CN205541968U - Intrinsic safe constrain cooling system of containment - Google Patents
Intrinsic safe constrain cooling system of containment Download PDFInfo
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- CN205541968U CN205541968U CN201521068700.0U CN201521068700U CN205541968U CN 205541968 U CN205541968 U CN 205541968U CN 201521068700 U CN201521068700 U CN 201521068700U CN 205541968 U CN205541968 U CN 205541968U
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- containment
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- constrain
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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
Abstract
The utility model belongs to the technical field of the constrain cooling system of containment, concretely relates to intrinsic safe constrain cooling system of containment can carry on constrainly to the containment after the reactor takes place loss of coolant accident and the steam pipe accident of breaking and the cooling. Reactor pressure vessel is arranged in the steel containment, and the reactor is arranged in reactor pressure vessel, and during circular heap of chamber of lowest bid height in the steel containment was arranged to reactor pressure vessel's lower part, the upper portion submergence of steel containment was in the shielding poind, upper portion space in the steel containment be the dry well, and lower part space in the steel containment be the wet well, and formation independent space is separately separated through reinforced concrete wall and floor to dry well and wet well, is dry well and the sole interface channel of wet well communicating pipe, the lower part of wet well is constrain pond, and the upper portion of wet well is the headroom. The utility model discloses can carry on constrainly to the containment after the reactor takes place loss of coolant accident and the steam pipe accident of breaking and the cooling.
Description
Technical field
This utility model belongs to the constrain cooling system technical field of containment, is specifically related to a kind of inherently safe
The constrain cooling system of containment, can be to safety after reactor generation loss of-coolant accident (LOCA) and steam pipe break accident
Shell carries out constrain and cooling.
Background technology
The constrain cooling system of containment is reply nuclear reactor designs basis accident and the ad hoc safety of major accident
Facility, the existing constrain cooling system of nuclear power reactor containment mostly uses enabling fashion and passive mode,
System design is complex, and cost is high, there is also the risk of thrashing.To the mould using little metal containment
For block formula reactor, owing to power is little, lose the economical efficiency of scale, how to design the simplest but also reliable
The constrain cooling system of containment, is the common difficulty of whole world nuclear energy circle.
Summary of the invention
The purpose of this utility model is to provide a kind of constrain cooling system of inherently safe containment, solves peace
The inherent safety of the complete constrain cooling system of shell.
For reaching above-mentioned purpose, technical solution adopted in the utility model is:
A kind of constrain cooling system of inherently safe containment, reactor pressure vessel is positioned in metal containment,
Reactor is positioned in reactor pressure vessel, and the lower disposed of reactor pressure vessel is minimum in metal containment
In the circular heap chamber of elevation location, the upper submerged of metal containment is in shielding poind;Upper in metal containment
Space, portion is dry-well, and the lower space in metal containment is wet-well, and dry-well and wet-well pass through reinforced concrete wall
Body and floor separate the space that formation is the most independent, and communicating pipe is dry-well and the unique interface channel of wet-well;
The bottom of wet-well is constrain pond, and the top of wet-well is headroom.
Described shield water water loading amount is about 3000m3。
Having the beneficial effect that acquired by this utility model
This utility model designed system is simple and reliable, has inherent safety, it is not necessary to any active means,
Eliminate the critical valves that may be present tripping of traditional passive mode and cause the constrain cooling system of passive containment
The risk that system lost efficacy;This utility model designed system can be greatly decreased thickness and the cost of metal containment.This
Utility model system is simple, it is not necessary to any active means and valve event, can realize design basis accident
Within latter 7 days, need not Operator actions.Shielding poind can realize the long-term cooling of containment after moisturizing.Intrinsic
The constrain cooling system of containment of safety is set by the dry-well of metal containment, wet-well, communicating pipe, shielding poind etc.
Executing composition, communicating pipe is by the dry-well of containment, wet-well connection.Metal containment is immersed in shielding poind.When
When there is Mass and energy release accident (loss of-coolant accident (LOCA) and steam pipe break accident), it is not required to any enabling signal and valve
Door action, relies on the natural principles such as conduction, convection current that the heat in containment is passed to shielding poind, shielding
Pond relies on water evaporation to transfer heat to ultimate heat sink air again.When there is Mass and energy release accident,
Being not required to any enabling signal and valve event, dry-well and the wet-well of metal containment are automatically obtained two by communicating pipe
Person's pressure balance thus reduce containment drywell pressure.Shielding poind has biological shielding, containment cools down,
The several functions such as the hot trap of emergency reactor Residual heat removal and offer reactor refuling water.Metal containment wet-well
In constrain pond after accident, also can flood heap chamber and reactor pressure vessel to Reactor cavity flooding, it is ensured that anti-
Answer core pressure vessel integrity after major accident, prevent radioactivity from escaping.
Accompanying drawing explanation
Fig. 1 is system structure schematic diagram of the present utility model;
Wherein: 1, metal containment;2, dry-well;3, wet-well;4, communicating pipe;5, shielding poind;6、
Reactor;7, constrain pond;8, heap chamber;9, reactor pressure vessel.
Detailed description of the invention
With specific embodiment, this utility model is described in detail below in conjunction with the accompanying drawings.
As it is shown in figure 1, for be applicable to the integrated module formula reactor that thermal power is 200~1000MW, this
The constrain cooling system of containment inherently safe described in utility model include metal containment 1, dry-well 2, wet-well 3,
Communicating pipe 4, shielding poind 5, shielding poind 5 water loading amount is about 3000m3, can be after design basis accident 7
It need not Operator actions.Shielding poind 5 can realize the long-term cooling of containment after moisturizing.
Reactor pressure vessel 9 is positioned in metal containment 1, and reactor 6 is positioned in reactor pressure vessel 9.
The lower part (containing low head and reactor core section cylinder) of reactor pressure vessel 9 is arranged in metal containment 1
In the circular heap chamber 8 of low elevation location.Upper part (containing cylinder section and the upper cover) submergence of metal containment 1
In shielding poind 5.Upper space in metal containment 1 is dry-well 2, the lower space in metal containment 1
For wet-well 3, dry-well 2 separates, by reinforced concrete wall and floor, the sky that formation is the most independent with wet-well 3
Between, communicating pipe 4 is dry-well 2 and the unique interface channel of wet-well 3.Loss of-coolant accident (LOCA) and steam pipe break accident
After can produce substantial amounts of steam or steam water interface in dry-well 2 so that dry-well 2 pressure and temp raise, steam
Vapour or steam water interface are able to by the constrain pond 7 entered communicating pipe 4 in wet-well 3 under pressure differential drives
Condensation.The bottom of wet-well 3 is constrain pond 7, and the top of wet-well 3 is headroom.
Metal containment 1 is immersed in shielding poind 5.When Mass and energy release accident (loss of-coolant accident (LOCA) and steam occur
Shape pipe breaking accident) time, it is not required to any enabling signal, relies on the natural principles such as conduction, convection current by containment 1
Interior heat passes to shielding poind 5, and shielding poind 5 relies on water evaporation to transfer heat to ultimate heat sink again
Air.
When there is Mass and energy release accident (loss of-coolant accident (LOCA) and steam pipe break accident), being not required to any startup and believing
Number, dry-well 2 and the wet-well 3 of metal containment 1 drop by communicating pipe 4 being automatically obtained both pressure balances
Lower security shell dry-well 2 pressure.
The hot trap of shielding poind 5 has biological shielding, containment 1 cools down, reactor 6 is met an urgent need Residual heat removal
And provide reactor 6 to reload with several functions such as water.
Heap also can be flooded to heap chamber 8 water filling after accident in constrain pond 7 in the wet-well 3 of metal containment 1
Chamber and reactor pressure vessel 9 low head, it is ensured that the low head of reactor pressure vessel 9 is not fused.
Claims (2)
1. the constrain cooling system of inherently safe containment, it is characterised in that: reactor pressure vessel (9)
Being positioned in metal containment (1), reactor (6) is positioned in reactor pressure vessel (9), reactor pressure
The lower disposed of container (9) in metal containment (1) in the circular heap chamber (8) of lowest bid high position, steel
The upper submerged of containment (1) is in shielding poind (5);Upper space in metal containment (1) is dry
Well (2), the lower space in metal containment (1) is wet-well (3), and dry-well (2) leads to wet-well (3)
Crossing reinforced concrete wall and floor separates the space that formation is the most independent, communicating pipe (4) is dry-well (2)
Interface channel unique with wet-well (3);The bottom of wet-well (3) is constrain pond (7), wet-well (3)
Top be headroom.
The constrain cooling system of inherently safe containment the most according to claim 1, it is characterised in that:
Described shielding poind (5) water loading amount is about 3000m3。
Priority Applications (1)
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CN201521068700.0U CN205541968U (en) | 2015-12-21 | 2015-12-21 | Intrinsic safe constrain cooling system of containment |
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CN201521068700.0U CN205541968U (en) | 2015-12-21 | 2015-12-21 | Intrinsic safe constrain cooling system of containment |
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CN205541968U true CN205541968U (en) | 2016-08-31 |
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Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN106898389A (en) * | 2015-12-21 | 2017-06-27 | 中国核动力研究设计院 | A kind of constrain cooling system of inherently safe containment |
CN108010591A (en) * | 2017-12-18 | 2018-05-08 | 中广核研究院有限公司 | A kind of multifunctional pressure container reactor pit structure and reactor safety shell structure |
-
2015
- 2015-12-21 CN CN201521068700.0U patent/CN205541968U/en active Active
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN106898389A (en) * | 2015-12-21 | 2017-06-27 | 中国核动力研究设计院 | A kind of constrain cooling system of inherently safe containment |
CN108010591A (en) * | 2017-12-18 | 2018-05-08 | 中广核研究院有限公司 | A kind of multifunctional pressure container reactor pit structure and reactor safety shell structure |
CN108010591B (en) * | 2017-12-18 | 2024-01-19 | 中广核研究院有限公司 | Multifunctional pressure vessel pit stacking structure and reactor containment structure |
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