CN104112481B - Reduce accident source term release device - Google Patents
Reduce accident source term release device Download PDFInfo
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- CN104112481B CN104112481B CN201410310652.5A CN201410310652A CN104112481B CN 104112481 B CN104112481 B CN 104112481B CN 201410310652 A CN201410310652 A CN 201410310652A CN 104112481 B CN104112481 B CN 104112481B
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- steam generator
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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 open one of the present invention reduces accident source term release device, including steam-water separation tank, slack tank, first isolating valve, second isolating valve, first pipeline, second pipe and the 3rd pipeline, steam-water separation tank connects with the first interface of steam generator by the first pipeline, first isolating valve is arranged on the first pipeline, slack tank is by the second orifice of second pipe Yu steam generator, second isolating valve is arranged on second pipe, steam-water separation tank and slack tank are by the 3rd pipeline communication, the first interface of steam generator is positioned on the second interface and is positioned at its top, the top of slack tank is less than the top of steam generator；In normal conditions, the present invention is evacuated, after having an accident, when steam generator water level reaches high water level, first and second isolating valve is opened, add air space so that radionuclide is by collected by slack tank, it is to avoid the situation of full water occurs, effectively alleviate or avoid contaminated water to be directly released in environment, the harm that the accident of decreasing is caused.
Description
Technical field
The present invention relates to a kind of used in nuclear power station device, particularly relate to one and act on steam generator for subtracting
The minimizing accident source term release device of few accident harm.
Background technology
Used in nuclear power station steam generator is the connection hinge in nuclear power unit one, between secondary circuit, is also core
Break down in power set operation one of most equipment；Wherein, the heat that nuclear reactor produces is cooled
Steam generator is taken in agent to, returns to reactor and continue cooling after steam generator cooling, and this is primary Ioops；Give
Steam generator supplies water, and steam generator produces the work of Steam Actuation steam turbine, and cooling condensed water returns to steam
Generator continues to produce steam, and this closed circuit is called secondary circuit, enters with steam generator for boundary's coolant
Enter a side loop of steam generator, it is simply that primary side of steam generator；Produce with steam generator for boundary and steam
One side loop of vapour, it is simply that steam generator secondary side.
The service behaviour of steam generator and security reliability for the safe and stable operation of whole nuclear power station be to
Close important；After existing PWR nuclear power plant accident, by steam generator secondary side atmospheric rilief valve
Discharge steam cools down primary Ioops, after steam generator full water, will directly put by atmospheric rilief valve
Penetrating property liquid, in external environment, so will cause steam generator accident (e.g., steam generator
Heat-transfer pipe break accident) after, the radioactive substance being discharged in environment exceeds standard, and will result in the core to environment dirty
Dye.
Therefore, need one badly can effectively prevent steam generator full water under accident conditions and reduce accident harm
Minimizing accident source term release device.
Summary of the invention
It is an object of the invention to provide one can effectively prevent steam generator full water and subtract under accident conditions
The minimizing accident source term release device of few accident harm.
For achieving the above object, the invention provides a kind of accident source term that reduces and discharge device, directly act on
On the steam generator of nuclear power station, wherein, described minimizing accident source term release device include steam-water separation tank,
Slack tank, the first isolating valve, the second isolating valve, the first pipeline, second pipe and the 3rd pipeline, described soda pop
Knockout drum connects with the first interface of described steam generator by described first pipeline, described first isolating valve
Being arranged on described first pipeline, described slack tank is by described second pipe and the second of described steam generator
Orifice, described second isolating valve is arranged on described second pipe, described steam-water separation tank and described sky
Tank is by described 3rd pipeline communication, and the first interface of described steam generator is positioned on described second interface,
And described first interface is positioned at the top of described steam generator, the top of described slack tank is sent out less than described steam
The top of raw device.
It is preferred that described minimizing accident source term release device also includes accident long-term disposal mechanism, described accident
Long-term disposal mechanism includes the 3rd isolating valve, the 4th pipeline and condenser, and one end of described condenser is with described
Steam-water separation tank connects, and the other end of described condenser connects with described second pipe by described 4th pipeline,
Described 3rd isolating valve is arranged on described 4th pipeline.
It is preferred that described accident long-term disposal mechanism also includes condensation water tank, inclined the putting of described condenser
Being placed in the bottom of described condensation water tank, the opening part of described condensation water tank seals by rupture disk.
It is preferred that described condensation water tank is cylindrical structural.
Compared with prior art, under accident conditions, trigger the present invention by steam generator high water level signal
The first isolating valve and the second isolating valve that reduce accident source term release device are opened, and the top of slack tank is less than
The top of steam generator so that slack tank and steam generator are connected formation linker by second pipe,
And then indirectly add the air space of steam generator, also make steam-water separation tank lead to steam generator simultaneously
Cross the first pipeline to be connected formation linker, and steam-water separation tank and slack tank are by the 3rd pipeline communication, from
And making after occurring such as accidents such as steam generator tube ruptures, steam generator water level reaches high water level
Time, by opening of the first isolating valve and the second isolating valve, steam-water separation tank, slack tank, the first pipeline,
Connect with steam generator under the interconnection function of second pipe and the 3rd pipeline and become an annular linker, make
The radionuclide (iodine and alkali metal nucleic) of secondary circuit must be discharged into from primary Ioops, by collected by slack tank, to keep away
Having exempted from steam generator under accident conditions and occurred that the situation of full water occurs, the accident of being effectively reduced is caused
Harm, solves in prior art and is directly discharged radiation because of what steam generator full water under accident conditions brought
Property liquid is to the technical problem of external environment.
Accompanying drawing explanation
Fig. 1 is the structural representation that the present invention reduces that accident source term release device is connected with steam generator.
Detailed description of the invention
With reference now to accompanying drawing, describing embodiments of the invention, element numbers similar in accompanying drawing represents similar unit
Part.
As it is shown in figure 1, the steam that the minimizing accident source term release device of the present invention directly acts on nuclear power station is sent out
On raw device, specifically, each steam generator is equipped with the minimizing accident source term release device of a present invention,
The present invention minimizing accident source term release device include steam-water separation tank 10, slack tank the 20, first isolating valve 31,
Second isolating valve the 32, first pipeline 41, second pipe 42 and the 3rd pipeline 43, described steam-water separation tank 10
Connect with the first interface 101 of described steam generator 100 by described first pipeline 41, described first every
Being arranged on described first pipeline 41 from valve 31, described first isolating valve 31 is used for controlling steam generator 100
The connected state (that is, connected state or off-state) of first interface 101 and steam-water separation tank 10, institute
State slack tank 20 to connect with the second interface 102 of described steam generator 100 by described second pipe 42,
Described second isolating valve 32 is arranged on described second pipe 42, and described second isolating valve 32 is used for controlling to steam
Second interface 102 of vapour generator 100 and the connected state of steam-water separation tank 10 (that is, connected state or disconnected
Open state), described steam-water separation tank 10 connects by described 3rd pipeline 43 with described slack tank 20, described
The first interface 101 of steam generator 100 is positioned on described second interface 102, and described first interface
101 tops being positioned at described steam generator 100, the top of described slack tank 20 is less than described steam generator
The top of 100；Under power plant's accidental conditions, the first isolating valve 31 and the second isolating valve 32 are turned off (i.e.,
Off-state), and slack tank the 20, first pipeline 41, second pipe 42 and the 3rd pipeline 43 be all evacuated,
After occurring such as steam generator 100 heat-transfer pipe break accident, steam generator 100 water level reaches high water level
Time, by the motor controlled corresponding to isolating valve, the first isolating valve 31 and the second isolating valve 32 are all beaten
Open (that is, connected state) so that slack tank 20 and steam generator 100 is connected shape by second pipe 42
One-tenth linker, and then indirectly add the air space of steam generator 100, also make steam-water separation tank simultaneously
10 are connected formation linker, and steam-water separation tank 10 by the first pipeline 41 with steam generator 100
Connected by the 3rd pipeline 43 with slack tank 20 so that be discharged into the radionuclide (iodine of secondary circuit from primary Ioops
And alkali metal nucleic) by collected by slack tank 20, it is to avoid under accident conditions, there is full water in steam generator 100
Situation occur, effectively alleviate or avoid contaminated water to be directly released in environment, decreasing accident institute
The harm caused.
As shown in Figure 1 preferably, described minimizing accident source term release device also include accident long-term disposal machine
Structure, described accident long-term disposal mechanism includes the 3rd isolating valve the 33, the 4th pipeline 44 and condenser 50, institute
State the 3rd isolating valve 33 to be arranged on described 4th pipeline 44, one end of described condenser 50 by pipeline with
Described steam-water separation tank 10 connects, the other end of described condenser 50 by described 4th pipeline 44 with described
Second pipe 42 connects, so that the branch road at condenser 50 place and steam-water separation tank 10 and slack tank 20
The branch road at place forms loop in parallel, further adds the air space of steam generator 100；In power plant
Under accidental conditions, the 4th pipeline 44 and condenser 50 are evacuated equally, and the 3rd isolating valve 33 closes
Closing, after occurring such as steam generator 100 heat-transfer pipe break accident, steam generator 100 water level reaches high
During water level, the first isolating valve 31 is all opened with the second isolating valve 32, accident long periods, operator
Member can open the 3rd isolating valve 33, after opening the 3rd isolating valve 33, the accident of the present invention according to the actual requirements
Long-term disposal mechanism just comes into operation, and owing to condenser 50 is interconnected with steam-water separation tank 10, therefore exists
In the case of the existence of steam-water separation tank 10, enter the water in the pipeline of the present invention and enter slack tank 20 and be collected,
Steam in pipeline then enters the branch road of condenser 50 and cools down, it is achieved thereby that the coldest to primary Ioops
But, the safety of nuclear power plant is further increased；Simultaneously in order to ensure further safety, more specifically
Ground, described accident long-term disposal mechanism also includes condensation water tank 60, described inclined being positioned over of condenser 50
The bottom of described condensation water tank 60, the opening part of described condensation water tank 60 seals by rupture disk 70, by cold
Condensation tank 60 is placed on the outer safe Factory Building top of containment, due to condensation water tank 60 by rupture disk 70 with big
Gas phase is led to, and owing to condenser 50 realizes the purpose that cools down steam in it by heat exchange, is condensed
The heat that device 50 is exchanged is transferred to again in the cooling water in condensation water tank 60, thus causes condensed water
Cooling water temperature in case 60 raises, and the temperature of condensation water tank 60 inner cooling water raises will cause condensation water tank
The air space pressure on 60 tops increases, when this pressure increases to the limiting pressure that rupture disk 70 can bear,
The rupture disk 70 of the opening part being sealed in condensation water tank 60 will be broken through, so that condensation water tank 60 is with outer
Boundary's environmental communication, further improves the safety of nuclear power plant.
Preferably, described condensation water tank 60 is in cylindrical structural, and the condensation water tank 60 of cylindrical structural is more
It is beneficial to install and use.
Shown in Fig. 1, under accident conditions, trigger this by steam generator 100 high water level signal
First isolating valve 31 and second isolating valve 32 of bright minimizing accident source term release device are opened, and slack tank 20
Top less than the top of steam generator 100 so that slack tank 20 and steam generator 100 are by the second pipe
Road 42 is connected formation linker, and then indirectly adds the air space of steam generator 100, also makes simultaneously
Steam-water separation tank 10 and steam generator 100 passes through the first pipeline 41 and is connected formation linker, and
Steam-water separation tank 10 is connected by the 3rd pipeline 43 with slack tank 20, so that occurring such as steam generator
After the accidents such as heat-transfer pipe ruptures, when steam generator 100 water level reaches high water level, by the first isolating valve 31
And second the opening of isolating valve 32, steam-water separation tank 10 and slack tank 20 are at the first pipeline 41, second pipe
42 and the 3rd pipeline 43 interconnection function under connect with steam generator 100 and to become an annular linker, make
The radionuclide (iodine and alkali metal nucleic) of secondary circuit must be discharged into by collected by slack tank 20 from primary Ioops,
Avoiding steam generator under accident conditions and occur that the situation of full water occurs, the accident of being effectively reduced is caused
Harm, solve in prior art because what steam generator full water under accident conditions was brought directly puts
Penetrating property liquid is to the technical problem of external environment.Meanwhile, at accident long periods, operator are according to reality
Demand can open the 3rd isolating valve 33, owing to condenser 50 is interconnected with steam-water separation tank 10, therefore exists
In the case of the existence of steam-water separation tank 10, enter the water in the pipeline of the present invention and enter slack tank 20 and be collected,
Steam in pipeline then enters the branch road of condenser and cools down, it is achieved thereby that the long-term cooling to primary Ioops,
Further increase the safety of nuclear power plant.
For the safety of nuclear power plant, the first interface 101 place branch road of steam generator 100 connects the most successively
It is connected to air steam exhaust system (that is, GCT-a), main steam safety valve (that is, MSSV), main steam isolation
Valve (that is, MSIV) and main steam line (that is, VVP)；Second interface 102 of steam generator 100 simultaneously
Place branch road is connected with check (non-return) valve 103, isolating valve 104 and auxiliary feedwater system (that is, ASG) in turn；Above-mentioned
These are provided to basic setup necessary to the safety of nuclear power, for common knowledge, are people in the art
Technology known to Yuan, therefore its involved operation principle and effect, be no longer described in detail at this.
Separately, steam generator 100, isolating valve 31,32,33 and the knot of condenser 50 involved in the present invention
Structure and operation principle, be well known to those of ordinary skill in the art, be no longer described in detail at this.
Above disclosed only the preferred embodiments of the present invention, can not limit the present invention with this certainly
Interest field, the equivalent variations therefore made according to scope of the present invention patent, still belong to the present invention and contained
Scope.
Claims (4)
1. reducing an accident source term release device, directly act on the steam generator of nuclear power station, it is special
Levy and be: described minimizing accident source term release device include steam-water separation tank, slack tank, the first isolating valve, the
Two isolating valves, the first pipeline, second pipe and the 3rd pipeline, described steam-water separation tank is by described first pipe
Road connects with the first interface of described steam generator, and described first isolating valve is arranged on described first pipeline,
Described slack tank is by the second orifice of described second pipe Yu described steam generator, described second isolation
Valve is arranged on described second pipe, described steam-water separation tank and described slack tank by described 3rd pipeline communication,
The first interface of described steam generator is positioned on described second interface, and described first interface is positioned at described
The top of steam generator, the top of described slack tank is less than the top of described steam generator.
2. the accident source term that reduces as claimed in claim 1 discharges device, it is characterised in that: also include accident
Long-term disposal mechanism, described accident long-term disposal mechanism includes the 3rd isolating valve, the 4th pipeline and condenser,
One end of described condenser connects with described steam-water separation tank, and the other end of described condenser is by the described 4th
Pipeline connects with described second pipe, and described 3rd isolating valve is arranged on described 4th pipeline.
3. the accident source term that reduces as claimed in claim 2 discharges device, it is characterised in that: described accident is long
Phase processing mechanism also includes condensation water tank, and what described condenser was inclined is positioned over the bottom of described condensation water tank,
The opening part of described condensation water tank seals by rupture disk.
4. the accident source term that reduces as claimed in claim 3 discharges device, it is characterised in that: described condensed water
Case is cylindrical structural.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410310652.5A CN104112481B (en) | 2014-07-01 | 2014-07-01 | Reduce accident source term release device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410310652.5A CN104112481B (en) | 2014-07-01 | 2014-07-01 | Reduce accident source term release device |
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| Publication Number | Publication Date |
|---|---|
| CN104112481A CN104112481A (en) | 2014-10-22 |
| CN104112481B true CN104112481B (en) | 2016-08-17 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201410310652.5A Active CN104112481B (en) | 2014-07-01 | 2014-07-01 | Reduce accident source term release device |
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Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN107068214B (en) * | 2017-05-09 | 2024-03-26 | 中广核研究院有限公司 | Nuclear power plant steam atmosphere discharge device and two-loop pressure release method |
| CN111145922A (en) * | 2018-11-05 | 2020-05-12 | 中广核（北京）仿真技术有限公司 | Apparatus and method for preventing core melting and release of radiation into the environment |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3662718A (en) * | 1971-03-02 | 1972-05-16 | Atomic Energy Commission | Sodium heated steam generator |
| JPS5455296A (en) * | 1977-10-12 | 1979-05-02 | Mitsubishi Atom Power Ind Inc | Residual heat removing system of fast breeder type reactor |
| CN202887746U (en) * | 2012-08-20 | 2013-04-17 | 中国核电工程有限公司 | Active and passive combined reactor core surplus heat discharging system for nuclear power station |
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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) Applicant after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Applicant 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) Applicant before: Zhongkehua Nuclear Power Technology Institute Co., Ltd. Applicant before: China General Nuclear Power Corporation |
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