CN101800085B - Auxiliary water supply system used for nuclear power station single reactor and actuating safety function - Google Patents
Auxiliary water supply system used for nuclear power station single reactor and actuating safety function Download PDFInfo
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- CN101800085B CN101800085B CN200910008675XA CN200910008675A CN101800085B CN 101800085 B CN101800085 B CN 101800085B CN 200910008675X A CN200910008675X A CN 200910008675XA CN 200910008675 A CN200910008675 A CN 200910008675A CN 101800085 B CN101800085 B CN 101800085B
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- water supply
- pump
- feedwater
- auxiliary
- nuclear power
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 45
- 230000005520 electrodynamics Effects 0.000 claims description 13
- 238000002955 isolation Methods 0.000 claims description 9
- 230000001105 regulatory effect Effects 0.000 abstract 3
- 239000011148 porous material Substances 0.000 abstract 1
- 238000001816 cooling Methods 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 230000000694 effects Effects 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 239000008400 supply water Substances 0.000 description 2
- 238000006392 deoxygenation reaction Methods 0.000 description 1
- 239000002283 diesel fuel Substances 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
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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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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention belongs to auxiliary water supply systems of nuclear power stations, and particularly relates to an auxiliary water supply system used for a nuclear power station with single reactors and actuating safety function. The auxiliary water supply system comprises an auxiliary water supply tank, and two water supply series connecting the auxiliary water supply tank with an evaporator. Each water supply series comprises an electric pump and a pneumatic pump which are connected in parallel, each pump is provided with a regulating valve, and an isolating valve is arranged on a pipeline between the regulating valve and a pore plate. The evaporator supplies steam power for the pneumatic pumps through a steam turbine, a connecting valve and a connecting pipe are installed between the two water supply series, the joint points between the connecting pipe and water supply pipelines are arranged on the pipeline between the regulating valve and the isolating valve. Because each water supply pipeline in the two water supply series comprises one 100 percent of electric pump and one 100 percent of pneumatic pump which are connected in parallel, the safety of the system is increased. The auxiliary water supply system is especially suitable for the auxiliary water supply system in a nuclear power station with pressurized water reactors, and can efficiently increase the safety of the nuclear power station.
Description
Technical field
The present invention relates to a kind of auxiliary water feed system of nuclear power plant, be specifically related to a kind of auxiliary feedwater system of execution security function of nuclear power station single reactor use.
Background technology
Auxiliary feedwater system is one of engineered safeguards features of pressurized-water reactor nuclear power plant.When main feed system had an accident, auxiliary feedwater system put into operation, discharged residual heat of nuclear core.Particularly when full factory dead electricity accident (off-site power outage emergency diesel-oil dynamo-electric source forfeiture simultaneously), auxiliary feedwater system is a last resort of getting rid of residual heat of nuclear core.Therefore, the appropriate design of auxiliary feedwater system and good operation are vital to the safe operation of guaranteeing nuclear power station.
Auxiliary feedwater system is made up of two parts, the auxiliary feedwater system of the execution security function that the single heap of a part uses, and another part is an auxiliary feedwater system deoxygenation part.The present invention is primarily aimed at single heap of carrying out security function and uses part.This a part of groundwork principle is: auxiliary feed water pump draws water from auxiliary feed-water tank, finally injects evaporator through a series of pipelines, discharges residual heat of nuclear core.
At present; The scheme that the auxiliary feedwater system of the execution security function that the single heap of Daya Bay nuclear power plant uses adopts is managed interconnection type as mother; Being that each series supplies water for simultaneously 3 evaporators, can be that pneumatic pump provides steam-operating power through steam turbine by 3 evaporators simultaneously, as shown in Figure 1:
Series I uses 2 50% flow (every 100m
3/ h) electrodynamic pump, serial II uses 1 100% flow (200m
3/ h) pneumatic pump, promptly the auxiliary feedwater system of the execution security function used of the single heap of Daya Bay nuclear power plant uses 3 pumps altogether, and the system water supply ability is 2 * 100%, and the redundance of pump number is N+1.According to single failure criteria, under the situation of arbitrary pump maintenance, allow also that a pump damages and the function that do not influence system.And under four types of operating modes, if pneumatic pump is overhauling, an electrodynamic pump fault will cause cooling power not enough, can not effectively get rid of residual heat of nuclear core.This scheme that Daya Bay nuclear power plant adopts can't be brought reactor into the safe shutdown state, can not satisfy single failure criteria.
Wherein, single failure is meant the isolated random occurrence that hinders an equipment to accomplish its function, also regards single failure as by a plurality of faults that single incident causes.The multiplicity of the application requirements system design of single failure criteria is to guarantee the available rate of security system.Single failure criteria is a kind of decisive criterion that can prevent random fault.Should adopt a series of additional regulation to come to reduce the risk relevant with common mode failure as far as possible.
Four types of operating modes are meant: serious hypothetical accident.Four types of affiliated accidents of operating mode are thought improbable.But, consider that these accidents possibly discharge a large amount of radioactive products, thereby must study the consequence that these accidents cause power plant safety.The envelope accident of these accident representative designs.For example main feed water pipe road breaks or a main steam line breaks.When four types of operating modes took place, auxiliary feedwater system will replace main feedwater to supply water to steam generator, to derive residual heat of nuclear core.
Summary of the invention
The object of the present invention is to provide and a kind ofly can effectively get rid of residual heat of nuclear core, the auxiliary feedwater system of the execution security function that safe and reliable nuclear power station single reactor uses.
Realize the technical scheme of the object of the invention: the auxiliary feedwater system of the execution security function that a kind of nuclear power station single reactor uses; Comprise auxiliary feed-water tank, two feedwater series of connection auxiliary feed-water tank and evaporator, described feedwater series comprises pump, passes through the variable valve that pipeline is connected with pump; And the steam turbine that is connected with evaporator through pipeline; Be provided with orifice plate near the evaporator water inlet, described every feedwater series comprises an electrodynamic pump and pneumatic pump of parallel connection, and every pump all is equipped with variable valve; On the pipeline between variable valve and the orifice plate, be provided with isolation valve; Evaporator is that pneumatic pump provides steam-operating power through steam turbine, between two feedwater series, attachment valve and connecting pipe is installed, and the tie point between connecting pipe and the feed piping is located on the pipeline between variable valve and the isolation valve.
Effect of the present invention is: owing to each feedwater series in two feedwater series is all composed in parallel by one 100% electrodynamic pump and one 100% pneumatic pump, the redundance of the number of pump is N+3.Lose electric power at auxiliary feedwater system and perhaps lose under the situation of steam-operating power, because the power source difference that pump of each feedwater series adopts, each feedwater series can both keep 100% water supply capacity, guarantees its cooling power, effectively gets rid of residual heat of nuclear core.Under four types of operating modes, if wherein arbitrary pump (is common mode failure, is meant owing to cause the redundant channel above to be broken down with a kind of reason in maintenance or generation common cause failure.Should take measures to prevent the influence of common mode failure to influence the probability of each redundant channel simultaneously to protection system to reduce this type fault as far as possible), this auxiliary feedwater system still can satisfy single failure criteria, has improved the security of auxiliary feedwater system.And because the vapour road is improved,, can cut off the air feed of these row pneumatic pump automatically, reduce the loss of water tank feedwater when a certain row evaporator damages.Because the auxiliary feed-water tank water yield is limited, the loss that reduces feedwater will help to prolong the time of feedwater, bring to many dirigibilities to accident treatment.
Description of drawings
Fig. 1 is the auxiliary feedwater system structural representation of the execution security function of the single heap use of Daya Bay nuclear power plant;
Fig. 2 is the auxiliary feedwater system structural representation of the execution security function of a kind of nuclear power station single reactor use provided by the present invention.
Among the figure: 1. auxiliary feed-water tank; 2. evaporator; 3. electrodynamic pump; 4. pneumatic pump; 5. variable valve; 6. orifice plate; 7. connecting pipe; 8. steam turbine; 9. attachment valve; 10. isolation valve; 11. non-return valve.
Embodiment
Below in conjunction with accompanying drawing and embodiment the present invention is further described.
As shown in Figure 2, the auxiliary feedwater system of the execution security function that a kind of nuclear power station single reactor uses comprises auxiliary feed-water tank 1; It is serial with two feedwater of evaporator 2 to connect auxiliary feed-water tank 1; Described feedwater series comprises pump, passes through the variable valve 5 that pipeline is connected with pump, and through the steam turbine 8 that pipeline is connected with evaporator 2, is provided with orifice plate 6 near evaporator 2 water inlets; Described every feedwater series comprises an electrodynamic pump 3 and pneumatic pump 4 of parallel connection; Every pump all is equipped with variable valve 5, on the pipeline between variable valve 5 and the orifice plate 6, is provided with isolation valve 10, and evaporator 2 provides steam-operating power through steam turbine 8 for pneumatic pump 4; Between two feedwater series, attachment valve 9 and connecting pipe 7 are installed, the tie point between connecting pipe 7 and the feed piping is located on the pipeline between variable valve 5 and the isolation valve 10.Orifice plate 6 can play metering function when evaporator breaks down, the effect of non-return valve 11 is to prevent ducted gas backstreaming.
Under the normal condition; Two attachment valve 9 on the connecting pipe 7 all are in normally off; Can think this auxiliary feedwater system by two fully independently the feed piping subsystem form, every the feedwater series be parallel with an electrodynamic pump and a pneumatic pump, totally 4 pumps; Every pump has 100% flow, and the redundance of system is 4 * 100% under the nominal situation.The pump of every feedwater in the series supplies water only for an evaporator.
Illustrate under improper operating mode the working condition of auxiliary feedwater system below.When a serial electrodynamic pump 3 of feedwater breaks down; When the pneumatic pump 4 of another feedwater series overhauls; Still have a pump sufficient confluent to be provided on every feedwater series to evaporator 2; Bring reactor into the safe shutdown state, this auxiliary feedwater system not enough problem of cooling power under this type of operating mode with regard to having solved Daya Bay nuclear power plant.When auxiliary feedwater system lost electrodynamic source, the pneumatic pump 4 of every feedwater series can keep 100% water supply capacity, still can guarantee the confluent that it is sufficient.Equally, when auxiliary feedwater system lost the vapour power source, the electrodynamic pump 3 of every feedwater series can keep 100% water supply capacity.Auxiliary feedwater system is provided with the auxiliary feed water pump of four 100% of two electric two vapour, when single failure takes place, can not influence the security function of auxiliary feedwater system.Consider the worst situation; When an evaporator 2 damages; And the electrodynamic pump 3 of another evaporator place feedwater series can be taked following measure when damaging simultaneously with pneumatic pump 4: close the isolation valve 10 that damages before evaporator 2 water inlets, isolation accident evaporator 2; Open two attachment valve 9 on the connecting pipe 7, the two pumps that is in normal operating conditions just can supply water for intact evaporator 2 through this connecting pipe 7.
In use, four pumps can start according to actual conditions simultaneously, also can only start electrodynamic pump 3 or only start pneumatic pump 4.And can regulate the water supply capacity of pump through variable valve 5 according to the water yield in the evaporator 2.Through facts have proved: the security of auxiliary feedwater system of the present invention improves greatly.The present invention is very suitable for the auxiliary feedwater system of pressurized-water reactor nuclear power plant, can promote the security of nuclear power station effectively.
Obviously, those skilled in the art can carry out various changes and modification to the present invention and not break away from the spirit and scope of the present invention.Belong within the scope of claim of the present invention and equivalent technologies thereof if these are revised with modification, then the present invention also is intended to comprise these changes and modification interior.
Claims (1)
1. the auxiliary feedwater system of the execution security function used of a nuclear power station single reactor; Comprise auxiliary feed-water tank (1); It is serial with two feedwater of evaporator (2) to connect auxiliary feed-water tank (1); Described feedwater series comprises pump, passes through the variable valve (5) that pipeline is connected with pump, and through the steam turbine (8) that pipeline is connected with evaporator (2), is provided with orifice plate (6) near evaporator (2) water inlet; It is characterized in that: described every feedwater series comprises an electrodynamic pump (3) and a pneumatic pump (4) of parallel connection; Every pump all is equipped with described variable valve (5), on the pipeline between said variable valve (5) and the said orifice plate (6), is provided with isolation valve (10), and said evaporator (2) provides steam-operating power through said steam turbine (8) for pneumatic pump (4); Between two feedwater series, attachment valve (9) and connecting pipe (7) are installed, the tie point between said connecting pipe (7) and the feed piping is located on the pipeline between said variable valve (5) and the said isolation valve (10).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN200910008675XA CN101800085B (en) | 2009-02-11 | 2009-02-11 | Auxiliary water supply system used for nuclear power station single reactor and actuating safety function |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN200910008675XA CN101800085B (en) | 2009-02-11 | 2009-02-11 | Auxiliary water supply system used for nuclear power station single reactor and actuating safety function |
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| Publication Number | Publication Date |
|---|---|
| CN101800085A CN101800085A (en) | 2010-08-11 |
| CN101800085B true CN101800085B (en) | 2012-06-27 |
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| CN200910008675XA Expired - Fee Related CN101800085B (en) | 2009-02-11 | 2009-02-11 | Auxiliary water supply system used for nuclear power station single reactor and actuating safety function |
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Families Citing this family (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102252547A (en) * | 2011-04-15 | 2011-11-23 | 中国铝业股份有限公司 | Online maintenance and overhaul method of mobile device capable of substituting operation of heat exchanger |
| CN102759098B (en) * | 2012-05-09 | 2014-05-07 | 杨子路 | Non-kinetic energy water supplying system |
| MY187908A (en) * | 2012-09-27 | 2021-10-28 | China Nuclear Power Eng Co Ltd | Combined active and passive secondary-side reactor core heat removal apparatus |
| CN102903402A (en) * | 2012-09-27 | 2013-01-30 | 中国核电工程有限公司 | Advanced secondary side core heat lead-out device |
| CN103050161B (en) * | 2012-12-11 | 2016-03-30 | 中国核电工程有限公司 | The method of auxiliary feedwater pipeline automatism isolation |
| CN103363513B (en) * | 2013-07-24 | 2015-10-07 | 陕西钢铁集团有限公司 | A kind of water supply system of sintering waste heat generating boiler |
| CN203338776U (en) * | 2013-07-30 | 2013-12-11 | 中广核工程有限公司 | Nuclear power station vapor generator auxiliary feedwater system |
| CN104505130B (en) * | 2014-11-18 | 2017-11-10 | 上海核工程研究设计院 | A kind of passive emergency feedwater supply system of nuclear power station |
| CN111105882A (en) * | 2018-10-29 | 2020-05-05 | 华龙国际核电技术有限公司 | Water intake connecting pipe of waste heat discharge system and nuclear reactor |
| CN110761360B (en) * | 2019-10-08 | 2021-07-13 | 中国核电工程有限公司 | Water intaking system of nuclear power |
| CN113257444B (en) * | 2021-04-22 | 2022-09-09 | 广东核电合营有限公司 | Method for preventing overspeed tripping in full-flow test of auxiliary water supply steam-driven pump of nuclear power station |
| CN114352941B (en) * | 2021-12-20 | 2023-08-08 | 中船邮轮科技发展有限公司 | Post wheel cold drink water distribution system |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0157571A2 (en) * | 1984-04-05 | 1985-10-09 | Westinghouse Electric Corporation | Emergency feedwater system for steam generators of a nuclear power plant |
| CN1641798A (en) * | 2004-01-14 | 2005-07-20 | 株式会社东芝 | Emergency core cooling system |
-
2009
- 2009-02-11 CN CN200910008675XA patent/CN101800085B/en not_active Expired - Fee Related
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0157571A2 (en) * | 1984-04-05 | 1985-10-09 | Westinghouse Electric Corporation | Emergency feedwater system for steam generators of a nuclear power plant |
| CN1641798A (en) * | 2004-01-14 | 2005-07-20 | 株式会社东芝 | Emergency core cooling system |
Non-Patent Citations (2)
| Title |
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| 欧阳中华，胡劲松.M310型核电站给水泵配置优化讨论.《核动力工程》.2006,第27卷(第2期),全文. * |
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| CN101800085A (en) | 2010-08-11 |
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