CN203397717U - Passive containment cooling device - Google Patents
Passive containment cooling device Download PDFInfo
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- CN203397717U CN203397717U CN201320464462.XU CN201320464462U CN203397717U CN 203397717 U CN203397717 U CN 203397717U CN 201320464462 U CN201320464462 U CN 201320464462U CN 203397717 U CN203397717 U CN 203397717U
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- evaporator
- cooling tower
- air cooling
- containment
- reactor
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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 discloses a passive containment cooling device which comprises a high-level refueling pool for storing cooling water, an evaporator, an air cooling tower, a plurality of pipelines and a refrigerating agent, wherein a reactor pit is arranged in a containment, a reactor pressure container is arranged in the reactor pit, the high-level refueling pool is arranged in the containment and positioned above the reactor pit, the high-level refueling pool is communicated with the reactor pit through an isolating valve, the evaporator is positioned in the reactor pit, the air-cooling tower is positioned outside the containment and is high than the reactor pit, the pipelines are connected between an outlet of the evaporator and an inlet in the upper end of the air cooling tower as well as between an outlet in the lower end of the air cooling tower and an inlet of the evaporator; the refrigerating agent flows in a circulating channel formed by the evaporator, the air cooling tower and the pipelines. According to the passive containment cooling device, the after-heat removal function of the containment under the accident can be realized without depending on an external power supply, the stability of the passive containment cooling device is improved, and the safety of a nuclear power plant is improved.
Description
Technical field
The utility model relates to a kind of nuclear reactor safety device, relates in particular to a kind of non-passive safety shell cooling device.
Background technology
The use of nuclear power is the important breakthroughs of the mankind in energy utilization history, utilize nuclear fission reaction, nuclear power plant can produce the incomparable high-energy output of other all traditional fossil energies, and these high-energy outputs often only need to expend a small amount of nuclear fuel.The characteristic of this low input high production, makes the utilization of mankind's pay attention to day by day to nuclear energy, and continues to increase the research and development in nuclear energy field, and even to this day, nuclear energy has become the important energy source ingredient of many countries in the world.Yet, nuclear power when thering is high value, its harm that may bring also make us talk core look and become.In using the process of nuclear power, if protect improper, cause major accidents such as occurring nuclear leakage, will to the environment of nuclear power plant's periphery and even the whole mankind brings and serious nuclear pollution disaster.
In presurized water reactor, ，Yi loop refers to that the heat energy that chilled water is emitted nuclear fuel takes reactor pressure vessel out of, and enters steam generator, by thousands of heat-transfer pipes, heat is passed to the secondary circuit water outside pipe, makes water boiling produce steam; Cooling water flow, after steam generator, then is sent into reactor pressure vessel by main pump, so back and forth circulation.When the security incident of reactor-loop generation large break dehydration, chilled water in reactor pressure vessel tails off, therefore, the temperature of reactor pressure vessel can rise rapidly, if cooling and the heat of reactor pressure vessel is derived not in time, just may make temperature and the pressure rising of containment, thereby cause more serious security incident, therefore, need to further safety guarantee be set to containment.The inner operated by rotary motion refuelling pool of current containment, when reactor pressure vessel temperature anomaly, refuelling pool actively injects water in reactor pit and carries out cooling to reactor pressure vessel.Yet, the existing type of cooling adopts actively water filling of external ac power source on the one hand, cannot tackle the situation that occurs power-off when security incident occurs, it is can only the short time cooling on the other hand, still the heat in containment cannot be exported to outside containment, after accident continues for a long time, containment temperature and pressure still rise, and security is not high.
Utility model content
The purpose of this utility model is to provide a kind of external ac power source that do not rely on, and realizes the waste heat export function of containment under accident, improves the non-passive safety shell cooling device of the security of nuclear power plant.
To achieve these goals, the utility model provides a kind of non-passive safety shell cooling device, being applicable to derives the decay heat in reactor pressure vessel, comprise the high-order refuelling pool that stores chilled water, evaporator, air cooling tower, some pipelines and cold-producing medium, in described containment, there is reactor pit, described reactor pressure vessel is placed in described reactor pit, described high-order refuelling pool is placed in described containment and is positioned at the top of described reactor pit, described high-order refuelling pool is communicated with described reactor pit by isolation valve, described evaporator is placed in described reactor pit, described air cooling tower is positioned at outside described containment and higher than described reactor pit, described pipeline is connected between the outlet of described evaporator and the entrance of described air cooling tower upper end and between the outlet and the entrance of described evaporator of described air cooling tower lower end, described cold-producing medium is at described evaporator, in the circulation passage that air cooling tower and pipeline form, flow.
Preferably, between one end of described pipeline and the entrance of described air cooling tower upper end, be provided with steam turbine.The heat that absorbs the chilled water in described reactor pit due to described evaporator flashes to cold-producing medium to have the steam of larger kinetic energy, therefore, by described steam turbine is set, make the running of Steam Actuation steam turbine, thereby the energy of steam is passed to steam turbine, on the one hand steam is played to cooling effect, can produce power on the other hand and drive miscellaneous part running.
Particularly, described air cooling tower upper end is provided with fan, and described fan is connected with the output terminal of described steam turbine.Described fan both can blow air cooling tower inside, and the cooling effect of strengthening air cooling tower, also can form stronger circuit cycle driving force simultaneously, accelerates the circuit cycle between described evaporator and air cooling tower, thereby the waste heat of reactor is derived rapidly; And the driving force running that described fan utilizes described steam turbine to produce, does not drive by any external power source, and therefore, it is not subject to the impact of external factor, stability and safe.
Preferably, between one end of described pipeline and the outlet of described air cooling tower lower end, be provided with condensation water tank.Described condensation water tank can get up steam liquid described refrigerant collecting cooling and that produce in described air cooling tower be transported in the evaporator in reactor pit, thereby can prevent that the steam in air cooling tower is fully not cooling directly in described pipeline Returning evaporimeter.
Preferably, the loop of described reactor pressure vessel is provided with blowdown line, and described blowdown line is provided with blowdown valve, and the output terminal of described blowdown line is positioned at described containment.While there is large break dehydration in Dang Yi loop, because a circuit cools water tails off, cooled reactor pressure vessel rapidly, the temperature of reactor pressure vessel inside and pressure can raise fast, therefore, utilize described blowdown line Dui Yi loop to carry out quick pressure releasing, on the one hand can carry out step-down in inside, Dui Yi loop, after a loop step-down, can make on the other hand chilled water in reactor pit more easily and rapidly Cong Yi loop cut place inject.In addition, the output terminal of described blowdown line is positioned at described containment and can prevents that nuclear pollution material is discharged into outside containment, causes nuclear leakage.
Preferably, described evaporator vertically or is obliquely placed in described reactor pit, and the outlet of described evaporator is positioned at upper end, and the entrance of described evaporator is positioned at lower end.
The utility model arranges evaporator in described reactor pit, and at described containment, air cooling tower is set outward, utilizes pipeline to be connected between described air cooling tower and described evaporator, thereby forms cooling circuit; When reactor-loop generation security incident, the chilled water that is positioned at the high-order refuelling pool of containment is injected to described reactor pit, reactor pit is flooded, thereby cooled reactor pressure vessel, recycling cold-producing medium constantly circulates in loop, thereby takes the heat in described reactor pit to described air cooling tower, realizes and carries out cooling to reactor pressure vessel, prevent that reactor pressure vessel Yin Yi loop dehydration from causing reactor internal temperature sharply to rise, and causes more serious security incident; Compared with prior art, the utility model just can not realized under accident the waste heat export function of containment owing to relying on external ac power source, therefore, has improved the stability of containment cooling system, has improved the security of nuclear power plant simultaneously.
Accompanying drawing explanation
Fig. 1 is the structural representation of the utility model non-passive safety shell cooling device.
Fig. 2 be in the utility model non-passive safety shell cooling device cold-producing medium flow to schematic diagram.
Embodiment
For the effect that describes technology contents of the present utility model, structural attitude in detail, realizes, below in conjunction with embodiment and coordinate accompanying drawing to be explained in detail.
As shown in Figure 1, the utility model non-passive safety shell cooling device is applicable to the decay heat in reactor pressure vessel 1 to derive, and it comprises high-order refuelling pool 2, evaporator 3, air cooling tower 4, some pipelines 5 and the cold-producing medium 6 that stores chilled water; In containment 7, have reactor pit 71, reactor pressure vessel 1 is placed in reactor pit 71; High-order refuelling pool 2 is placed in containment 7 and is positioned at the top of reactor pit 71, high-order refuelling pool 2 is communicated with described reactor pit 71 by isolation valve 21, high-order refuelling pool 2 is in order to guarantee when there is emergency episode higher than reactor pit 71, water in pond can inject in reactor pit 71 automatically, reactor pressure vessel 1 is flooded, thereby remove use pumping for water pump from, realize non-active water filling, the situation that occurs power-off during Accident prevention and cannot water filling occurs, improves security.Evaporator 3 is placed in reactor pit 71, and evaporator 3 is vertically placed in reactor pit 71, and the outlet of evaporator 3 is positioned at upper end, and the entrance of evaporator 3 is positioned at lower end.Certainly, evaporator 3 also can be placed in reactor pit 71 obliquely herein.When high-order refuelling pool 2 floods reactor pressure vessel 1, evaporator 3 is in water surface below.Air cooling tower 4 is positioned at outside containment 7 and higher than reactor pit 71, can guarantee cold-producing medium automatic back flow like this.Pipeline 5 is connected between the outlet of evaporator 3 and the entrance of air cooling tower 4 upper ends, and another pipeline 5 is connected between the outlet of air cooling tower 4 lower ends and the entrance of evaporator 3, in the circulation passage that cold-producing medium 6 forms at evaporator 3, air cooling tower 4 and pipeline 5, flows.
Again as shown in Figure 1, between one end of pipeline 5 and the import of air cooling tower 4 upper ends, be provided with steam turbine 8.Air cooling tower 4 upper ends are provided with two fans 41, and fan 41 is positioned at the both sides of steam turbine 8, and are connected with the output terminal of steam turbine 8.The heat that absorbs the chilled water in reactor pit 71 due to evaporator 3 makes cold-producing medium 6 flash to the steam with larger kinetic energy, therefore, by steam turbine 8 is set, make 8 runnings of Steam Actuation steam turbine, thereby the energy of steam is passed to steam turbine 8, on the one hand steam is played to cooling effect, can produce power on the other hand and drive miscellaneous part running.And fan 41 both can blow air cooling tower 4 inside, the cooling effect of strengthening air cooling tower 4, also can form stronger circuit cycle driving force simultaneously, accelerates the circuit cycle between evaporator 3 and air cooling tower 4, thereby the waste heat of reactor is derived rapidly; And the driving force running that fan 41 utilizes steam turbine 8 to produce, does not drive by any external power source, and therefore, it is not subject to the impact of external factor, stability and safe.
Referring again to Fig. 1, between one end of pipeline 5 and the outlet of air cooling tower 4 lower ends, be provided with condensation water tank 9.Condensation water tank 9 can collect steam be transported in the evaporator 3 in reactor pit 71 at the interior liquid cold-producing medium 6 cooling and that produce of air cooling tower 4, thereby can prevent that the steam in air cooling tower 4 is fully cooling not rear directly in pipeline 5 Returning evaporimeters 3.
Again as shown in Figure 1, the loop of reactor pressure vessel 1 is provided with blowdown line 11, and blowdown line 11 is provided with blowdown valve 12, and the output terminal of blowdown line 11 is positioned at containment 7.While there is large break dehydration in Dang Yi loop, because a circuit cools water tails off, cooled reactor pressure vessel 1 rapidly, the temperature of reactor pressure vessel 1 inside and pressure can raise fast, therefore, utilize blowdown line 11 Dui Yi loops to carry out quick pressure releasing, on the one hand can carry out step-down in inside, Dui Yi loop, after a loop step-down, can make on the other hand chilled water in reactor pit 71 more easily and rapidly Cong Yi loop cut place inject.In addition, the output terminal of blowdown line 11 is positioned at containment 7 and can prevents that nuclear pollution material is discharged into outside containment, causes nuclear leakage.
Comprehensive above-mentioned and in conjunction with Fig. 2, the large break dehydration of Dang Yi loop, during reactor pressure vessel 1 temperature anomaly, blowdown valve 12 is opened inside, ，Yi loop to the interior pressure release of containment 7.Meanwhile, isolation valve 21 is opened, and the chilled water in high-order refuelling pool 2 injects automatically due to pressure differential in the reactor pit 71 of containment 7, and reactor pit 71 and evaporator 3 are submerged.Now, the chilled water heating in 1 pair of reactor pit 71 of reactor pressure vessel, and by chilled water, heat is delivered to the cold-producing medium 6 in evaporator 3, cold-producing medium 6 is subject to thermal evaporation to form steam, and rises along the pipeline 5 being connected with steam turbine 8.Afterwards, first steam enter steam turbine 8, and pushing turbine 8 rotations, last, enters air cooling tower 4 inside after steam turbine 8; Meanwhile, steam turbine 8 rotates and drives fan 41 to rotate, and fan 41 rotates the inner blowing cooling of air cooling tower 4.Steam after the interior cooling of air cooling tower 4 release heat from steam state liquefy, liquid cold-producing medium 6 accumulates in the bottom of air cooling tower 4, and flow in condensation water tank 9, condensation water tank 9 is transported in the evaporator 3 in reactor pit 71 by pipeline 5 after collecting liquid cold-producing medium 6, recycles continuing.By constantly circulating of above-mentioned cold-producing medium 6, and then the heat in reactor pit 71 is exported to containment 7 outsides, thereby guarantee the safety of containment 7.
The utility model is by the interior evaporator 3 that arranges of reactor pit 71, and at the outer air cooling tower 4 that arranges of containment 7, utilizes pipeline 5 to be connected between air cooling tower 4 and evaporator 3, thereby forms cooling circuit; When reactor-loop generation security incident, the chilled water that is positioned at the high-order refuelling pool 1 of containment 7 is injected to reactor pit 71 automatically, reactor pit 71 is flooded, thereby cooled reactor pressure vessel 1, recycling cold-producing medium 6 constantly circulates in loop, thereby take the heat in reactor pit 71 to air cooling tower 4, realization is carried out cooling object to reactor pressure vessel 1, prevent that reactor pressure vessel 1 Yin Yi loop dehydration from causing reactor internal temperature sharply to rise, and causes more serious security incident; Compared with prior art, the utility model just can not realized under accident the waste heat export function of containment 7 owing to relying on external ac power source, therefore, has effectively improved the stability of system, has improved the security of nuclear power plant simultaneously.
Above disclosed is only preferred embodiments of the present utility model, certainly can not limit with this interest field of the utility model, and the equivalent variations of therefore doing according to the utility model claim, still belongs to the scope that the utility model is contained.
Claims (6)
1. a non-passive safety shell cooling device, being applicable to derives the decay heat in reactor pressure vessel, comprise the high-order refuelling pool that stores chilled water, in described containment, there is reactor pit, described reactor pressure vessel is placed in described reactor pit, described high-order refuelling pool is placed in described containment and is positioned at the top of described reactor pit, described high-order refuelling pool is communicated with described reactor pit by isolation valve, it is characterized in that: described non-passive safety shell cooling device also comprises evaporator, air cooling tower, some pipelines and cold-producing medium, described evaporator is placed in described reactor pit, described air cooling tower is positioned at outside described containment and higher than described reactor pit, described pipeline is connected between the outlet of described evaporator and the entrance of described air cooling tower upper end and between the outlet and the entrance of described evaporator of described air cooling tower lower end, described cold-producing medium is at described evaporator, in the circulation passage that air cooling tower and pipeline form, flow.
2. non-passive safety shell cooling device as claimed in claim 1, is characterized in that: between one end of described pipeline and the entrance of described air cooling tower upper end, be provided with steam turbine.
3. non-passive safety shell cooling device as claimed in claim 2, is characterized in that: described air cooling tower upper end is provided with fan, and described fan is connected with the output terminal of described steam turbine.
4. non-passive safety shell cooling device as claimed in claim 1, is characterized in that: between one end of described pipeline and the outlet of described air cooling tower lower end, be provided with condensation water tank.
5. non-passive safety shell cooling device as claimed in claim 1, is characterized in that: the loop of described reactor pressure vessel is provided with blowdown line, and described blowdown line is provided with blowdown valve, and the output terminal of described blowdown line is positioned at described containment.
6. non-passive safety shell cooling device as claimed in claim 1, is characterized in that: described evaporator vertically or is obliquely placed in described reactor pit, and the outlet of described evaporator is positioned at upper end, and the entrance of described evaporator is positioned at lower end.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320464462.XU CN203397717U (en) | 2013-07-31 | 2013-07-31 | Passive containment cooling device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320464462.XU CN203397717U (en) | 2013-07-31 | 2013-07-31 | Passive containment cooling device |
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| CN203397717U true CN203397717U (en) | 2014-01-15 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201320464462.XU Expired - Lifetime CN203397717U (en) | 2013-07-31 | 2013-07-31 | Passive containment cooling device |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104167231A (en) * | 2014-07-30 | 2014-11-26 | 中科华核电技术研究院有限公司 | Concrete containment passive cooling system |
| CN104167229A (en) * | 2014-04-24 | 2014-11-26 | 国核华清（北京）核电技术研发中心有限公司 | Passive containment shell condensed water injection system |
-
2013
- 2013-07-31 CN CN201320464462.XU patent/CN203397717U/en not_active Expired - Lifetime
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104167229A (en) * | 2014-04-24 | 2014-11-26 | 国核华清（北京）核电技术研发中心有限公司 | Passive containment shell condensed water injection system |
| CN104167231A (en) * | 2014-07-30 | 2014-11-26 | 中科华核电技术研究院有限公司 | Concrete containment passive cooling system |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C56 | Change in the name or address of the patentee | ||
| CP01 | Change in the name or title of a patent holder |
Address after: 518000 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building 15 layer (1502-1504, 1506) Patentee after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee after: CHINA GENERAL NUCLEAR POWER Corp. Address before: 518000 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building 15 layer (1502-1504, 1506) Patentee before: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee before: CHINA GENERAL NUCLEAR POWER Corp. |
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| CX01 | Expiry of patent term |
Granted publication date: 20140115 |
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| CX01 | Expiry of patent term |