CN107393605A - The passive air-cooling apparatus and method of a kind of modular small nuclear reactor - Google Patents
The passive air-cooling apparatus and method of a kind of modular small nuclear reactor Download PDFInfo
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- CN107393605A CN107393605A CN201710551911.7A CN201710551911A CN107393605A CN 107393605 A CN107393605 A CN 107393605A CN 201710551911 A CN201710551911 A CN 201710551911A CN 107393605 A CN107393605 A CN 107393605A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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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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- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a kind of passive air-cooling apparatus of modular small nuclear reactor and method, the passive air-cooling apparatus includes itself steam generator of modular small nuclear reactor, intermediate loop and cooling tower, intermediate loop include water supply tank, air-cooled heat exchanger and associated conduit valve；When accident occurs, the device establishes complete natural convection loop, water supply tank injects cooling water by gravity to steam generator secondary side, cooling water takes away reactor core primary side heat by steam generator, flow back to subsequently into air-cooled heat exchanger and again water supply tank, air-cooled heat exchanger by with gas converting heat in cooling tower, so as to finally taking away reactor waste；The device is to be directed to modular small nuclear reactor when accident occurs, utilize the heat-exchanger rig of the steam generator connection intermediate loop of reactor in itself, discharge residual heat of nuclear core in time, ultimate heat sink is provided for reactor accident, realize prevention and alleviate the effect of reactor disaster process, it is ensured that nuclear reactor safety.
Description
Technical field
The present invention relates to nuclear reactor safety equipment and technical field, more particularly to a kind of modular small nuclear reactor
Passive air-cooling apparatus and method.
Background technology
Advanced passive nuclear power station adds largely on the basis of traditional concept design according to passive design concept
Passive component and system, greatly improve security of system.Passive safety system drives reactor safety by gravity
System, it is not necessary to active measure, such as pump, blower fan, diesel-driven generator, in the state of accident, the valve in pipeline automatically turn on,
Natural Circulation is established, so as to export residual heat of nuclear core, it is ensured that reactor core safety and the integrality of pressure vessel.
The AP1000 of US Westinghouse company employs passive major accident prevention and mitigation strategy, AP1000 in the design
Completely self-contained passive core cooling system includes two big portion of Heat Discharging System of Chinese and passive safety injection system
Point.The EPR-1000 nuclear power stations design in Europe also uses the similar passive core cooling systems of AP1000, major function
It is to be depressured automatically after accident, injects boron water to reactor core, takes away reactor core decay heat etc..Siemens are SWR1000
Devise passive Automatic Depressurization System and passive steam and condensate system after accident, after accident generation, main steam line every
From again steam and condensate system automatically engages, and steam enters the condenser of pressure vessel wall, is flowed under gravity after condensation
In pressure vessel, Natural Circulation is completed.The simplification boiling-water reactor (ESBWR) in Europe devises a passive condenser system, utilizes
Condensation sets up Natural Circulation and takes away reactor core decay heat.
The concept of non-passive safety is largely carried out and is widely used in the world, and passive theory is
A kind of important means through being proved to be that reactor inherent safety and reliability can be effectively improved.Meanwhile recently as
The development of science and technology, the advantage of modular small nuclear reactor is slowly discovered, the also military affairs single since most of its application
Using civilian nuclear energy field is progressively expanded to, carried out in recent years applied to city heat supply, industry vapour/hydrogen manufacturing, desalinization,
The modular small nuclear reactor research and design of portable nuclear power unit and other aspect heat energy utilizations.Modular small heap
It is primarily referred to as such as steam generator of the equipment in reactor main circuit, main pump, voltage-stablizer being incorporated into reactor pressure vessel,
So as to eliminate the use of a large amount of pipelines in major loop, avoid occurring the possibility of large-break LOCA, while integrated design side
Formula make reactor design it is more compact so that space requirement reduce, modularized design mode simplify reactor construction process and
Maintenance and repair cost, so modular small nuclear reactor is increasingly favored by nuclear industry field.And modularization rickle
Passive safety system is often with reference to traditional large-scale and design of reactor, mostly using a set of independent system, i.e., anti-
Answer in the structure of heap script and adding single Heat Discharging System of Chinese, such as the W-SMR reactors in the U.S., while module
The ultimate heat sink design for changing rickle typically all uses water tank, such as the IRIS of international cooperation and the W-SMR reactors in U.S. difference
The design of material-changing water tank and hot trap large water tank is employed, they, which are required in water tank, has substantial amounts of cooling agent to ensure to react
The refrigerating function of a period of time can be provided by piling up under accident transient state.But the volume of water tank is limited eventually, that is reaction
Ultimate heat sink after heap accident be not it is indefinite provide cooling capacity for reactor, therefore in order to raise the peace of nuclear power station
Full property should consider after accident for reactor provides one with infinitely can but ability ultimate heat sink.
The content of the invention
In order to overcome the above-mentioned problems of the prior art, it is an object of the invention to provide a kind of modular small core is anti-
The passive air-cooling apparatus and method of heap are answered, is to provide a kind of passive air cooling for modular small nuclear reactor
Nuclear plant severe accident relieving apparatus.
In order to achieve the above object, the present invention adopts the following technical scheme that：
A kind of passive air-cooling apparatus of modular small nuclear reactor, suitable for the prevention of reactor disaster
And alleviation, the waste heat in primary Ioops is exported after reactor accident, the device includes the steaming of itself of modular small nuclear reactor
Vapour generator 4, intermediate loop 9 and cooling tower 1, the intermediate loop 9 include water supply tank 3, air-cooled heat exchanger 2 and corresponding pipeline valve
Door；Containment vessel 5 is placed in underground, and reactor pressure vessel 6 is placed in inside containment vessel 5, and steam generator 4 is placed in
Inside reactor pressure vessel 6, air cooling tower 1 is placed in outside containment and above ground level, air-cooled heat exchanger 2 is placed in air cooling tower
Inside 1, the outlet of air-cooled heat exchanger 2 is connected with the upper end of water supply tank 3 by the first pipeline 201, and the lower end of water supply tank 3 passes through second pipe
301 are connected with the level entrance of steam generator 4 two, and the first valve 11, steam generator 4 two are housed on second pipe 301
Level outlet is connected to the entrance of air-cooled heat exchanger 2 by the 3rd pipeline 401, and the second valve 12 is housed on the 3rd pipeline 401,
So as to form complete natural convection loop, the valve 12 of the first valve 11 and second is only opened in accident conditions, connection
The steam generator 4 and intermediate loop 9；Cooling water is filled in the water supply tank 3, its position is higher than steam generator 4 two times
Side entrance.
The cooling tower 1 is the profile of hyperbolic-type, optimizes air flow channel in tower and reduces the shadow of the outer wind-force of cooling tower
Ring.
The steam generator 4 is steam generator used in modular small nuclear reactor normal operation, only in accident work
It is connected during condition with the intermediate loop 9.
The air-cooled heat exchanger 2 is 690 alloy materials, Bottomhole pressure secondary side cooling water, it is hollow to manage outer flowing air cooling tower
Gas, the horizontal direction of air-cooled heat exchanger 2 arrange and are arranged in the bottom of cooling tower 1, ensure that heat exchange is not easily susceptible to air speed influence.
The water supply tank 3 is carbon steel and inner liner stainless steel, and outlet can be blocked by being not present in the circulatory flow in case and all
The material of filter screen, the upper end connecting pipe of water supply tank 3 are connected through reactor pressure vessel 6 with air-cooled heat exchanger 2.
The cooling means of the passive air-cooling apparatus of the modular small nuclear reactor, when occur station blackout or
When losing main water supply accident, the first valve 11 and the second valve 12 on the pipeline that intermediate loop 9 is connected with steam generator 4 are certainly
Dynamic to open, switching intermediate loop 9 is connected with the secondary side of steam generator 4 and forms new Natural Circulation, is sent out instead of script steam
The raw main feedwater of the secondary side of device 4, cooling water injects the secondary side of steam generator 4 by Action of Gravity Field in water supply tank 3, at accident initial stage,
Natural Circulation energy is larger, can replace the main feedwater of the secondary side of steam generator 4 itself, and cooling water passes through steam generator 4
Heat-transfer pipe is exchanged heat with reactor core primary Ioops cooling agent, and takes away waste heat caused by reactor core primary Ioops, the secondary side of steam generator 4
Heated cooling water is flowed into air-cooled heat exchanger 2 by Natural Circulation driving force, by entering with the atmospheric environment in cooling tower 1
Row heat exchange, the heat in cooling water is taken away by atmospheric environment, the cooling water for reducing temperature exports again by air-cooled heat exchanger 2
Water supply tank 3 is returned to, and such accident that circulates in triggers continuous repetitive cycling after the first valve 11 and the second valve 12, for a long time
Stable operation, heap in-core waste heat is constantly taken away, indefinite duration cooling is provided for reactor.
The present invention compared with prior art, has advantage following prominent and effect：
1st, passive air cooled nuclear plant severe accident relieving apparatus provided by the invention, it is to be directed at present in the world
The modular small nuclear reactor of extensive concern, be it is a kind of using water supply tank, air-cooled heat exchanger, air cooling tower, reactor in itself from
The passive residual heat removal device of the compages of carrying vapour generator composition, under accident conditions, filled using passive air cooling
The intermediate loop put is connected with steam generator secondary side, in water supply tank cooling water by Action of Gravity Field to steam generator secondary side
Water filling, reactor can be taken away by heat exchange with the main feedwater of simulated accident steam generator at initial stage, cooling water in a vapor generator
Primary Ioops heat is simultaneously flowed into air-cooled heat exchanger, by air heat-exchange in air-cooled heat exchanger and cooling tower, and it is hollow by cooling tower
Gas finally takes away heat.
2nd, because apparatus of the present invention are to be used as ultimate heat sink by cooling tower to take away reactor waste, i.e. atmospheric environment is anti-
Answer heap ultimate heat sink, it means that the reactor provided with the device substantially increases reactor there is unlimited cooling capacity
Security.
3rd, present invention incorporates traditional large pressurized water reactor Safety System Design theory and modular small nuclear reaction
The own structural characteristics of heap, by using reactor steam generator part itself under accident conditions, simplify reactor sheet
Body system design, while the apparatus structure is simple and reliable, has the characteristics of passive without relying on external ac power source, in accident
Reactor waste can be exported after generation, and is run steadily in the long term, adds reactor inherent safety, prevents and alleviates reaction
Heap major accident, improve the security and economy of nuclear power station.
Brief description of the drawings
Fig. 1 is a kind of passive air-cooling apparatus schematic diagram of modular small nuclear reactor of the present invention.
Fig. 2 is that a kind of passive air-cooling apparatus of modular small nuclear reactor of the present invention cools down current direction signal
Figure.
Embodiment
In order to describe the technology contents of the present invention, construction feature, the effect realized in detail, below in conjunction with embodiment simultaneously
Accompanying drawing is coordinated to describe in detail.
The present invention is to provide a kind of passive air-cooling apparatus for modular small nuclear reactor, prevention and alleviation
Reactor disaster.When nuclear power station occurs station blackout or loses the accidents such as main feedwater, due to steam generator secondary side
Coolant loss, reactor waste can not be taken away, primary Ioops temperature may be caused to raise, core meltdown, damage etc..The present invention is non-
Active air cooling device establishes new Natural Circulation using intermediate loop design after accident and takes away residual heat of nuclear core, ensures reactor peace
Entirely.
Fig. 1 is a kind of passive air-cooling apparatus schematic diagram of modular small nuclear reactor.The device is small by modularization
Steam generator 4, intermediate loop 9 and the cooling tower 1 of type nuclear reactor itself combine long-term cold to export reactor waste realization
But.Wherein intermediate loop 9 includes water supply tank 3, cooling water, air cooling tower 1, air-cooled heat exchanger 2 and corresponding pipeline valve again.Reaction
Heap itself containment 5 is placed in underground, and reactor pressure vessel 6 is placed in inside containment vessel 5, and air cooling tower 1 is placed in containment
Outside and above ground level, air-cooled heat exchanger 2 is placed in inside air cooling tower 1, and the outlet of air-cooled heat exchanger 2 leads to the upper end of water supply tank 3
The first pipeline 201 to be crossed to connect, the lower end of water supply tank 3 is connected by second pipe 301 with the level entrance of steam generator 4 two, and
First valve 11 is housed, the outlet of the level of steam generator 4 two is connected to air cooling by the 3rd pipeline 401 and changed on second pipe 301
The hot entrance of device 2, and the second valve 12 is housed on the 3rd pipeline 401, so as to form complete natural convection loop.
As shown in figure 1, the position of water supply tank 3 is significantly larger than 4 two side entrances of steam generator, when occur station blackout or
When losing main water supply accident, the first valve 11 and the second valve 12 on the pipeline that intermediate loop 9 is connected with steam generator 4 are certainly
Dynamic to open, therefore steam generator 4 is switched to the heat exchanger of passive air cooling system, the cooling water in water supply tank 3 by
Action of Gravity Field injects the secondary side of steam generator 4, and at accident initial stage, Natural Circulation energy is larger, can replace steam generator 4
The main feedwater of secondary side itself, cooling water is exchanged heat by steam generator heat-transfer pipe and reactor core primary Ioops cooling agent, and is taken away
Waste heat caused by reactor core primary Ioops, the heated cooling water of the secondary side of steam generator 4 are flowed into empty by Natural Circulation driving force
In cold heat exchanger 2, by being exchanged heat with the atmospheric environment in cooling tower 1, the heat in cooling water is taken away by atmospheric environment, is dropped
The cooling water of low temperature returns once again to water supply tank 3 by the outlet of air-cooled heat exchanger 2, and such circulates in accident triggering the
Continuous repetitive cycling after one valve 11 and the second valve 12, operation steady in a long-term, constantly takes away heap in-core waste heat, is carried for reactor
Cooled down for indefinite duration.
As shown in Fig. 2 after station blackout occurs or loses main water supply accident, pass through the first valve 11 and the second valve 12
Switching intermediate loop 9 is connected with the secondary side of steam generator 4 and forms new Natural Circulation, secondary instead of script steam generator
The main feedwater in side, cooling water injects the secondary side of steam generator 4 enhancing Natural Circulation driving force by Action of Gravity Field in water supply tank 3, really
There are enough and stable natural-circulation capacities in guarantor's accident passive air-cooling apparatus at initial stage so that the heat that intermediate loop is taken away
Amount matches with reactor core primary Ioops waste heat.Cooling tower 1 air flow channel and is dropped in tower by the contour optimization by hyperbolic-type
The influence of the outer wind-force of low cooling tower, by air, the Natural Circulation of stroke is taken away one time that intermediate loop is taken out of in cooling tower
Road waste heat, so as to ensure that atmospheric environment turns into the ultimate heat sink of reactor, indefinite duration cooling is provided for reactor.
Above content is to combine specific preferred embodiment further description made for the present invention, it is impossible to is assert
The embodiment of the present invention is only limitted to this, for the ordinary technical staff in the technical field of the invention, as long as
Within the spirit of the present invention, change and modification to embodiment described above should all be considered as the power in the present invention
In the range of sharp claim.
Claims (6)
- A kind of 1. passive air-cooling apparatus of modular small nuclear reactor, it is characterised in that：It is serious suitable for reactor The prevention and alleviation of accident, export the waste heat in primary Ioops after reactor accident, and the device includes modular small nuclear reaction Steam generator (4), intermediate loop (9) and the cooling tower (1) of heap itself, the intermediate loop (9) include water supply tank (3), sky Cold heat exchanger (2) and corresponding pipeline valve；Containment vessel (5) is placed in underground, and reactor pressure vessel (6) is placed in reactor Containment (5) is internal, and steam generator (4) is placed in reactor pressure vessel (6) inside, and air cooling tower (1) is placed in outside containment And above ground level, air-cooled heat exchanger (2) is placed in inside air cooling tower (1), in air-cooled heat exchanger (2) outlet and water supply tank (3) End is connected by the first pipeline (201), and water supply tank (3) lower end is entered by second pipe (301) and the level of steam generator (4) two Mouth connection, and the first valve (11) is housed on second pipe (301), the outlet of the level of steam generator (4) two passes through the 3rd pipe Road (401) is connected to air-cooled heat exchanger (2) entrance, and the second valve (12) is housed on the 3rd pipeline (401), so as to formed Whole natural convection loop, first valve (11) and the second valve (12) are only opened in accident conditions, connect the steaming Vapour generator (4) and intermediate loop (9)；Cooling water is filled in the water supply tank (3), its position is higher than steam generator (4) two Secondary side entrance.
- 2. the passive air-cooling apparatus of modular small nuclear reactor according to claim 1, it is characterised in that：Institute The profile that cooling tower (1) is hyperbolic-type is stated, air flow channel in tower is optimized and reduces the influence of the outer wind-force of cooling tower.
- 3. the passive air-cooling apparatus of modular small nuclear reactor according to claim 1, it is characterised in that：Institute It is steam generator used in modular small nuclear reactor normal operation to state steam generator (4), only in accident conditions and institute State intermediate loop (9) connection.
- 4. the passive air-cooling apparatus of modular small nuclear reactor according to claim 1, it is characterised in that：Institute It is 690 alloy materials to state air-cooled heat exchanger (2), and Bottomhole pressure secondary side cooling water manages air in outer flowing air cooling tower, and air cooling changes Hot device (2) horizontal direction arranges and is arranged in the cooling tower (1) bottom, ensures that heat exchange is not easily susceptible to air speed influence.
- 5. the passive air-cooling apparatus of modular small nuclear reactor according to claim 1, it is characterised in that：Institute Water supply tank (3) is stated as carbon steel and inner liner stainless steel, the material that can block outlet filter screen is all not present in case and in the circulatory flow Material, water supply tank (3) upper end connecting pipe are connected through reactor pressure vessel (6) with air-cooled heat exchanger (2).
- 6. the cooling means of the passive air-cooling apparatus of modular small nuclear reactor described in claim 1, its feature exist In：When station blackout occurs or loses main water supply accident, on the pipeline that intermediate loop (9) is connected with steam generator (4) First valve (11) and the second valve (12) automatically open up, and switching intermediate loop (9) is connected simultaneously with steam generator (4) secondary side New Natural Circulation is formed, instead of the main feedwater of script steam generator (4) secondary side, cooling water is made by gravity in water supply tank (3) With injection steam generator (4) secondary side, at accident initial stage, Natural Circulation energy is larger, can replace steam generator (4) this The main feedwater of body secondary side, cooling water is exchanged heat by the heat-transfer pipe of steam generator (4) with reactor core primary Ioops cooling agent, and band Waste heat caused by reactor core primary Ioops is walked, the heated cooling water of steam generator (4) secondary side passes through Natural Circulation driving force stream Enter in air-cooled heat exchanger (2), by being exchanged heat with the atmospheric environment in cooling tower (1), taken away by atmospheric environment in cooling water Heat, reduce the cooling water of temperature and return once again to water supply tank (3) by air-cooled heat exchanger (2) outlet, and such follow Ring triggers the first valve (11) and the second valve (12) continuous repetitive cycling afterwards in accident, operation steady in a long-term, constantly takes away heap In-core waste heat, indefinite duration cooling is provided for reactor.
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| CN108170924A (en) * | 2017-12-21 | 2018-06-15 | 西安交通大学 | One kind is for Steam Generators in NPP heat transfer pipe plug stream condition model method for building up |
| CN108417282A (en) * | 2018-05-11 | 2018-08-17 | 上海核工程研究设计院有限公司 | A kind of loop structure of reactor circuit and a kind of low-temperature heat supply reactor with the reactor circuit |
| CN108615566A (en) * | 2018-06-14 | 2018-10-02 | 华南理工大学 | A kind of small cores reactor heat transport system cooled down using circuit parallel heatpipe |
| CN108877965A (en) * | 2018-06-25 | 2018-11-23 | 哈尔滨工程大学 | A kind of passive air cooling system applied to PCCS heat-exchanging water tank |
| CN108962407A (en) * | 2018-06-13 | 2018-12-07 | 上海核工程研究设计院有限公司 | A kind of advanced Core makeup tank structure |
| CN108986935A (en) * | 2018-05-25 | 2018-12-11 | 中国核电工程有限公司 | A kind of nuclear power plant's accident hot trap water tank passive cooling system |
| CN109300556A (en) * | 2018-09-19 | 2019-02-01 | 中广核研究院有限公司 | A kind of reactor voltage-stabilizing system having peace pouring functions |
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| CN110911020A (en) * | 2019-12-04 | 2020-03-24 | 上海核工程研究设计院有限公司 | Configuration scheme of advanced special safety facility with double layers on top of pressure container |
| CN111898275B (en) * | 2020-08-03 | 2022-07-26 | 山东核电有限公司 | Pressurized water reactor decay heat analysis method |
| CN111898275A (en) * | 2020-08-03 | 2020-11-06 | 山东核电有限公司 | Pressurized water reactor decay heat analysis method |
| CN112420226B (en) * | 2020-11-19 | 2022-02-11 | 中国核动力研究设计院 | Passive residual heat removal system based on annular air cooler |
| CN112420226A (en) * | 2020-11-19 | 2021-02-26 | 中国核动力研究设计院 | Passive residual heat removal system based on annular air cooler |
| WO2022198826A1 (en) * | 2021-03-26 | 2022-09-29 | 中广核工程有限公司 | Emergency residual heat removal and water replenishing system for nuclear power plant |
| CN114171216A (en) * | 2021-10-27 | 2022-03-11 | 中国原子能科学研究院 | Passive residual heat removal device and nuclear reactor |
| CN114171216B (en) * | 2021-10-27 | 2024-05-14 | 中国原子能科学研究院 | Passive waste heat discharging device and nuclear reactor |
| CN114582529A (en) * | 2022-02-16 | 2022-06-03 | 中国核动力研究设计院 | Miniature full natural circulation pressurized water reactor system based on large coil pipe steam generator |
| CN115240880A (en) * | 2022-08-01 | 2022-10-25 | 哈尔滨工程大学 | Passive residual heat removal system and method capable of achieving continuous heat removal |
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