CN202816402U - Passive containment spraying-submerged cooling system - Google Patents
Passive containment spraying-submerged cooling system Download PDFInfo
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- CN202816402U CN202816402U CN2012202776009U CN201220277600U CN202816402U CN 202816402 U CN202816402 U CN 202816402U CN 2012202776009 U CN2012202776009 U CN 2012202776009U CN 201220277600 U CN201220277600 U CN 201220277600U CN 202816402 U CN202816402 U CN 202816402U
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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
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Abstract
The utility model belongs to an engineered safety system for a nuclear reactor, and in particular relates to a passive containment spraying-submerged cooling system. The passive containment spraying-submerged cooling system comprises a reinforced concrete shield building, wherein a containment is arranged in the reinforced concrete shield building, the containment and the reinforced concrete shield building are fixed together by a steel-concrete composite structure, a water-stop annular space is formed between the reinforced concrete shield building and the steel-concrete composite structure, and a passive containment spraying device is arranged above the containment. The passive containment spraying-submerged cooling system disclosed by the utility model has the advantage of realizing short-term and long-term cooling of the containment when the reactor is subjected to loss of coolant accident or main stream line rupture accident in combination with multiple extreme accidents, such as station blackout. The annular space between the containment and the shield building is of a water-stop structure and can be used for collecting residual spraying water.
Description
Technical field
The utility model belongs to a kind of nuclear reactor engineered safety system, is specifically related to a kind of Passive containment cooling system.
Background technology
Containment is as the engineered safeguards features of nuclear power plant, but the protective reaction heap avoids the harm of external event, last one barrier that contains as the nuclear reactor radioactivity after the accident, but protection of the environment and the public avoid excess radiation.Behind reactor generation loss of-coolant accident (LOCA) or main steam pipe break accident, a large amount of mass-energy is released in the containment, causes that containment temperature and pressure raise rapidly.For preventing the containment over-temp and over-pressure, must in time the containment heat be derived.At present, the common nuclear power plant in countries in the world mostly adopts inner active containment spray system to carry out decrease temperature and pressure, must configuration safe level emergency power pack.When the multiple extreme accident that Fukushima nuclear accident and so on occurs superposeed the station blackout that causes, active system all can't start.
Though the AP1000 unit of US Westinghouse company's exploitation has designed Passive containment cooling system, but its elevated tank is given shielding factory building antidetonation because of liquid-solid coupling effect and is brought totally unfavorable impact, metal containment is provided with upper water flow sharing system and the air guide structure of bulky complex, and cost and maintenance cost are high.
Summary of the invention
The purpose of this utility model is to provide a kind of system simple, and cost and maintenance cost are low, and reliability is high, and the non-passive safety shell that can solve the multiple rear containment short-term of extreme accident stack and long-term cooling sprays-flood cooling system.
The utility model is to realize like this, a kind of non-passive safety shell sprays-floods cooling system, it comprises reinforced concrete shielding factory building, be provided with containment in the reinforced concrete shielding factory building, be fixed together by steel-concrete composite structure between containment and the reinforced concrete shielding factory building, form the water-stop annular space between reinforced concrete shielding factory building and the steel-concrete composite structure, the top of containment is provided with non-passive safety shell spray equipment.
The utility model has the advantages that, can realize containment short-term and long-term cooling with non-enabling fashion during the multiple extreme accidents such as reactor loss of-coolant accident (LOCA) or main steam line rupture accident stack station blackout.Annular space between containment and the shielding factory building is watertight construction, can collect the spray residual water.During normal reactor operation, be in the dry-well state, collect the spray residual water after the accident and flood containment, avoided flooding for a long time containment inner atmosphere condensation trouble, a containment anticorrosion difficult problem and the liquid-solid coupling effect of earthquake that causes because of containment during the normal reactor operation, system is simple, cost and maintenance cost are low, reliability is high, further improves security and the economy of nuclear energy.
Description of drawings
Fig. 1 is that a kind of non-passive safety shell provided by the utility model sprays-flood the cooling system structure synoptic diagram.
Among the figure, 1 non-passive safety shell spray equipment, 2 containments, 3 reinforced concrete shielding factory building, 4 water-stop annular spaces, 5 steel-concrete composite structure, 6 steam (vapor) outlets, 7 steam-condensations, 8 reactors, 9 pressurized air.
Embodiment
Below in conjunction with the drawings and specific embodiments the utility model is elaborated.
As shown in Figure 1, a kind of non-passive safety shell sprays-flood cooling system, and it comprises reinforced concrete shielding factory building 3, be provided with containment 2 in the reinforced concrete shielding factory building 3, containment 2 and the reinforced concrete shielding factory building 3 formation steel-concrete composite structure 5 that below ground elevation, fits together, the top of containment 2 is provided with non-passive safety shell spray equipment 1, the inside of containment 2 is provided with reactor 8, the top of reinforced concrete shielding factory building 3 has steam (vapor) outlet 6, containment 2, reinforced concrete shielding factory building 3 forms water-stop annular space 4 with steel-concrete composite structure 5 more than ground elevation, when the spray in the water-stop annular space 4 floods the water evaporation, can be discharged in the atmosphere by steam (vapor) outlet 6.
Present embodiment metal containment internal diameter is 28m, and the water-stop annular space width between metal containment and the reinforced concrete shielding factory building is 1.2m, and heat output of reactor is about 500MW.Behind reactor generation loss of-coolant accident (LOCA) or main steam pipe break accident, a large amount of mass-energy is released in the metal containment, causes that containment temperature and pressure raise rapidly.For preventing the containment over-temp and over-pressure, must in time the containment heat be derived.
The non-passive safety shell sprays-floods cooling system after receiving metal containment alarm for high voltage threshold signal (pressure is 0.24MPa), non-passive safety shell spray equipment starts automatically, and dependence pressurized air sprays to the dome outside surface of metal containment with water and flow to the cylinder outside surface of metal containment under Action of Gravity Field.Spray in the water part of metal containment outside surface through the heating vaporization, along with the latent heat of vaporization of steam with metal containment heat transferred ultimate heat sink-atmosphere, remaining spray residual water compiles at water-stop annular space 4.Along with the spray residual water constantly compiles, the water level of water-stop annular space 4 constantly raises, and floods gradually the cylinder section of metal containment.Water spray in non-passive safety shell spray equipment is complete, and the water level that floods of water-stop annular space reaches the about 15m of peak level, and the metal containment that is in flooding continues to be cooled off by flooding water convection heat transfer' heat-transfer by convection and evaporation.Because the waste heat of late phase reaction heap constantly reduces, containment amount of cooling water and cooldown rate are lower, and it floods the water yield can realize that the containment cooling reached more than 7 days.
The non-passive safety shell sprays-floods cooling system and is comprised of the water-stop annular space between non-passive safety shell spray equipment, metal containment and the reinforced concrete shielding factory building.Realize successively that according to spraying first two stages of flooding afterwards the metal containment short-term reaches long-term (〉 7 days behind reactor loss of-coolant accident (LOCA) or the main steam line rupture accident) cooling.System sprayed outside to metal containment at the accident initial stage.By non-passive safety shell spray equipment water is sprayed at the metal containment outside surface, shower water forms moisture film at the metal containment outside surface and is heated evaporation, produce steam, take away the metal containment heat by the steam latent heat of vaporization, with thermal release to ultimate heat sink---atmosphere, realize fast the metal containment decrease temperature and pressure.Rely on the spray residual water to compile at the water-stop annular space in the accident middle and later periods and automatically flood metal containment.The metal containment heat is given by convection heat transfer' heat-transfer by convection and is flooded water, flood water and be heated evaporation, with thermal release to ultimate heat sink---atmosphere, thus continue the cooling steel containment.Metal containment and the reinforced concrete shielding factory building formation steel-concrete composite structure that is close together in the annular space bottom is realized the water-stop function.The water-stop annular space is in the dry-well state during normal reactor operation, collect the spray residual water and flood containment after accident.
Behind reactor generation loss of-coolant accident (LOCA) or main steam pipe break accident, initial stage containment mass-energy burst size is large, the containment increasing temperature and pressure is rapid, the non-passive safety shell sprays-flood steam that cooling system produces by spray constantly to be reduced with the waste heat of the efficient fast cooling steel containment late phase reaction of latent heat of vaporization heap, containment amount of cooling water and cooldown rate are lower, the non-passive safety shell sprays-floods cooling system and relies on the convection heat transfer' heat-transfer by convection flood water and evaporation constantly with containment heat transferred atmosphere, can realize long-term (〉 7 days of containment) cool off.
Claims (1)
1. a non-passive safety shell sprays-floods cooling system, it is characterized in that: it comprises reinforced concrete shielding factory building (3), be provided with containment (2) in the reinforced concrete shielding factory building (3), containment (2) forms steel-concrete composite structure (5) with reinforced concrete shielding factory building (3) below ground elevation, reinforced concrete shielding factory building (3) forms water-stop annular space (4) with steel-concrete composite structure (5) more than ground elevation, the top of containment (2) is provided with non-passive safety shell spray equipment (1).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012202776009U CN202816402U (en) | 2012-06-13 | 2012-06-13 | Passive containment spraying-submerged cooling system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012202776009U CN202816402U (en) | 2012-06-13 | 2012-06-13 | Passive containment spraying-submerged cooling system |
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| Publication Number | Publication Date |
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| CN202816402U true CN202816402U (en) | 2013-03-20 |
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| CN2012202776009U Expired - Lifetime CN202816402U (en) | 2012-06-13 | 2012-06-13 | Passive containment spraying-submerged cooling system |
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| CN (1) | CN202816402U (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103489489A (en) * | 2012-06-13 | 2014-01-01 | 中国核动力研究设计院 | Passive containment spraying-submerged cooling system |
| CN104409111A (en) * | 2014-11-20 | 2015-03-11 | 中科华核电技术研究院有限公司 | Energy control system for externally-often-submerged steel safety shell |
| GB2533829A (en) * | 2014-06-30 | 2016-07-06 | China Nuclear Power Eng Co Ltd | Active-combined passive containment cooling system |
| CN105788675A (en) * | 2016-05-06 | 2016-07-20 | 上海核工程研究设计院 | Long-time containment cooling system of nuclear power station |
| CN105825899A (en) * | 2016-05-06 | 2016-08-03 | 上海核工程研究设计院 | Containment cooling system of nuclear power station |
| 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 |
| CN111370150A (en) * | 2020-03-17 | 2020-07-03 | 中国核动力研究设计院 | Outer wall flow equalizing structure for containment vessel |
| CN112599257A (en) * | 2020-12-01 | 2021-04-02 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Marine capillary force driven containment heat exporting system |
-
2012
- 2012-06-13 CN CN2012202776009U patent/CN202816402U/en not_active Expired - Lifetime
Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103489489A (en) * | 2012-06-13 | 2014-01-01 | 中国核动力研究设计院 | Passive containment spraying-submerged cooling system |
| GB2533829A (en) * | 2014-06-30 | 2016-07-06 | China Nuclear Power Eng Co Ltd | Active-combined passive containment cooling system |
| GB2533829B (en) * | 2014-06-30 | 2017-03-29 | China Nuclear Power Eng Co Ltd | Active-combined passive containment cooling system |
| CN104409111A (en) * | 2014-11-20 | 2015-03-11 | 中科华核电技术研究院有限公司 | Energy control system for externally-often-submerged steel safety shell |
| 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 |
| CN105788675A (en) * | 2016-05-06 | 2016-07-20 | 上海核工程研究设计院 | Long-time containment cooling system of nuclear power station |
| CN105825899A (en) * | 2016-05-06 | 2016-08-03 | 上海核工程研究设计院 | Containment cooling system of nuclear power station |
| CN111370150A (en) * | 2020-03-17 | 2020-07-03 | 中国核动力研究设计院 | Outer wall flow equalizing structure for containment vessel |
| CN111370150B (en) * | 2020-03-17 | 2022-02-11 | 中国核动力研究设计院 | Outer wall flow equalizing structure for containment vessel |
| CN112599257A (en) * | 2020-12-01 | 2021-04-02 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Marine capillary force driven containment heat exporting system |
| CN112599257B (en) * | 2020-12-01 | 2024-03-15 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Marine capillary force driven containment heat export system |
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| Date | Code | Title | Description |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term |
Granted publication date: 20130320 |
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| CX01 | Expiry of patent term |