WO2022146185A1 - Система локализации и охлаждения расплава активной зоны ядерного реактора - Google Patents
Система локализации и охлаждения расплава активной зоны ядерного реактора Download PDFInfo
- Publication number
- WO2022146185A1 WO2022146185A1 PCT/RU2021/000576 RU2021000576W WO2022146185A1 WO 2022146185 A1 WO2022146185 A1 WO 2022146185A1 RU 2021000576 W RU2021000576 W RU 2021000576W WO 2022146185 A1 WO2022146185 A1 WO 2022146185A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- melt
- drum
- housing
- flange
- water supply
- Prior art date
Links
- 238000001816 cooling Methods 0.000 title claims abstract description 40
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 85
- 239000000945 filler Substances 0.000 claims abstract description 26
- 230000003014 reinforcing effect Effects 0.000 claims abstract description 8
- 239000000155 melt Substances 0.000 claims description 68
- 230000004224 protection Effects 0.000 claims description 25
- 230000000284 resting effect Effects 0.000 claims description 4
- 125000006850 spacer group Chemical group 0.000 claims description 4
- 230000006378 damage Effects 0.000 abstract description 15
- 230000004807 localization Effects 0.000 description 14
- 239000000203 mixture Substances 0.000 description 13
- 230000005855 radiation Effects 0.000 description 11
- 238000000034 method Methods 0.000 description 10
- 230000008569 process Effects 0.000 description 10
- 230000000694 effects Effects 0.000 description 9
- 238000010438 heat treatment Methods 0.000 description 6
- 239000000498 cooling water Substances 0.000 description 5
- 239000012634 fragment Substances 0.000 description 5
- 230000003993 interaction Effects 0.000 description 5
- 238000002844 melting Methods 0.000 description 5
- 230000008018 melting Effects 0.000 description 5
- 230000002093 peripheral effect Effects 0.000 description 5
- 239000000941 radioactive substance Substances 0.000 description 4
- 230000035939 shock Effects 0.000 description 4
- 230000015572 biosynthetic process Effects 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- 230000004907 flux Effects 0.000 description 3
- 230000002706 hydrostatic effect Effects 0.000 description 3
- 238000009434 installation Methods 0.000 description 3
- 102200052313 rs9282831 Human genes 0.000 description 3
- 238000012546 transfer Methods 0.000 description 3
- 230000009471 action Effects 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000004880 explosion Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 230000009993 protective function Effects 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 230000001960 triggered effect Effects 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 239000000443 aerosol Substances 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 230000000903 blocking effect Effects 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 238000002425 crystallisation Methods 0.000 description 1
- 230000008025 crystallization Effects 0.000 description 1
- 230000006870 function Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000000048 melt cooling Methods 0.000 description 1
- 238000002156 mixing Methods 0.000 description 1
- 238000013021 overheating Methods 0.000 description 1
- 230000002028 premature Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
- 239000002893 slag Substances 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
- 238000009834 vaporization Methods 0.000 description 1
- 230000008016 vaporization Effects 0.000 description 1
- 230000003313 weakening effect Effects 0.000 description 1
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
-
- 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 (NPP), and can be used in severe accidents leading to the destruction of the reactor vessel and its containment.
- NPP nuclear power plants
- the greatest radiation hazard is posed by accidents with a core meltdown, which can occur in the event of a multiple failure of the core cooling systems.
- the key aspect in this case is that the water supply through the installed valves must be carried out at a certain point in time when certain (specific) conditions are reached, namely: premature water supply can lead to a steam explosion, and the inability to supply water can lead to overheating of the equipment inside the vessel under the action of radiant heat flows from the side of the melt mirror, which, ultimately, can lead to the collapse of equipment inside the vessel, water from the reactor shaft into the melt, mixing of water with the melt, resulting in steam explosions that destroy the localization and cooling system melt and containment area with the release of radioactive substances into the environment.
- a known system [1, 2, 3] for localization and cooling of the melt of the core of a nuclear reactor containing a guide plate installed under the nuclear reactor vessel, and based on a truss-console mounted on embedded parts at the base of a concrete mine, a multilayer housing, the flange of which is provided with a thermal protection, a filler consisting of a set of cassettes installed on top of each other, a service platform installed inside the body between the filler and the guide plate.
- the superheated melt begins to flow into the hole formed under the influence of the residual pressure present in the reactor vessel, which propagates non-axisymmetrically inside the volume of the multilayer vessel and exerts a dynamic effect on peripheral structures: the zone of hermetic connection of the multilayer vessel with farm-console, thermal protection of the flange of the multilayer housing, water supply valves located in the multilayer housing, which leads to their destruction, as well as the destruction of the flange of the multilayer housing, and the internal surfaces of the truss-console, washed by the core melt, which as a result leads to disruption of the localization system and melt cooling, due to the destruction of its elements;
- the technical result of the claimed invention is to increase the reliability of the system for localization and cooling of the melt of the core of a nuclear reactor.
- the tasks to be solved by the claimed invention are to prevent the destruction of peripheral structures, equipment installed on the housing flange, and to ensure a guaranteed supply of cooling water to the melt in case of failure of the water supply valves installed in the housing.
- the system for localizing and cooling the melt of the core of a nuclear reactor containing a guide device, a truss-console, a filler for receiving and distributing the melt, is located in a housing, along the perimeter of which water supply valves are installed and a thermal protection is installed on the flange
- the invention additionally contains a drum mounted on the housing flange, made in the form of a shell with reinforcing ribs installed on the inside along its perimeter, resting on the cover and bottom, having tension elements connecting the drum through a support flange welded to it with a housing flange, spacers providing an adjusting gap between the drum and the housing flange, while the drum has branch pipes equipped with thermal reflectors and cooling ribs, in which water supply valves are installed.
- One essential feature of the claimed invention is the presence in the system of localization and cooling of the melt of the core of a nuclear reactor of a drum mounted on the flange of the housing, made in the form of a shell with reinforcing ribs installed on the inside along its perimeter, resting on the cover and bottom, having tension elements connecting drum through a support flange welded to it with a housing flange, spacers providing an adjustment gap between the drum and the housing flange, branch pipes equipped with thermal reflectors and ribs, in which water supply valves are located.
- the drum with water supply valves installed in it, makes it possible to ensure the recirculation of the vapor-gas mixture, steam-water mixture or water between the space inside and outside the housing in case of failure of the water supply valves installed along the perimeter of the housing, and, therefore, provide steam-gas, steam-water or water cooling of the melt mirror and equipment located above the melt mirror (truss-console and guide device) due to the recirculation of cooling media between the reactor shaft and internal volumes located both inside the vessel and above the melt mirror.
- Reinforcing ribs installed on the inner side of the drum shell protect the drum water supply valves from the impact of flying objects and the azimuth propagation of shock waves due to crushing and reflection of shock waves, weakening their effect on the housing water supply valves.
- Thermal reflectors and cooling ribs protect the drum water supply valves from off-design effects of thermal radiation from the melt surface, as well as from the impact of flying objects that can disrupt the operation of these water supply valves.
- FIG. 1 shows a system for localizing and cooling the melt of the core of a nuclear reactor, made in accordance with the claimed invention.
- FIG. 2 shows a drum mounted on a housing flange.
- FIG. 3 shows a fragment of the drum mounted on the housing flange.
- FIG. 4 shows a water supply valve installed in the drum.
- the system for localization and cooling of the melt of the core of a nuclear reactor contains a guide device (1) installed under the body (2) of the nuclear reactor and based on a truss-console (3). Under the truss-console (3) there is a body (4), which is mounted at the base of the reactor shaft on embedded parts.
- the body (4) with filler (7) is designed to receive and distribute the melt.
- Filler (7) is installed inside the body (4).
- a drum (12) is mounted on the flange (5) of the housing (4).
- pipes (10) with thermal reflectors (11) and cooling fins (21) are installed in the drum (12), valves (9) for water supply are installed in the pipes (10), which ensure recirculation steam-gas mixture, steam-water mixture or water between the space inside and outside the housing (4).
- the claimed system for localization and cooling of the melt of the core of a nuclear reactor operates as follows.
- the core melt under the action of hydrostatic and residual pressures begins to flow onto the surface of the guide device (1) held by the truss-console (3).
- the melt, flowing down the guide device (1) enters the housing (4) and comes into contact with the filler (7).
- partial melting of the thermal protection of the truss-console (3) and thermal protection (6) of the flange (5) of the body (4) occurs.
- these thermal protections reduce the thermal effect of the core melt on the protected equipment, and, on the other hand, reduce the temperature and chemical activity of the melt itself.
- Thermal protection (6) of the flange (5) of the body (4) provides protection of its upper thick-walled inner part from thermal effects from the core melt mirror from the moment the melt enters the filler (7) and until the end of the interaction of the melt with the filler (7), then until the start of water cooling of the crust located on the surface of the core melt.
- Thermal protection (6) of the flange (5) of the body (4) is installed in such a way that it allows to protect the inner surface of the body (4) above the level of the core melt formed in the body (4) in the process of interaction with the filler (7), namely, that upper part of the body (4), which has a greater thickness compared to the cylindrical part of the body (4), which ensures normal (without a heat transfer crisis in the boiling mode in a large volume) heat transfer from the core melt to the water located on the outer side of the body ( four).
- the thermal protection (6) of the flange (5) of the body (4) is heated and partially destroyed, shielding thermal radiation from the side of the melt mirror.
- the geometrical and thermophysical characteristics of the thermal protection (6) of the flange (5) of the body (4) are selected in such a way that, under any conditions, they provide shielding of the flange (5) of the body (4) from the side of the melt mirror, thereby ensuring the independence of protective functions from time completion of the processes of physical and chemical interaction of the core melt with the filler (7).
- the presence of thermal protection (6) of the flange (5) of the housing (4) makes it possible to ensure the performance of protective functions before the start of water supply to the crust located on the surface of the core melt.
- thermal protection (6) of the flange (5) of the housing (4) provides protection against flying objects in the event of the destruction of the bottom of the reactor vessel (2), provides protection against destruction by the flowing melt and protection from falling fragments of thermal protection located above the melt surface.
- the temperature of the melt mirror begins to grow due to the redistribution of residual energy releases in the melt between physical and chemical reactions, heat transfer through the body (4), thermal radiation to the equipment and convective heating gas mixture from the side of the melt mirror.
- the water supply of the housing (4) will heat up faster than the valves (9) of the water supply of the drum (12) and will work to open much earlier in time.
- a drum (12) is installed on the flange (5) of the body (4).
- the drum (12) is made in the form of a shell (13) with reinforcing ribs (14) installed on the inside along its perimeter, resting on the cover (15) and bottom (16).
- the drum (12) has tension elements (17) connecting the drum (12) through the support flange (18) welded to it with the flange (5) of the body (4).
- Spacer elements (20) are installed in the drum (12), by means of which an adjusting gap (19) is provided between the drum (12) and the flange (5) of the housing (4).
- Branch pipes (10) are installed in the drum (12). Each branch pipe (10) is equipped with heat reflectors (11) and cooling fins (21). In the branch pipes (10) of the drum (12) there are water supply valves (9) that ensure the recirculation of the steam-gas mixture, steam-water mixture or water between the space inside and outside the housing (4).
- Thermal reflectors (11) and cooling ribs (21) protect the water supply valves (9) of the drum (12) from non-design impact of thermal radiation from the melt surface, as well as from the impact of flying objects that can disrupt the operation of these water supply valves (9).
- Adjustment gap (19) allows for accurate installation of the drum (12) on the flange (5) of the housing (4).
- the heating intensity of the drum (12) located between the truss-console (3) and the body (4) will significantly depend on the intensity of thermal radiation from the side of the melt mirror and the condition of the water supply valves (8) of the body (4): fragments of the bottom of the body (2) of the nuclear reactor into the melt located in the body (4), there will be an ejection (splash) of the liquid melt or its wave-like rise, then it is possible to weld the valves (8) for supplying water to the body (4) with liquid melt and completely block their passage sections. Under these conditions, a complete failure of the water supply valves (8) of the housing (4) to supply cooling water to the melt mirror is possible.
- Heating of the thermal protection (6) of the flange (5) of the body (4), thermal protections in the truss-console (3) and the drum (12) will continue.
- the heating of the drum (12) is accompanied by the heating of the water supply valves (9), which are triggered to open when the set temperature is reached.
- Actuation to open the water supply valves (9) of the drum (12) provides communication between the media located outside and inside the housing (4) above the position of the melt mirror, that is, above the location of the filler (7).
- the water supply valves (9) of the drum (12) are opened, the steam-water mixture located outside the housing (4) begins to flow into the internal space of the housing (4) from above onto the slag cap formed by the dissolved filler elements (7).
- water supply valves (9) are installed in the drum (12), located above the water supply valves (8) of the body (4) in such a way that the "steam hump" formed when water boils on the outer surface of the body (4) does not locks the flow area of the water supply valves (9) of the drum (12) and does not interfere with the equalization of pressure between the vapor-gas media located both outside and inside the housing (4).
- the melt mirror After actuation of the water supply valves (8) of the body (4), the melt mirror does not cool down, since the water level is somewhat lower than the location of the indicated water supply valves (8). There is a further heating by radiant heat fluxes of the equipment located above the melt mirror, including the valves (9) of the water supply of the drum (12). Having reached the response temperature, the water supply valves (9) of the drum (12) open, ensuring pressure equalization inside and outside the housing (4).
- a vertical steam-gas draft arises, which ensures the circulation of the steam-gas mixture along the following path: the steam-water mixture enters through the valves (8) for supplying water into the body (4) into the space above the melt mirror, where it evaporates intensively and, rushing upwards, partially exits through the open valves (9) water supply of the drum (12) into the space around the outer surface of the housing (4) - in the space above it, located around the outer surface of the shell (13) of the drum (12), and then into a sealed shell, and partially passes along the truss-console (3) and enters the guide device (1), through which, depending on the state the bottom of the reactor vessel (2) and the guide device (1) may eventually also go into the hermetic shell.
- the successive operation of the water supply valves (8) of the body (4) and the water supply valves (9) of the drum (12) ensures the recirculation of the vapor-gas mixture that cools the equipment of the nuclear reactor core melt localization and cooling system located above the melt mirror, which allows, ultimately, to ensure stable long-term, first steam-gas, and then steam (vapor-droplet) cooling of the melt mirror in conditions of over-design equipment failures.
- the use of a drum with water supply valves installed in nozzles equipped with thermal reflectors and cooling fins as part of the system for localizing and cooling the core melt of a nuclear reactor made it possible to increase its reliability by placing water supply valves at different levels and ensuring cooling of the melt mirror. with insufficient level of cooling water in the reactor shaft.
Landscapes
- 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 (5)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2023539290A JP7490897B2 (ja) | 2020-12-29 | 2021-12-15 | 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 |
CN202180088302.7A CN116686055A (zh) | 2020-12-29 | 2021-12-15 | 核反应堆堆芯熔化物冷却和定域系统 |
EP21915935.7A EP4273884A1 (en) | 2020-12-29 | 2021-12-15 | System for confining and cooling melt from the core of a nuclear reactor |
KR1020237020695A KR20230125196A (ko) | 2020-12-29 | 2021-12-15 | 원자로 노심 용융 코어 캐처 및 냉각 시스템 |
CA3203514A CA3203514A1 (en) | 2020-12-29 | 2021-12-15 | System for confining and cooling melt from the core of a nuclear reactor |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RU2020143779A RU2758496C1 (ru) | 2020-12-29 | 2020-12-29 | Система локализации и охлаждения расплава активной зоны ядерного реактора |
RU2020143779 | 2020-12-29 |
Publications (1)
Publication Number | Publication Date |
---|---|
WO2022146185A1 true WO2022146185A1 (ru) | 2022-07-07 |
Family
ID=78466548
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/RU2021/000576 WO2022146185A1 (ru) | 2020-12-29 | 2021-12-15 | Система локализации и охлаждения расплава активной зоны ядерного реактора |
Country Status (7)
Country | Link |
---|---|
EP (1) | EP4273884A1 (ru) |
JP (1) | JP7490897B2 (ru) |
KR (1) | KR20230125196A (ru) |
CN (1) | CN116686055A (ru) |
CA (1) | CA3203514A1 (ru) |
RU (1) | RU2758496C1 (ru) |
WO (1) | WO2022146185A1 (ru) |
Citations (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU2575878C1 (ru) | 2014-12-16 | 2016-02-20 | 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 |
RU2576516C1 (ru) | 2014-12-16 | 2016-03-10 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа |
RU2696004C1 (ru) * | 2018-08-29 | 2019-07-30 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа |
RU2696619C1 (ru) * | 2018-09-25 | 2019-08-05 | Акционерное Общество "Атомэнергопроект" | Устройство локализации расплава активной зоны ядерного реактора |
RU2700925C1 (ru) * | 2018-09-25 | 2019-09-24 | Акционерное Общество "Атомэнергопроект" | Устройство локализации расплава активной зоны ядерного реактора |
CN109273109B (zh) * | 2018-11-13 | 2020-01-31 | 中国核动力研究设计院 | 一种熔融物安全壳滞留系统 |
RU2734734C1 (ru) * | 2020-03-13 | 2020-10-22 | Акционерное Общество "Атомэнергопроект" | Направляющее устройство системы 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 |
Family Cites Families (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU2696612C1 (ru) | 2018-12-26 | 2019-08-05 | Акционерное Общество "Атомэнергопроект" | Устройство локализации расплава |
JP7182504B2 (ja) | 2019-03-27 | 2022-12-02 | 日立Geニュークリア・エナジー株式会社 | コリウムシールド |
-
2020
- 2020-12-29 RU RU2020143779A patent/RU2758496C1/ru active
-
2021
- 2021-12-15 EP EP21915935.7A patent/EP4273884A1/en active Pending
- 2021-12-15 CN CN202180088302.7A patent/CN116686055A/zh active Pending
- 2021-12-15 KR KR1020237020695A patent/KR20230125196A/ko unknown
- 2021-12-15 WO PCT/RU2021/000576 patent/WO2022146185A1/ru active Application Filing
- 2021-12-15 CA CA3203514A patent/CA3203514A1/en active Pending
- 2021-12-15 JP JP2023539290A patent/JP7490897B2/ja active Active
Patent Citations (11)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU2575878C1 (ru) | 2014-12-16 | 2016-02-20 | 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 |
RU2576516C1 (ru) | 2014-12-16 | 2016-03-10 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа |
RU2696004C1 (ru) * | 2018-08-29 | 2019-07-30 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа |
RU2696619C1 (ru) * | 2018-09-25 | 2019-08-05 | Акционерное Общество "Атомэнергопроект" | Устройство локализации расплава активной зоны ядерного реактора |
RU2700925C1 (ru) * | 2018-09-25 | 2019-09-24 | Акционерное Общество "Атомэнергопроект" | Устройство локализации расплава активной зоны ядерного реактора |
WO2020067919A1 (ru) * | 2018-09-25 | 2020-04-02 | Акционерное Общество "Атомэнергопроект" | Устройство локализации расплава активной зоны ядерного реактора |
CN109273109B (zh) * | 2018-11-13 | 2020-01-31 | 中国核动力研究设计院 | 一种熔融物安全壳滞留系统 |
RU2734734C1 (ru) * | 2020-03-13 | 2020-10-22 | Акционерное Общество "Атомэнергопроект" | Направляющее устройство системы 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 |
Also Published As
Publication number | Publication date |
---|---|
JP2024501979A (ja) | 2024-01-17 |
EP4273884A1 (en) | 2023-11-08 |
CA3203514A1 (en) | 2022-07-07 |
RU2758496C1 (ru) | 2021-10-29 |
KR20230125196A (ko) | 2023-08-29 |
CN116686055A (zh) | 2023-09-01 |
JP7490897B2 (ja) | 2024-05-27 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US11476010B2 (en) | Cooling method for reactor molten core melt and cooling control system for reactor molten core | |
RU2696004C1 (ru) | Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа | |
JP2023515283A (ja) | 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 | |
JPH0727050B2 (ja) | 受動冷却系を備えた液体金属冷却型原子炉 | |
RU2758496C1 (ru) | Система локализации и охлаждения расплава активной зоны ядерного реактора | |
KR102626473B1 (ko) | 원자로 노심용융물의 억제 및 냉각 시스템 | |
RU2767599C1 (ru) | Система локализации и охлаждения расплава активной зоны ядерного реактора | |
EP4246534A1 (en) | System for confining and cooling melt from the core of a nuclear reactor | |
EA045342B1 (ru) | Система локализации и охлаждения расплава активной зоны ядерного реактора | |
CA3191248A1 (en) | Corium localizing and cooling system of a nuclear reactor | |
EA045312B1 (ru) | Система локализации и охлаждения расплава активной зоны ядерного реактора | |
US20230343476A1 (en) | System for confining and cooling melt from the core of a nuclear reactor | |
JP7494398B2 (ja) | 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 | |
JP7494384B2 (ja) | 原子炉における炉心溶融物の局在化および冷却のためのシステム | |
EA044913B1 (ru) | Система локализации и охлаждения расплава активной зоны ядерного реактора | |
CA3066230A1 (en) | Cooling method for reactor molten core melt and cooling control system for reactor molten core | |
EA044696B1 (ru) | Система локализации и охлаждения расплава активной зоны ядерного реактора |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
121 | Ep: the epo has been informed by wipo that ep was designated in this application |
Ref document number: 21915935 Country of ref document: EP Kind code of ref document: A1 |
|
ENP | Entry into the national phase |
Ref document number: 3203514 Country of ref document: CA |
|
WWE | Wipo information: entry into national phase |
Ref document number: 2023539290 Country of ref document: JP |
|
WWE | Wipo information: entry into national phase |
Ref document number: 202180088302.7 Country of ref document: CN |
|
REG | Reference to national code |
Ref country code: BR Ref legal event code: B01A Ref document number: 112023012405 Country of ref document: BR |
|
ENP | Entry into the national phase |
Ref document number: 112023012405 Country of ref document: BR Kind code of ref document: A2 Effective date: 20230621 |
|
NENP | Non-entry into the national phase |
Ref country code: DE |
|
ENP | Entry into the national phase |
Ref document number: 2021915935 Country of ref document: EP Effective date: 20230731 |
|
WWE | Wipo information: entry into national phase |
Ref document number: 523441394 Country of ref document: SA |