WO2020067919A1 - Устройство локализации расплава активной зоны ядерного реактора - Google Patents
Устройство локализации расплава активной зоны ядерного реактора Download PDFInfo
- Publication number
- WO2020067919A1 WO2020067919A1 PCT/RU2018/000898 RU2018000898W WO2020067919A1 WO 2020067919 A1 WO2020067919 A1 WO 2020067919A1 RU 2018000898 W RU2018000898 W RU 2018000898W WO 2020067919 A1 WO2020067919 A1 WO 2020067919A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- melt
- trap
- radial supports
- radial
- embedded plate
- Prior art date
Links
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 (NPPs), and can be used in severe accidents leading to core melting, destruction of the nuclear reactor shell and exit of the melt into the space of the sealed shell of nuclear power plants.
- NPPs nuclear power plants
- the greatest radiation hazard is accidents with core melting, which can occur during various combinations of failures (destruction of equipment components) of active and passive safety systems and normal operation systems, or in conditions of complete de-energization of the nuclear power plant and the inability to supply power within the time period set by the design of the nuclear power plant to ensure emergency core cooling.
- a device [1] for localizing a melt in the core of a nuclear reactor comprising a melt trap installed under the bottom of the reactor vessel and provided with a cooled shell in the form of a multilayer vessel, a melt dilution filler placed in said multilayer vessel, a lower support consisting of a horizontal sectional, continuous or divided, embedded plate installed under the multilayer vessel in the concrete of the reactor shaft, a vertical cylindrical pipe connecting the melt trap to the embedded plate by means of clamps and fasteners products.
- the disadvantages of this device is that when the melt moves in the trap, free thermal radial expansion of its bottom is not provided, as well as maintaining the integrity of the bottom of the melt trap and the embedded plate in the floor of the reactor shaft during axial thermal expansions of the bottom of the melt trap and during impacts, which is due to structural features fastening the melt trap using a vertical cylindrical pipe to the lower support.
- the inner surface of the melt trap is heated to a temperature close to the melting temperature of steel, which is about one and a half thousand degrees Celsius.
- the thickness of the bottom of the melt trap is no less than 30% thicker than its side walls, this still leads to the emergence of critical thermal stresses between the bottom of the melt trap expanding in the radial direction and the relatively cold vertical cylindrical pipe, the expansion of which in the radial direction occurs only under the action of mechanical loading from the bottom of the melt trap.
- a vertical cylindrical pipe begins to deform unevenly, both in the azimuthal and in the radial directions, which as a result leads to the appearance of cracks in it with subsequent destruction.
- the destruction of the vertical cylindrical pipe leads to the termination of the design functioning of the melt trap.
- the technical result of the claimed invention is to increase the reliability of the device for localization of the melt of the active zone of a nuclear reactor.
- a filler for diluting the melt placed in the said multilayer vessel the lower support, consisting of a horizontal sectional, continuous or divided, embedded plate installed under a multilayer vessel in the concrete of the reactor shaft, according to the invention, a horizontal section A solid, solid or split mortar plate contains radial bearings, the melt trap also contains radial bearings, resting on the radial bearings of a horizontal sectional, solid or divided mortar plate, radial bearings of a horizontal sectional, solid or divided, mortar plate and radial supports of the melt trap are connected by means of retainers, while the radial bearings and retainers have oval-shaped openings.
- a distinctive feature of the claimed invention is the lower support, consisting of a horizontal sectional, continuous or divided, embedded plate having radial supports, and radial supports installed in the lower part of the melt trap, while the radial supports of the embedded plate and the melt trap are connected by means of clamps.
- Radial bearings of the embedded plate, melt traps, as well as clamps have oval-shaped openings.
- Figure 1 shows the device for localization of the melt of the active zone of a nuclear reactor, made in accordance with the claimed invention.
- the claimed invention works as follows.
- Figure 1 shows a device for localizing the melt (1) of the core of a nuclear reactor, which contains a trap (2) of the melt (1) installed under the bottom of the reactor vessel and provided with a cooled shell in the form of a multilayer vessel, a filler (3) for diluting the melt (1) ) located in the said multilayer vessel, the lower support (4), consisting of a horizontal sectional, continuous or divided, embedded plate (5) installed under a multilayer vessel in the concrete of the reactor shaft (6), having radial supports (7).
- radial bearings (8) are made, based on the radial bearings (7) of the horizontal embedded plate (5).
- the radial bearings (7) of the horizontal embedded plate (5) and the radial bearings (8) of the melt trap (2) (1) are connected by means of clamps (9), each of the radial supports (8) of the melt trap (2) (1) and horizontal embedded plate (5), as well as the latch (9) has holes (10) oval.
- the melt (1) mainly accumulates in the central part of the bottom of the melt trap (2) (1).
- the melt temperature is about 2500 ° C, which leads to the expansion of both the melt trap (2) (1) and the radial supports (7), (8).
- the presence of radial bearings (8) in the lower part of the melt trap (2) (1) and radial bearings (7) at the horizontal embedded plate (5) connected to each other by means of clamps (9) with oval holes (10) shape allows you to maintain the integrity of the bottom of the melt trap, horizontal embedded plate (5) in the floor of the shaft (6) of the reactor with non-uniform axial thermal expansions of the melt trap due to the sliding of the clamps (9) in the oval holes (10) of the radial supports in the axial (vertical) the plane that providing It is provided with a small mechanical axial play of the clamps (9) located in the oval holes (10).
- the main shock and thermal loads are on the side inner wall of the melt trap (2) (1).
- the load is redistributed between the radial supports (7) of the lower embedded plate and the radial supports (8) of the melt trap.
- Part of the mechanical shock is absorbed by the elastic 5 vibrations of the bottom of the melt trap, part is absorbed by the elastic vibrations of the radial supports (7), (8), and part is damped by the fastenings of the melt trap to the lower support due to the location of the fasteners in the oval holes (10) of the radial supports (7) , (8) and structural backlash mounts in these supports.
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 (8)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CA3066161A CA3066161C (en) | 2018-09-25 | 2018-12-28 | Reactor molten core localization device |
EP18922104.7A EP3859747A4 (en) | 2018-09-25 | 2018-12-28 | DEVICE FOR LOCATING THE MELTED MASS OF THE ACTIVE ZONE OF A NUCLEAR REACTOR |
EA201992738A EA039179B1 (ru) | 2018-09-25 | 2018-12-28 | Устройство локализации расплава активной зоны ядерного реактора |
JP2019572489A JP7332844B2 (ja) | 2018-09-25 | 2018-12-28 | 原子炉の炉心溶融物のローカライズ装置 |
CN201880043383.7A CN111226291B (zh) | 2018-09-25 | 2018-12-28 | 核反应堆堆芯熔化定位装置 |
US16/627,744 US11610693B2 (en) | 2018-09-25 | 2018-12-28 | Reactor molten core localization device |
KR1020197038905A KR102440126B1 (ko) | 2018-09-25 | 2018-12-28 | 원자로의 노심 융해물의 로컬라이즈 장치 |
BR112019028211-4A BR112019028211B1 (pt) | 2018-09-25 | 2018-12-28 | Dispositivo de localização de fusão da zona ativa do reator nuclear |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RU2018133761A RU2696619C1 (ru) | 2018-09-25 | 2018-09-25 | Устройство локализации расплава активной зоны ядерного реактора |
RU2018133761 | 2018-09-25 |
Publications (1)
Publication Number | Publication Date |
---|---|
WO2020067919A1 true WO2020067919A1 (ru) | 2020-04-02 |
Family
ID=67586524
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/RU2018/000898 WO2020067919A1 (ru) | 2018-09-25 | 2018-12-28 | Устройство локализации расплава активной зоны ядерного реактора |
Country Status (9)
Country | Link |
---|---|
US (1) | US11610693B2 (ru) |
EP (1) | EP3859747A4 (ru) |
JP (1) | JP7332844B2 (ru) |
KR (1) | KR102440126B1 (ru) |
CN (1) | CN111226291B (ru) |
EA (1) | EA039179B1 (ru) |
JO (1) | JOP20190311A1 (ru) |
RU (1) | RU2696619C1 (ru) |
WO (1) | WO2020067919A1 (ru) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU2736544C1 (ru) * | 2020-03-20 | 2020-11-18 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
RU2758496C1 (ru) * | 2020-12-29 | 2021-10-29 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
RU2767599C1 (ru) * | 2020-12-29 | 2022-03-17 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
Families Citing this family (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU2736545C1 (ru) * | 2020-03-20 | 2020-11-18 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
RU2749995C1 (ru) * | 2020-11-10 | 2021-06-21 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
RU2750204C1 (ru) * | 2020-11-10 | 2021-06-24 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
RU2771463C1 (ru) * | 2021-10-26 | 2022-05-04 | Акционерное Общество "Атомэнергопроект" | Опорная система корпуса устройства локализации расплава |
RU2771340C1 (ru) * | 2021-10-26 | 2022-04-29 | Акционерное Общество "Атомэнергопроект" | Опорная система корпуса устройства локализации расплава |
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2018
- 2018-09-25 RU RU2018133761A patent/RU2696619C1/ru active
- 2018-12-28 WO PCT/RU2018/000898 patent/WO2020067919A1/ru unknown
- 2018-12-28 EP EP18922104.7A patent/EP3859747A4/en active Pending
- 2018-12-28 CN CN201880043383.7A patent/CN111226291B/zh active Active
- 2018-12-28 JP JP2019572489A patent/JP7332844B2/ja active Active
- 2018-12-28 KR KR1020197038905A patent/KR102440126B1/ko active IP Right Grant
- 2018-12-28 EA EA201992738A patent/EA039179B1/ru unknown
- 2018-12-28 US US16/627,744 patent/US11610693B2/en active Active
-
2019
- 2019-12-31 JO JOP/2019/0311A patent/JOP20190311A1/ar unknown
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WO1988009998A1 (fr) * | 1987-06-11 | 1988-12-15 | Societe Des Electrodes & Refractaires Savoie | Dispositif pour empecher la penetration dans le sol d'un coeur de reacteur nucleaire fondu |
RU2398294C1 (ru) | 2009-04-15 | 2010-08-27 | Открытое акционерное общество "Атомэнергопроект" | Устройство для локализации расплава активной зоны ядерного реактора |
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Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU2736544C1 (ru) * | 2020-03-20 | 2020-11-18 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
RU2758496C1 (ru) * | 2020-12-29 | 2021-10-29 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
RU2767599C1 (ru) * | 2020-12-29 | 2022-03-17 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
WO2022146184A1 (ru) * | 2020-12-29 | 2022-07-07 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
WO2022146185A1 (ru) * | 2020-12-29 | 2022-07-07 | Акционерное Общество "Атомэнергопроект" | Система локализации и охлаждения расплава активной зоны ядерного реактора |
Also Published As
Publication number | Publication date |
---|---|
BR112019028211A2 (pt) | 2021-04-13 |
EP3859747A4 (en) | 2022-07-06 |
JP7332844B2 (ja) | 2023-08-24 |
EA039179B1 (ru) | 2021-12-14 |
JOP20190311A1 (ar) | 2020-03-25 |
CN111226291B (zh) | 2023-08-11 |
CN111226291A (zh) | 2020-06-02 |
KR20200102918A (ko) | 2020-09-01 |
JP2022511136A (ja) | 2022-01-31 |
KR102440126B1 (ko) | 2022-09-05 |
US11610693B2 (en) | 2023-03-21 |
EP3859747A1 (en) | 2021-08-04 |
EA201992738A1 (ru) | 2020-09-16 |
US20210296013A1 (en) | 2021-09-23 |
RU2696619C1 (ru) | 2019-08-05 |
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