CN103413581A - Passive containment cooling system - Google Patents
Passive containment cooling system Download PDFInfo
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- CN103413581A CN103413581A CN2013103285145A CN201310328514A CN103413581A CN 103413581 A CN103413581 A CN 103413581A CN 2013103285145 A CN2013103285145 A CN 2013103285145A CN 201310328514 A CN201310328514 A CN 201310328514A CN 103413581 A CN103413581 A CN 103413581A
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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 invention discloses passive containment cooling system. The passive containment cooling system comprises a high-position material exchanging water pool used for storing cooling water, an evaporator, an air cooling tower, a plurality of pipes, and a refrigerant, wherein a containment is equipped with a vault; a reactor pressure vessel o is located in the vault; the high-position material exchanging water pool is positioned in the containment and above the vault, and is communicated with the vault through an isolating valve; the evaporator is positioned in the vault; the air cooling tower is positioned outside the containment and is higher than the vault, the pipes are connected between the outlet of the evaporator and the inlet in the upper end of the air cooling tower, and between the outlet in the lower end of the air cooling tower and the inlet of the evaporator; the refrigerant flows in a circulation channel formed among the evaporator, the air cooling tower and the pipes. The passive containment cooling system can realize the function of exporting waste heat of the containment in case of an accident without relying on an external power supply, so as to increase the stability of the system and also the safety of the nuclear power station.
Description
Technical field
The present invention relates to a kind of nuclear reactor safety device, relate in particular to a kind of Passive containment cooling system.
Background technology
The use of nuclear power is the important breakthroughs of the mankind on the 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, make the utilization of mankind's pay attention to day by day to nuclear energy, and continue to increase the research and development in the 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 having high value, its harm that may bring also make us talk the core look and become.In using the process of nuclear power, if protect improper, cause major accidents such as nuclear leakage occur, 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, a 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 outer secondary circuit water of pipe, makes the 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, can't tackle the situation that occurs outage when security incident occurs, it is can only the short time cooling on the other hand, still the heat in containment can't be exported to outside containment, after accident continued for a long time, containment temperature and pressure still rose, and security is not high.
Summary of the invention
The object of the present invention is to provide a kind of external ac power source that do not rely on, realize the waste heat export function of containment under accident, improve the Passive containment cooling system of the security of nuclear power plant.
To achieve these goals, the invention provides a kind of Passive containment cooling system, 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, has 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 entrance of the outlet of described evaporator and described air cooling tower upper end and between the entrance of the outlet of described air cooling tower lower end and described evaporator, described cold-producing medium is at described evaporator, in the circulation passage that air cooling tower and pipeline form, flow.
Preferably, between the entrance of an end of described pipeline and 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 the 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, do not drive by any external power source, and therefore, it is not subjected to the impact of external factor, stability and safe.
Preferably, between the outlet of an end of described pipeline and described air cooling tower lower end, be provided with condensation water tank.Described condensation water tank can be cooling and the described refrigerant collecting liquid state that produces gets up and is transported in the evaporator in reactor pit in described air cooling tower by steam, 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.When the large break dehydration occurs in a 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 to carry out quick pressure releasing to a loop, can carry out step-down to an inside, loop on the one hand, the chilled water in reactor pit more easily and is rapidly injected from a loop cut.In addition, the output terminal of described blowdown line is positioned at described containment and can prevents that the nuclear pollution material is discharged into outside containment, causes nuclear leakage.
Preferably, described evaporator vertically or obliquely is 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 present invention arranges evaporator in described reactor pit, and outside described containment, air cooling tower is set, and 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 will be positioned at the high-order refuelling pool of containment injects described reactor pit, reactor pit is flooded, thereby cooled reactor pressure vessel, the recycling cold-producing medium constantly circulates in loop, thereby takes the heat in described reactor pit to described air cooling tower, realizes carrying out cooling to reactor pressure vessel, prevent that reactor pressure vessel from sharply rising because a loop dehydration causes the reactor internal temperature, causes more serious security incident; Compared with prior art, the present invention just can not realize under accident therefore the waste heat export function of containment, has been improved to the stability of containment cooling system owing to relying on external ac power source, has improved simultaneously the security of nuclear power plant.
The accompanying drawing explanation
Fig. 1 is the structural representation of Passive containment cooling system of the present invention.
Fig. 2 be in Passive containment cooling system of the present invention cold-producing medium flow to schematic diagram.
Embodiment
For the effect that describes technology contents of the present invention, structural attitude in detail, realizes, below in conjunction with embodiment and coordinate accompanying drawing to be explained in detail.
As shown in Figure 1, Passive containment cooling system of the present invention is applicable to the decay heat in reactor pressure vessel 1 is derived, 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 emergency episode occurs higher than reactor pit 71, water in pond can inject in reactor pit 71 automatically, reactor pressure vessel 1 is flooded, thereby remove the use pumping for water pump from, realize non-active water filling, the situation that occurs outage during Accident prevention and can't water filling occurs, improves security.Evaporator 3 is placed in reactor pit 71, and evaporator 3 vertically is 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 flooded reactor pressure vessel 1, evaporator 3 was in water surface below.Air cooling tower 4 is positioned at outside containment 7 and higher than reactor pit 71, can guarantee the cold-producing medium automatic back flow like this.Pipeline 5 is connected between the entrance of the outlet of evaporator 3 and air cooling tower 4 upper ends, and another pipeline 5 is connected between the entrance of the outlet of air cooling tower 4 lower ends and evaporator 3, and cold-producing medium 6 flows in the circulation passage that evaporator 3, air cooling tower 4 and pipeline 5 form.
Again as shown in Figure 1, between the import of an end of pipeline 5 and 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 the 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, do not drive by any external power source, and therefore, it is not subjected to the impact of external factor, stability and safe.
Please consult again Fig. 1, be provided with condensation water tank 9 between the outlet of an end of pipeline 5 and air cooling tower 4 lower ends.Condensation water tank 9 can be interior cooling and cold-producing medium 6 liquid state that produces collects and is transported in the evaporator 3 reactor pit 71 at air cooling tower 4 by steam, thereby can prevent that the steam in air cooling tower 4 is inabundant 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.When the large break dehydration occurs in a 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 11 pairs of loops of blowdown line to carry out quick pressure releasing, can carry out step-down to an inside, loop on the one hand, the chilled water in reactor pit 71 more easily and is rapidly injected from a loop cut.In addition, the output terminal of blowdown line 11 is positioned at containment 7 and can prevents that the nuclear pollution material is discharged into outside containment, causes nuclear leakage.
Comprehensive above-mentioned and in conjunction with Fig. 2, when a loop large break dehydration, during reactor pressure vessel 1 temperature anomaly, blowdown valve 12 is opened, and an inside, loop is to the interior pressure release of containment 7.Simultaneously, 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 of reactor pressure vessel 71, and by chilled water, heat is delivered to the cold-producing medium 6 in evaporator 3, cold-producing medium 6 is subjected to thermal evaporation to form steam, and rises along the pipeline 5 be connected with steam turbine 8.Afterwards, at first steam enter steam turbine 8, and pushing turbine 8 rotations, last, after steam turbine 8, enters air cooling tower 4 inside; Meanwhile, steam turbine 8 rotates and drives fan 41 rotations, 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 the 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 present invention 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 will be positioned at the high-order refuelling pool 1 of containment 7 injects 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 purpose to reactor pressure vessel 1, prevent that reactor pressure vessel 1 from sharply rising because a loop dehydration causes the reactor internal temperature, causes more serious security incident; Compared with prior art, the present invention just can not realize under accident therefore the waste heat export function of containment 7, has effectively been improved to the stability of system owing to relying on external ac power source, has improved simultaneously the security of nuclear power plant.
Above disclosed is only preferred embodiments of the present invention, certainly can not limit with this interest field of the present invention, and the equivalent variations of therefore doing according to the present patent application the scope of the claims, still belong to the scope that the present invention is contained.
Claims (6)
1. Passive containment cooling system, being applicable to derives the decay heat in reactor pressure vessel, comprise the high-order refuelling pool that stores chilled water, in described containment, has 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 Passive containment cooling system 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 entrance of the outlet of described evaporator and described air cooling tower upper end and between the entrance of the outlet of described air cooling tower lower end and described evaporator, described cold-producing medium is at described evaporator, in the circulation passage that air cooling tower and pipeline form, flow.
2. Passive containment cooling system as claimed in claim 1, is characterized in that: be provided with steam turbine between the entrance of an end of described pipeline and described air cooling tower upper end.
3. Passive containment cooling system as claimed in claim 2, it 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. Passive containment cooling system as claimed in claim 1, is characterized in that: be provided with condensation water tank between the outlet of an end of described pipeline and described air cooling tower lower end.
5. Passive containment cooling system as claimed in claim 1, it 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. Passive containment cooling system as claimed in claim 1, it is characterized in that: described evaporator vertically or obliquely is 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.
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Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN103617815A (en) * | 2013-12-05 | 2014-03-05 | 哈尔滨工程大学 | Passive residual heat exhausting system of pressurized water reactor nuclear power plant |
| CN104134474A (en) * | 2014-07-30 | 2014-11-05 | 中科华核电技术研究院有限公司 | Passive cooling system |
| CN104134473A (en) * | 2014-06-30 | 2014-11-05 | 中国核电工程有限公司 | Active-combined passive containment vessel cooling system |
| CN104332189A (en) * | 2014-09-18 | 2015-02-04 | 中国核电工程有限公司 | System for finally guaranteeing functions of containment vessel and preventing large-scale radioactive release and method thereof |
| CN104979023A (en) * | 2014-04-03 | 2015-10-14 | 国核（北京）科学技术研究院有限公司 | Passive containment heat exporting system and controlling method thereof, and pressurized water reactor |
| WO2016015474A1 (en) * | 2014-07-30 | 2016-02-04 | 中科华核电技术研究院有限公司 | Passive concrete containment cooling system |
| CN106875987A (en) * | 2017-03-31 | 2017-06-20 | 中广核研究院有限公司 | A kind of containment and fuel factory building passive cooling system |
| CN108597630A (en) * | 2018-04-26 | 2018-09-28 | 中国核动力研究设计院 | A kind of passive gravity injected system of nuclear power plant's total head |
| CN108831573A (en) * | 2018-06-28 | 2018-11-16 | 哈尔滨工程大学 | A kind of nuclear power station secondary side passive residual heat removal security system |
| CN109545400A (en) * | 2018-12-07 | 2019-03-29 | 中广核研究院有限公司 | A kind of Passive containment cooling system |
| CN113035386A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Containment built-in efficient heat exchanger adopting double-wheel double-blade composite power air suction type |
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| CN104332189A (en) * | 2014-09-18 | 2015-02-04 | 中国核电工程有限公司 | System for finally guaranteeing functions of containment vessel and preventing large-scale radioactive release and method thereof |
| CN106875987A (en) * | 2017-03-31 | 2017-06-20 | 中广核研究院有限公司 | A kind of containment and fuel factory building passive cooling system |
| CN108597630A (en) * | 2018-04-26 | 2018-09-28 | 中国核动力研究设计院 | A kind of passive gravity injected system of nuclear power plant's total head |
| CN108597630B (en) * | 2018-04-26 | 2021-05-28 | 中国核动力研究设计院 | Nuclear power plant full-pressure passive gravity injection system |
| CN108831573A (en) * | 2018-06-28 | 2018-11-16 | 哈尔滨工程大学 | A kind of nuclear power station secondary side passive residual heat removal security system |
| CN109545400A (en) * | 2018-12-07 | 2019-03-29 | 中广核研究院有限公司 | A kind of Passive containment cooling system |
| CN113035386A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Containment built-in efficient heat exchanger adopting double-wheel double-blade composite power air suction type |
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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 Patentee after: China General Nuclear Power Corporation 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: Zhongkehua Nuclear Power Technology Institute Co., Ltd. Patentee before: China General Nuclear Power Corporation |