and along the upper inclined plate (18), a collapsible thermal plate metal shield (13) installed on the supporting ribs (17) and closing the hole (4).
- thermal lamellar metal screens (23) makes it possible to ensure gravity flow into the filler of the core melt after the destruction or melting of the reactor vessel, to protect the console truss and its communications from destruction during the movement of the melt, to exclude direct contact of the core melt with the reactor shaft equipment and building concrete.
- Another distinctive feature of the claimed invention is the presence in the guiding device (1) of a system for localizing and cooling the melt of a cooling channel (21) leaving the collector (6) and passing between the upper and lower inclined plates (18 and 20), as well as between the middle and the outer upper power shells (12 and 11), connected through the hole (14) with the gap (22), which forms the space between the thermal plate metal screen (23) and the middle power shell (12), as well as between the thermal plate metal screen (23) and the upper inclined plate (18).
- the presence of the cooling channel (21) provides thermal stabilization of the entire guide device (1) during reactor operation at power under normal operating conditions.
- Another distinctive feature of the claimed invention is that in the guiding device (1) of the system for localizing and cooling the melt of the core of a nuclear reactor, the space (24), limited by the base
- Another distinctive feature of the claimed invention is the presence in the guide device (1) of a system for localizing and cooling the core melt of a nuclear reactor of a sealed bottom (28) connected to the outer lower power shell (15) and supporting ribs
- this design of the guiding device allows: - to provide a gradual flow of corium (melt) after the destruction or penetration of the reactor into the melt trap;
- Figure 1 shows the guiding device of the system for localizing and cooling the core melt of a nuclear reactor, made in accordance with the claimed invention.
- Figure 2 shows a sectional guide device of the system for localizing and cooling the core melt of a nuclear reactor, made in accordance with the claimed invention.
- Fig.Z shows a fragment of the guiding device of the system for localization and cooling of the melt of the active zone of a nuclear reactor, made in accordance with the claimed invention.
- the guiding device (1) of the system for localizing and cooling the core melt of a nuclear reactor installed under the reactor vessel and resting on a cantilever truss, comprises a cylindrical part (2) and a conical part (3).
- a hole (4) is made at the base of the conical part (3).
- Strength ribs (5) located radially relative to the hole (4) run along the conical and cylindrical parts (2 and 3). Force ribs (5) divide the walls of the cylindrical (2) and conical (3) parts into sectors (7).
- the device (1) contains a load-bearing frame, which consists of the following main (load-bearing) elements: an external upper load-bearing ring (8), an external lower load-bearing ring (9), an internal central load-bearing ring (10), an external upper load-bearing shell (11), middle power shell (12).
- the middle load-bearing shell (11) is divided into sectors by force ribs (5) similarly to the wall of the cylindrical part (2).
- the structure of the load-bearing frame also includes an external lower load-bearing shell (15), a base (16), support ribs (17), and an upper inclined plate (18).
- the upper inclined plate (18) connects the conical bottom (19), power ribs (5) and the middle power shell (12).
- the lower inclined plate (20) connects the conical bottom (19), power ribs (5), the middle power shell (12) and the outer upper power shell (11).
- thermal plate metal screens 23
- collapsible thermal plate metal screen 13
- Thermal plate metal shields (23) are installed on the supporting ribs (17), as well as with a gap (22) along the inner surface of the middle load-bearing shell (12) and along the upper inclined plate (18).
- a collapsible thermal plate metal shield (13) is installed on the supporting ribs (17) and closes the hole (4).
- a cooling channel (21) runs between the upper and lower inclined plates (18 and 20), as well as between the middle and outer upper power shells (12 and 11).
- the cooling channel (21) leaves the collector (6) and is connected through the hole (14) with the gap (22), which forms the space between the thermal plate metal screen (23) and the middle power shell (12), as well as between the thermal plate metal screen ( 23) and the upper inclined plate (18).
- a sealed bottom (28) is welded to the outer lower power shell (15) and support ribs (17).
- the claimed guide device operates as follows.
- the guiding device (1) installed on the truss-console under the bottom of the reactor vessel, in accordance with the essence of the claimed invention, serves as a thermal barrier between the reactor vessel and the equipment of the reactor shaft in its lower part, as well as between the bottom of the reactor vessel and a melt trap located below the guide device (1).
- the presence of a thermal barrier allows, during normal operation, to provide thermal insulation of the bottom of the reactor vessel, and in a severe accident, at the time of the destruction of the reactor vessel by the melt of the core, to provide conditions for diagnosing the beginning of the flow of melt into the trap.
- thermal insulation is installed on the guide plate, consisting of plate metal heat shields (23), made in the form of packages assembled from puckered and non-poured thin sheets of stainless steel.
- Such packages are installed on the walls (6) of the cylindrical and conical parts (2 and 3), as well as on the inner surface of the middle load-bearing shell (12) and the upper inclined plate (18) with the help of fasteners that provide thermal displacement of the heat-insulating packages and the frame of the guide plate relative to each other during normal operation, disruption of normal operation and design basis accident.
- a collapsible thermal plate metal shield (13) is installed directly under the pole of the bottom of the reactor vessel, which provides, if necessary, access to the outer surface of the reactor vessel.
- a hatch with a displacing insert is made in the lower part of the guide device (1) from the side of the service platform.
- the space between the load-bearing elements (5, 8, 11, 9, 15, 16, 19, 18, 12) of the guide device is filled with heat-resistant concrete.
- Power elements (5, 8, 11, 9, 15, 10) and concrete and ceramic material (27) form, in their function, a guiding vane in the form of a funnel, providing coverage of the lower part of the reactor vessel above the plane, connecting the bottom with a cylindrical particle ( 2).
- the guiding device (1) can be subjected to both relatively slow loading during plastic deformations of the reactor vessel and shock loading when the bottom of the reactor vessel is torn off under the influence of residual pressure.
- the sacrificial material located under the upper inclined plate (18), dissolving in the core melt provides an increase in the flow area in the sectors of the guide device (1), if the increase in the effective flow area provided by flattening and melting of thin elements of the plate metal screen ( 23) turned out to be insufficient when, for example, the outflow of the melt from the reactor vessel at a high flow rate exceeding the throughput of the flow area of the guiding device (1) or when the melt outflows with core debris blocking the flow area and preventing the free flow of the melt.
- Dissolving the sacrificial material prevents overheating and destruction of the power ribs (5). With the destruction of the load-bearing ribs (5), a complete blocking of the flow section is possible and, as a consequence of this, the sectorial destruction of the guide device (1).
- a heat-resistant heat-resistant layer located under the lower inclined plate (20) provides strength and stability of the structure while reducing the thickness of the sacrificial material, located between the upper and lower inclined plates (18 and 20).
- Heat-resistant concrete protects the underlying equipment from the melt, preventing the melt from penetrating through the sector or destroying the guide.
- the guiding device (1) takes on the dynamic loads arising: during the lateral outflow of the melt under the influence of the residual pressure in the reactor vessel; with an increase in the flow area of the side cavity in the reactor vessel and a change in its profile during the outflow of the melt; when parts of the bottom of the reactor vessel are torn off as a result of plastic deformation under the action of thermomechanical loads and residual pressure; by tearing off portions of the bottom of the reactor vessel as a result of pulsed pressure rise within the housing (water when casting the melt of the core) and their impact on the braking guide unit; under external influences and car shocks in the course of a beyond design basis accident.
- the filler located in the trap body is hermetically closed by the bottom (28) of the guiding device (1), which ensures: drainage of water from the bottom surface (28) and, as a consequence, the absence of steam explosions at the moment the melt enters the filler; preservation of the integrity of the filler and structural materials during the entire period of normal operation, as well as in the event of a violation of normal operation and in a design basis accident.
- the sealed bottom (28) is made in the form of an easily destructible membrane; thermal plate metal shields (13 and 23) are made easily destructible by high-temperature melt so as not to impede its movement.
- thermal plate metal shields 13 and 23
- the flow area for melt flowing over the surface of the guide vanes increases several times.
- thermal plate metal screens (23) a different degree of increase in the flow area is provided, which is associated with a different geometry of the channels formed by vertical force ribs; a hole (4) is made in the central part of the guide vane for the passage of the corium, the dimensions of which limit the spread of solid and liquid fragments of the core during its outflow from the reactor vessel.
- thermal plate metal shields (23) and sacrificial material installed under the upper and lower inclined plates (18 and 20), used as part of the guiding device (1) of the system for localizing and cooling the core of a nuclear reactor perform shockproof, channel-forming and protective functions.
- Plate metal heat shields (23) provide the initial damping of the shock load from the detached sectors of the destroyed bottom, taking into account the acceleration created by the residual pressure inside the reactor vessel.
- crushable plate metal heat shields (23) provide initial protection of the guiding device (1) and from the impact of melt jets at a small residual pressure in the reactor vessel.
- the shock load is perceived by a concrete or ceramic material (27), which forms protective layers around the critical strength elements (5, 11, 15, 9) of the guiding device (1), moreover, the strength ribs (5) can be partially melted, especially for the inclined part, protected by layers of sacrificial material located under the upper and lower inclined plates (18 and 20).
- the concrete or ceramic material (27) creates impenetrable barriers for projectiles and jets of the core melt.
- thermal plate metal shields (23) and concrete or ceramic material (27), forming protective layers of the load-bearing elements (5, 9, 11, 12, 15) of the guide device (1) provide deceleration and blocking of large fragments of the reactor vessel and its internals, at the same time, ensuring the consistent flow of core melt, fragments of internals and the bottom of the nuclear reactor vessel into the melt trap.
- Crushable thermal plate metal screens (23) provide an increase in the flow area for moving the core melt in each radial vertical and inclined sector and in the azimuthal direction with horizontal melt flow.
- thermal plate metal shields (23) and concrete or ceramic material (27), forming protective layers of the load-bearing elements (5, 9, 11, 12, 15) of the guiding device (1) provide protection of the construction and serpentinite concrete of the reactor shaft from interaction with the melt.
- Concrete or ceramic material (27) which forms protective layers around the critical load-bearing elements (5, 11, 15, 9) of the guide device (1), create thermal and chemical barriers preventing damage and destruction of the load-bearing elements (5, 8, 11, 9, 15, 18, 20, 12) of the guiding device (1) under thermochemical and thermomechanical influences from the jets of the core melt, for which the heat resistance of the concrete or ceramic material (27) is chosen differently in different directions of the core melt flow, which provides more early destruction of the sacrificial material located under the upper inclined plate (18), closest to the reactor vessel, which achieves a faster evacuation of the melt and a decrease in thermochemical and thermomechanical effects on critical power elements (5, 6, 9, 7, 11, 14 , 10) guiding device (1).
- concrete or ceramic material (27), forming protective layers of the load-bearing elements (5, 6, 9, 7, 11, 14, 10) of the guide device (1), provide their strength during lateral penetration of the reactor vessel and, as a consequence, protection of construction and serpentinite concrete of the reactor shaft from interaction with the melt.
- a guiding device (1) which has a load-bearing frame, equipped with additional thermal elements, made it possible to ensure a gradual flow of corium (melt) after the destruction or penetration of the reactor vessel into the melt trap, keeping large fragments of internals, fuel assemblies and the bottom of the reactor vessel from falling into the trap. melt, protection the truss-console and its communications from destruction when the melt flows from the reactor vessel into the melt trap, without blocking the central hole made in the conical part, protection of the concrete shaft and dry protection with serpentinite concrete from direct contact with the core melt.
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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
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Priority Applications (7)
Application Number | Priority Date | Filing Date | Title |
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CA3145726A CA3145726A1 (en) | 2020-03-18 | 2020-12-29 | Guide assembly of the corium localizing and cooling system of a nuclear reactor |
JOP/2021/0346A JOP20210346A1 (ar) | 2020-03-18 | 2020-12-29 | جهاز التوجيه لأنظمة التوطين والتبريد لمصهور المنطقة الفعالة (ذوبان القلب) لمفاعل النووي |
KR1020217043133A KR102637846B1 (ko) | 2020-03-18 | 2020-12-29 | 원자로 노심용융물의 억제 및 냉각 시스템의 안내장치 |
CN202080047857.2A CN114424295A (zh) | 2020-03-18 | 2020-12-29 | 核反应堆堆芯熔体定位冷却***的导向装置 |
BR112021026596A BR112021026596A2 (pt) | 2020-03-18 | 2020-12-29 | Dispositivo guia para o sistema de localização e resfriamento do fundido no núcleo de um reator nuclear |
JP2021578279A JP7329084B2 (ja) | 2020-03-18 | 2020-12-29 | 原子炉の炉心溶融物の位置特定と冷却のためのシステムのガイド装置 |
ZA2021/10607A ZA202110607B (en) | 2020-03-18 | 2021-12-17 | Guide assembly of the corium localizing and cooling system of a nuclear reactor |
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RU2020111301A RU2740400C1 (ru) | 2020-03-18 | 2020-03-18 | Направляющее устройство системы локализации и охлаждения расплава активной зоны ядерного реактора |
RU2020111301 | 2020-03-18 |
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WO2021188005A1 true WO2021188005A1 (ru) | 2021-09-23 |
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JP (1) | JP7329084B2 (ru) |
KR (1) | KR102637846B1 (ru) |
CN (1) | CN114424295A (ru) |
BR (1) | BR112021026596A2 (ru) |
CA (1) | CA3145726A1 (ru) |
JO (1) | JOP20210346A1 (ru) |
RU (1) | RU2740400C1 (ru) |
WO (1) | WO2021188005A1 (ru) |
ZA (1) | ZA202110607B (ru) |
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2020
- 2020-03-18 RU RU2020111301A patent/RU2740400C1/ru active
- 2020-12-29 CN CN202080047857.2A patent/CN114424295A/zh active Pending
- 2020-12-29 JP JP2021578279A patent/JP7329084B2/ja active Active
- 2020-12-29 WO PCT/RU2020/000763 patent/WO2021188005A1/ru unknown
- 2020-12-29 KR KR1020217043133A patent/KR102637846B1/ko active IP Right Grant
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2021
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Patent Citations (6)
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RU2253914C2 (ru) | 2003-08-18 | 2005-06-10 | Хабенский Владимир Бенцианович | Система локализации и охлаждения кориума аварийного ядерного реактора водо-водяного типа |
CN203070782U (zh) * | 2013-01-08 | 2013-07-17 | 上海核工程研究设计院 | 一种大型非能动压水堆核电厂坩埚型堆芯捕集器 |
RU2575878C1 (ru) | 2014-12-16 | 2016-02-20 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа |
RU2576516C1 (ru) | 2014-12-16 | 2016-03-10 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа |
RU2576517C1 (ru) | 2014-12-16 | 2016-03-10 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа |
KR20170126361A (ko) * | 2016-05-09 | 2017-11-17 | 포항공과대학교 산학협력단 | 노심용융물 냉각을 위한 기둥과 경사면을 가진 다공성재질의 원자력발전소 코어 캐쳐. |
Non-Patent Citations (1)
Title |
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"7th International Research and practical conference ''Safety assurance of NPP with VVER", 17 May 2011, OKB GIDROPRESS, article "Corium localizing device" |
Also Published As
Publication number | Publication date |
---|---|
RU2740400C1 (ru) | 2021-01-14 |
CN114424295A (zh) | 2022-04-29 |
JOP20210346A1 (ar) | 2023-01-30 |
CA3145726A1 (en) | 2021-09-23 |
KR102637846B1 (ko) | 2024-02-16 |
BR112021026596A2 (pt) | 2022-09-27 |
JP2023519773A (ja) | 2023-05-15 |
JP7329084B2 (ja) | 2023-08-17 |
ZA202110607B (en) | 2022-08-31 |
KR20220044685A (ko) | 2022-04-11 |
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