CN103531256B - The non-active cooling system of presurized water reactor prestressed concrete containment vessel - Google Patents
The non-active cooling system of presurized water reactor prestressed concrete containment vessel Download PDFInfo
- Publication number
- CN103531256B CN103531256B CN201310513382.3A CN201310513382A CN103531256B CN 103531256 B CN103531256 B CN 103531256B CN 201310513382 A CN201310513382 A CN 201310513382A CN 103531256 B CN103531256 B CN 103531256B
- Authority
- CN
- China
- Prior art keywords
- water
- containment
- comer
- storage tank
- hot
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 103
- 238000001816 cooling Methods 0.000 title claims abstract description 56
- 239000011513 prestressed concrete Substances 0.000 title claims abstract description 11
- 239000004567 concrete Substances 0.000 claims abstract description 4
- 229910000831 Steel Inorganic materials 0.000 claims description 11
- 239000010959 steel Substances 0.000 claims description 11
- 239000011148 porous material Substances 0.000 claims description 10
- 239000000498 cooling water Substances 0.000 claims description 5
- 239000000941 radioactive substance Substances 0.000 claims description 3
- 230000000694 effects Effects 0.000 claims description 2
- 210000002435 tendon Anatomy 0.000 claims 1
- 239000011150 reinforced concrete Substances 0.000 abstract description 3
- 238000005516 engineering process Methods 0.000 description 3
- 238000010276 construction Methods 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 238000012544 monitoring process Methods 0.000 description 2
- 239000007921 spray Substances 0.000 description 2
- 229910000975 Carbon steel Inorganic materials 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 239000010962 carbon steel Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 239000008236 heating water Substances 0.000 description 1
- 230000008676 import Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000001681 protective effect Effects 0.000 description 1
- 238000003908 quality control method Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000003014 reinforcing effect Effects 0.000 description 1
- 239000002689 soil Substances 0.000 description 1
Classifications
-
- 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
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The present invention relates to the non-active cooling system of presurized water reactor prestressed concrete containment vessel, belong to the safety devices technical field of reactor. This system comprises: water storage tank, containment, many down-comers, many water cooling tubes, hot water header, hot arc; Wherein, all down-comers are all positioned at containment reinforced concrete structure, and all water cooling tubes are all positioned at containment inner side; Each down-comer and water cooling tube are all vertical array; Every water cooling tube lower end is connected with every down-comer lower end, and down-comer upper end is connected with water tank bottom; Every water cooling tube upper end is connected with hot water header lower end; Hot water header upper end is connected with hot arc lower end; Hot arc upper end is connected with water tank bottom. The present invention uses non-passive safety design concept, simple in structure, adopt less equipment to design individual layer concrete containment and simple Passive containment cooling system, system only relies on Natural Circulation in the time of operation, drive without any need for external force, effectively reduce the thrashing causing because of active component fault, improved economy and the security of reactor.
Description
Technical field
The invention belongs to the safety devices technical field of reactor, relate in particular to a kind of presurized water reactor prestressed concrete containment vessel non-
Active cooling system.
Background technology
Containment is the structures that contain nuclear reactor and some systems, radioactive substance while being used for preventing nuclear safety accident
Discharge to environment, and protective reaction reactor coolant pressure-bearing boundary and security system are avoided external event impact.
When reactor loss of-coolant accident (LOCA), reactor core heat is discharged in containment in a large number, makes containment internal pressure and temperature excursion, needs
To heat be set out to ultimate heat sink by the containment cooling system of special setting, otherwise, the increasing of shell internal pressure and temperature
May exceed containment design benchmark, jeopardize its safety, thereby cause the nuclear safety accident that serious radioactive substance leaks,
This is in nuclear reactor designs, to need one of most important safety problem of paying close attention to.
In two traditional generations and two generations, add containment vessel and mostly are prestressed reinforced concrete construction, inside establish containment spray system, by
Signal transducer starts, and spray pump, for system provides power, belongs to active security system, therefore can not resist picture Fukushima, Japan
The major accident occurring.
The double containment of reactor AP1000 is mixed by cylindrical steel container made and the outer field reinforcing bar of core band elliposoidal end socket
Solidifying soil shielding structures form. Double containment design raises containment vessel construction cost. Simultaneously huge steel peace
Full shell is processed, assembling difficulty is large, and quality control difficulty, exists certain potential safety hazard. In addition, AP1000 containment needs profit
Trigger containment top discharge valve of cistern for water-closet by external signal and open, not completely non-active. Double containment phase with AP1000
Ratio, prestressed concrete containment vessel cost reduces greatly. The cooling system being arranged in concrete containment replaces steel safety
Shell, economy and the security that can further improve reactor.
Summary of the invention
The object of the invention is the weak point for overcoming prior art, design a kind of presurized water reactor prestressed concrete containment vessel
Non-active cooling system, this system architecture is simple, and failure probability is extremely low; Do not need external power source, completely non-active;
And there is no huge steel containment vessel, can improve security and economy; Can guarantee system conditions and failure conditions
Promptly and accurately monitoring.
For solving the problems of the technologies described above, the invention provides the non-active cooling system of a kind of prestressed concrete containment vessel, its spy
Levy and be, comprising:
Water storage tank, containment, down-comer, water cooling tube, hot water header, hot arc, reactor pressure vessel;
Described down-comer is positioned at containment xoncrete structure, and water cooling tube is positioned at containment inner side, around described reactor pressure
Container is arranged.
Described water storage tank is also provided with pore, and bottom is connected with the upper end of down-comer and hot arc.
Described water storage tank is positioned at containment center of top.
Described water cooling tube and down-comer uniformly-spaced arrange, and vertical array.
Described hot arc lower end is connected with described hot water header.
Described water cooling tube two ends are connected with described hot water header with described down-comer lower end respectively.
Cooling system is also provided with outlet plug and entrance float, lays respectively in described hot arc and is connected with water storage tank with down-comer
Place.
Described water storage tank, down-comer, water cooling tube and containment inner surface are all lined with in steel lining.
On described pore, be also provided with an electric butterfly valve of often opening.
Described water storage tank top is also provided with top cover, air flow channel and screen pack.
The present invention can produce following beneficial effect:
The invention provides a kind of prestressed concrete containment vessel cooling system based on non-passive safety design concept. With
AP1000 compares, and huge steel containment vessel has been cancelled in this design, has better security and economy; With traditional
Two generation reactor compare, the operation of the cooling system of this containment need to be by the action of any active component, also without
Under accident conditions, start or switch, operation automatically, only relies on the natural circulation mode can be by the heat in reactor all the time
In containment, reaching ultimate heat sink---atmosphere, has the features such as simple in structure, failure rate is low.
1. when system works in cooling circuit without any active component, adopt water natural circulation mode to carry out heat exchange completely, be
Unite simple in structure, failure probability is extremely low;
2. do not need external power source, the driving force of Natural Circulation only relies on the difference in height between water storage tank and down-comer, with
And the recirculated water density that heats up after being heated reduces the lifting pressure head producing;
3. system maintains the stable of environment in containment in the time of normal reactor operation, does not need to take any opening when accident conditions
Moving or handover operation can be carried out containment refrigerating function, completely non-active;
4. system is provided with entrance plug and outlet float, can occur disconnected run affairs thus time automatically fall and block the mouth of pipe, avoid cooling
Water depletion;
5. can ensure still boiling lower than water under operating pressure of hot arc outlet water temperature under emergency conditions by concrete system
Point, makes system move in the mode of single-phase water, guarantees effective foundation of Natural Circulation;
6. there is no huge steel containment vessel, can improve security and economy;
7. cooling system can arrange the independently measuring point such as water cooling tube out temperature, water cooling tube rate of discharge, to guarantee system
The promptly and accurately monitoring of operating condition and failure conditions.
Brief description of the drawings
Fig. 1 is system principle structural representation of the present invention;
Fig. 2 is entrance cell of the present invention and plug partial structurtes schematic diagram;
Fig. 3 is that system axle of the present invention measures intention.
Wherein, 1, water storage tank; 2, containment; 3, down-comer; 4, cooling tube; 5, hot water header; 6, hot arc; 7,
Reactor pressure vessel; 8, pore.
Detailed description of the invention
Under regard to the non-active cooling system of a kind of prestressed concrete containment vessel proposed by the invention, by reference to the accompanying drawings and implement
Example describes in detail.
The invention provides a kind of structure of the prestressed concrete containment vessel cooling system based on non-passive safety design concept
As shown in Figure 1,3, by water storage tank 1, containment 2, many down-comers 3, many water cooling tubes 4, hot water header 5, hot arc
6 compositions such as parts such as grade. Wherein, all down-comers 3 are all positioned at containment reinforced concrete structure, all positions of all water cooling tubes 4
In containment inner side. Each down-comer 3 and water cooling tube 4 are all vertical array, are spacedly distributed. Every water cooling tube 4 lower end with
Every down-comer 3 lower ends are connected, and down-comer 3 upper ends are connected with water storage tank 1 bottom; Every water cooling tube 4 upper end and hot water connection
Case 5 lower ends are connected, and hot water header 5 upper ends are connected with hot arc 6 lower ends; Cooling by water cooling tube 4 separately of hot water header 5
Water is collected to hot arc 6. Hot arc 6 upper ends are connected with water storage tank 1 bottom, and junction is provided with outlet float; There is the disconnected event of running affairs
In time, exports float and can under the effect of linking springs, automatically fall and block the mouth of pipe, prevents that cooling water from losing.
Water storage tank 1 is positioned at containment 2 top center, and bottom and each down-comer 3 junctions are provided with entrance cell 9, inside insert
Mouth plug 10, as shown in Figure 2; Occur disconnected run affairs thus time plug 10 can automatically fall and block down-comer 3 mouths of pipe, prevent cold
But water depletion. Water storage tank 1 upper wall is also provided with pore 8, and pore 8 tops arrange top cover 11 and are connected with water storage tank 1 sidewall, top
Between lid 11 and water storage tank 1 sidewall, be provided with air flow channel 12 and screen pack 13. In addition, for extreme accident conditions after
From containment and external environment, pore 8 places are provided with an electric butterfly valve 14(Fig. 1 who often opens), only in the time of extreme accident conditions
Close.
Described water storage tank 1, down-comer 3, water cooling tube 4 and containment 2 inner surfaces are all lined with in steel lining.
Operation principle of the present invention is as follows: owing to having the larger temperature difference, reaction between the interior gas of containment 2 and water cooling tube 4
In heap, heat mainly reaches water cooling tube 4 by condensing heat-exchange, and free convection and the radiation of gas simultaneously also can strengthen and water cooling tube
Heat transfer between 4. Heat reaches the cooling water in the rear heating water cooling tube 4 of water cooling tube 4. Due to water storage tank 1 and water cooling tube 4
Between there is certain difference in height, after recirculated water is heated produce promote pressure head, become the driving force of Natural Circulation and make it upwards
Flow to water storage tank 1, with the cold water mix release heat in water storage tank 1, in water storage tank 1 water under Action of Gravity Field through down-comer
3 downstreams, to water cooling tube 4 lower ends, complete circulation; When whole cooling waters all reach after 100 ° of C, the interior water of water storage tank 1 is continuous
Evaporation, reaches ultimate heat sink by pore by interior containment 2 heat---atmosphere.
Because the present invention is passive system, can automatically put into operation without any starting the operating system. The pass of impact operation
Key problem is the exhaust work while moving for the first time, the air in pipeline should be emptied completely, otherwise can not form sufficient nature
Circulation. After Natural Circulation is stable, in the time of normal reactor operation, system can maintain the stable of the interior environment of containment; In thing
Therefore under operating mode, in containment, temperature and pressure raises, the Natural Circulation of cooling system can be strengthened, thereby takes more heat out of,
Realize the cooling function of containment.
Embodiment
The present invention is taking 1700MW reactor as example, and the detail parameters of the present embodiment is as follows: pipeline material is SA516-70.
The long 51m of down-comer 3 is the passage that cold water declines. The long 50m of water cooling tube 4, wherein vertical direction length is 30m, level
The long 20m of direction is the heat exchange interface of system. The long 6m of hot arc 6, the hot water after hot water header 5 is collected imports water storage tank 1
In. Water storage tank 1 material is carbon steel, high 16m, and internal diameter 24m, is the hot trap of system.
As can be seen from the above embodiments, the present invention uses non-passive safety design concept, there is no huge steel containment vessel,
Simple in structure, adopt less equipment to design simple Passive containment cooling system, system only relies on certainly in the time of operation
So circulation, does not need any external force to drive, and has effectively reduced the thrashing causing because of active component fault, has improved reaction
Economy and the security of heap.
Above embodiment is only for the present invention is described, but not limitation of the present invention, the ordinary skill people in relevant technologies field
Member, without departing from the spirit and scope of the present invention, can also make a variety of changes and modification, therefore all being equal to
Technical scheme also belong to category of the present invention, scope of patent protection of the present invention should be defined by the claims.
Claims (3)
1. the non-active cooling system of prestressed concrete containment vessel, is characterized in that, this system comprises: water storage tank,
Containment, many down-comers, many water cooling tubes, hot water header, hot arc; Wherein, all down-comers are all positioned at containment steel
In tendon concrete structure, all water cooling tubes are all positioned at containment inner side; Each down-comer and water cooling tube are all vertical array; Every
Water cooling tube lower end is connected with every down-comer lower end, and down-comer upper end is connected with water tank bottom; Every water cooling tube upper end is with hot
Water manifold lower end is connected; Hot water header upper end is connected with hot arc lower end; Hot arc upper end is connected with water tank bottom, and nature is followed
Loop back path is airtight, prevents Natural Circulation interruption; Described water storage tank is enclosed water storage tank, is positioned at containment top center, to increase
Strong system Natural Circulation and heat-carrying capacity; Upper wall is provided with pore, and pore top arranges top cover and is connected with water storage tank sidewall, top cover
And between water storage tank sidewall, be provided with air flow channel and screen pack;
Described hot arc upper end and water tank bottom junction are provided with outlet float, described water tank bottom and each down-comer junction
Be provided with entrance cell, interior posting port plug; When run affairs event for breaking in generation, export under the effect of float at linking springs automatic
Fall and block the mouth of pipe, prevent cooling water forfeiture.
Described pore place is provided with an electric butterfly valve of often opening, and makes water vapour evaporator strip walking system heat; Only superpose in pipeline breaking
When float and plug lose efficacy extreme accident conditions, closed, prevented that in containment, radioactive substance leaked.
2. the system as claimed in claim 1, is characterized in that, described down-comer and water cooling tube uniformly-spaced arrange, and perpendicular
To arrangement.
3. the system as claimed in claim 1, is characterized in that, described water storage tank, down-comer, water cooling tube and containment
Inner surface is all lined with in steel lining.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201310513382.3A CN103531256B (en) | 2013-10-25 | 2013-10-25 | The non-active cooling system of presurized water reactor prestressed concrete containment vessel |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201310513382.3A CN103531256B (en) | 2013-10-25 | 2013-10-25 | The non-active cooling system of presurized water reactor prestressed concrete containment vessel |
Publications (2)
Publication Number | Publication Date |
---|---|
CN103531256A CN103531256A (en) | 2014-01-22 |
CN103531256B true CN103531256B (en) | 2016-05-25 |
Family
ID=49933199
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201310513382.3A Active CN103531256B (en) | 2013-10-25 | 2013-10-25 | The non-active cooling system of presurized water reactor prestressed concrete containment vessel |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN103531256B (en) |
Families Citing this family (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN106328223B (en) * | 2016-09-05 | 2018-06-22 | 中广核研究院有限公司 | A kind of novel passive containment energy management system |
CN108154942B (en) * | 2016-12-05 | 2023-09-15 | 国核示范电站有限责任公司 | Passive containment external air cooler device |
CN108630328B (en) * | 2017-03-24 | 2024-05-07 | 国核示范电站有限责任公司 | Passive containment built-in heat exchanger system |
CN108766595A (en) * | 2018-05-25 | 2018-11-06 | 哈尔滨工程大学 | External prestressing-steel concrete composite structure Nuclear containment new structure |
CN110594899A (en) * | 2019-08-15 | 2019-12-20 | 中国核电工程有限公司 | Passive emergency cooling system |
Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5178185A (en) * | 1991-03-06 | 1993-01-12 | Hydra-Shield Manufacturing Inc. | Suction inlet valve for fire truck pumpers |
CN201281156Y (en) * | 2008-07-30 | 2009-07-29 | 中芯国际集成电路制造(上海)有限公司 | Self-closing valve |
CN102243897A (en) * | 2011-06-27 | 2011-11-16 | 华北电力大学 | Passive residual heat removal system under accident of boiling-water reactor based on characteristics of nanometer fluid |
CN102563999A (en) * | 2012-01-17 | 2012-07-11 | 清华大学 | Passive natural circulation cooling system |
CN202691178U (en) * | 2012-07-27 | 2013-01-23 | 苏州纽威阀门股份有限公司 | Nuclear secondary lifting-type check valve |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP4398640B2 (en) * | 2002-12-16 | 2010-01-13 | 株式会社東芝 | Reactor containment cooling equipment |
-
2013
- 2013-10-25 CN CN201310513382.3A patent/CN103531256B/en active Active
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5178185A (en) * | 1991-03-06 | 1993-01-12 | Hydra-Shield Manufacturing Inc. | Suction inlet valve for fire truck pumpers |
CN201281156Y (en) * | 2008-07-30 | 2009-07-29 | 中芯国际集成电路制造(上海)有限公司 | Self-closing valve |
CN102243897A (en) * | 2011-06-27 | 2011-11-16 | 华北电力大学 | Passive residual heat removal system under accident of boiling-water reactor based on characteristics of nanometer fluid |
CN102563999A (en) * | 2012-01-17 | 2012-07-11 | 清华大学 | Passive natural circulation cooling system |
CN202691178U (en) * | 2012-07-27 | 2013-01-23 | 苏州纽威阀门股份有限公司 | Nuclear secondary lifting-type check valve |
Also Published As
Publication number | Publication date |
---|---|
CN103531256A (en) | 2014-01-22 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN202887748U (en) | Passive heat discharge device for dealing with plant switch-off accident | |
CN202855316U (en) | Containment cooling system for PWR (pressurized water reactor) nuclear power plant | |
CN204596431U (en) | Passive containment thermal conduction system and the pressurized water reactor with it | |
CN103531256B (en) | The non-active cooling system of presurized water reactor prestressed concrete containment vessel | |
CN106104701B (en) | Containment cooling system and containment combine cooling system with reactor pressure vessel | |
CN102522127B (en) | Passive containment thermal conduction system | |
CN203931515U (en) | Based on actively adding of 177 reactor cores non-active nuclear steam supply system and nuclear power station thereof | |
WO2014029306A1 (en) | Secondary-side passive residual heat discharge system for nuclear power plant steam generator | |
CN202102728U (en) | Safety system used for guaranteeing safety of nuclear power plant | |
CN102332313A (en) | Passive residual heat removal system for high temperature gas cooled reactor | |
WO2014048290A1 (en) | Combined active and passive reactor cavity water injection cooling system | |
CN104103325B (en) | Heat derivation system for long-term passive containment | |
CN104361914A (en) | Passive safe cooling system | |
CN202887745U (en) | Active and passive combined safety shell heat extraction device | |
CN103985422A (en) | Active and passive nuclear steam supplying system based on 177 reactor core and nuclear power station thereof | |
CN202615805U (en) | Non-dynamic safety case cooling system | |
CN106328223B (en) | A kind of novel passive containment energy management system | |
CN103903657B (en) | The non-active ultimate heat sink cooling system of nuclear power plant and method | |
CN102881342A (en) | Active and passive combined heat removal device for containment | |
CN104021824B (en) | In-pile melts retention system after nuclear power station accident | |
KR101250479B1 (en) | Apparatus for safety improvement of passive type emergency core cooling system with a safeguard vessel and Method for heat transfer-function improvement using thereof | |
CN102820067B (en) | Natural circulation heat exchanger for discharging waste heat of supercritical water reactor | |
CN104134474B (en) | passive cooling system | |
CN206601953U (en) | Cooling system outside a kind of passive pressure vessel | |
CN104751907B (en) | The passive water charging system in Nuclear Power Station's Exhausted Fuels pond |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
C06 | Publication | ||
PB01 | Publication | ||
C10 | Entry into substantive examination | ||
SE01 | Entry into force of request for substantive examination | ||
C14 | Grant of patent or utility model | ||
GR01 | Patent grant |