CN105070327A - Nuclear power station secondary side long-term waste heat removal system - Google Patents
Nuclear power station secondary side long-term waste heat removal system Download PDFInfo
- Publication number
- CN105070327A CN105070327A CN201510548603.XA CN201510548603A CN105070327A CN 105070327 A CN105070327 A CN 105070327A CN 201510548603 A CN201510548603 A CN 201510548603A CN 105070327 A CN105070327 A CN 105070327A
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- heat exchanger
- water
- isolation valve
- outlet
- secondary side
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- 230000007774 longterm Effects 0.000 title claims abstract description 19
- 239000002918 waste heat Substances 0.000 title abstract 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 69
- 238000002955 isolation Methods 0.000 claims abstract description 36
- 238000001816 cooling Methods 0.000 claims abstract description 6
- 230000008676 import Effects 0.000 claims description 10
- 238000012546 transfer Methods 0.000 claims description 4
- 230000007123 defense Effects 0.000 claims description 3
- 230000005484 gravity Effects 0.000 claims description 3
- 230000003020 moisturizing effect Effects 0.000 claims description 2
- 238000000034 method Methods 0.000 description 6
- 239000002826 coolant Substances 0.000 description 4
- 230000004048 modification Effects 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- 230000008859 change Effects 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 230000009471 action Effects 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
- 230000001052 transient effect Effects 0.000 description 1
Classifications
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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 provides a nuclear power station secondary side long-term waste heat removal system, which comprises a steam generator, wherein an outlet of the steam generator is connected with a steam discharge pipeline through a main steam pipeline by passing through a steam discharge valve, an inlet of the steam generator is connected onto a water supply pipeline through a water supply check valve and a water supply isolation valve, an emergency make-up water tank and a heat exchanger are connected between the main steam pipeline and the water supply pipeline in parallel, an inlet of the emergency make-up water tank is connected onto the main steam pipeline through an emergency make-up water tank inlet isolation valve and an emergency make-up water pipeline, an emergency make-up water tank outlet is connected onto a water supply pipeline through an emergency make-up water tank outlet isolation valve and an emergency make-up water tank check valve, a heat exchanger inlet is connected onto the main steam pipeline through a heat exchanger inlet isolation valve and a cooling circulation pipeline, and a heat exchanger outlet is connected onto a water supply pipeline through a heat exchanger outlet isolation valve and a heat exchanger outlet check valve.
Description
Technical field
The present invention relates to nuclear power station safety full guard field, relate to a kind of nuclear power station secondary side Residual heat removal system particularly.
Background technology
The emergency feedwater supply system of conventional pressurized water heap is as back-up system use when main feedwater was lost efficacy of main feed system.Under the breakdown operating mode of power station, emergency feedwater supply system is used for maintaining power station hot shutdown operating mode with time enough, and reactor is cooled to the state that residual heat removal system can put into operation.Emergency feedwater supply system belongs to engineered safeguards features, and under the transient state losing main feedwater or secondary side steam line break, emergency feedwater supply system is used to prevent reactor core from damaging, and discharges reactor core decay heat, until residual heat removal system puts into operation.Non-security relevant startup water supply system is provided with in third generation advanced pressurized water reactor, this system layout is at conventional island, in the main feedwater of forfeiture and forfeiture normal communication electricity event, feedwater is provided to steam generator from the water suction of condensate water tank, thus realize the depth defense function of discharging reactor coolant loop heat, prevent passive safety system action.In above process, the heat of reactor coolant loop passes to secondary coolant circuit system by steam generator, and secondary coolant circuit system is by taking heat out of to turbine bypass system or airborne release.
In existing presurized water reactor emergency feedwater supply system, mainly through power supply or diesel engine as drive source, and with rotating machinery to steam generator conveying feedwater, to take away reactor core decay heat.If can design a kind of have non-can dynamic characteristic and do not have the residual heat removal system of moving component, by making, the safety system of nuclear power station is more safe and reliable.
Summary of the invention
The object of the present invention is to provide a kind of long-term residual heat removal system of nuclear power station secondary side, do not need power drives and the Diesel Driven of traditional core power plant, and do not have rotating machinery and moving component, system is simple and reliable.
The long-term residual heat removal system of a kind of nuclear power station secondary side provided by the invention, comprise steam generator, described steam generator outlet connects steam discharge line by main steam pipe through steam release valve, the entrance of described steam generator is through feed water check valve, feedwater isolation valve is connected to water-supply line, emergence compensating water case is connected in parallel between described main steam pipe and described water-supply line, heat exchanger, the import of described emergence compensating water case is connected to main steam pipe by emergence compensating water case import isolation valve and emergence compensating water pipeline, described emergence compensating water case outlet is through anxious water supply tank outlet isolation valve, emergence compensating water case outlet non-return valve is connected to water-supply line, described heat exchanger inlets is by heat exchanger inlets isolation valve, cool cycles pipeline is connected to described main steam pipe, described heat exchanger outlet is by heat exchanger outlet isolation valve, heat exchanger outlet non-return valve is connected to water-supply line.
In one embodiment, described main steam pipe is also connected to main steam isolation valve.The subcooled water of initial press is housed in described emergence compensating water case.
Further, described system is at the Residual heat removal initial stage, and being injected by gravity by emergence compensating water case is steam generator moisturizing, and by steam discharge line to airborne release steam, to take away reactor core decay heat.
Further, described system, at long-term cooling stage, by Natural Circulation by heat delivery heat exchanger, and passes through pipe outer air convection heat transfer by delivered heat to air.
Native system can be the system that safety is relevant, also can perform the non-safety-related system of depth defense function.
Accompanying drawing explanation
Fig. 1 is the long-term residual heat removal system general flow chart of nuclear power station secondary side.
Reference numeral
1-steam generator 2-main steam pipe 3-main steam isolation valve 4-steam release valve
5-steam discharge line 6-emergence compensating water case import isolation valve 7-emergence compensating water pipeline
8-emergence compensating water case 9-emergence compensating water case outlet isolation valve 10-emergence compensating water case outlet non-return valve
11-heat exchanger inlets isolation valve 12-long-term cool cycles pipeline 13-heat exchanger
14-heat exchanger outlet isolation valve 15-heat exchanger outlet non-return valve 16-feed water check valve
17-feedwater isolation valve 18-water-supply line
Embodiment
For enabling above-mentioned purpose of the present invention, feature and advantage become apparent more, and below in conjunction with the drawings and specific embodiments, the present invention is further detailed explanation.
The present embodiment is implemented premised on technical solution of the present invention, give detailed embodiment and concrete operating process, but protection scope of the present invention is not limited to following embodiment.
In order to understand the present invention more clearly, occur to lose main water supply accident for nuclear power station below, the long-term residual heat removal system of composition graphs 1 to secondary side of the present invention is described further.As shown in Figure 1, a kind of nuclear power station secondary side residual heat removal system provided by the invention, comprise steam generator 1, described steam generator 1 exports and connects steam discharge line 2 by main steam pipe through steam release valve, the entrance of described steam generator 1 is through feed water check valve 16, feedwater isolation valve 17 is connected to water-supply line 18, emergence compensating water case 8 is connected in parallel between described main steam pipe 2 and described water-supply line 18, heat exchanger 13, the import of described emergence compensating water case 8 is connected to main steam pipe 2 by emergence compensating water case 8 import isolation valve 6 and emergence compensating water pipeline 7, described emergence compensating water case outlet is through anxious water supply tank outlet isolation valve 9, emergence compensating water case 8 outlet non-return valve is connected to water-supply line 18, the import of described heat exchanger 13 is by heat exchanger inlets isolation valve 11, cool cycles pipeline 12 is connected to described main steam pipe 2, described heat exchanger outlet is by heat exchanger outlet isolation valve 14, heat exchanger outlet non-return valve 15 is connected to water-supply line 18.
The long-term residual heat removal system of secondary side is arranged on outside the containment of reactor, and under normal operation, the long-term residual heat removal system of secondary side is in stand-by state, is full of high pressure subcooled water in emergence compensating water case 8, is full of low pressure subcooled water in heat exchanger 13.By the import isolation valve 6,11 of emergence compensating water case 8 and heat exchanger 13 and outlet isolation valve 9,14 and non-return valve 10,15, itself and main steam pipe 2 and water-supply line 18 are isolated.
When occurring to lose main water supply accident, main steam isolation valve 3 and feedwater isolation valve 17 are closed, and steam release valve 4 is opened.Open emergence compensating water case import isolation valve 6 simultaneously, pressure in emergence compensating water case 8 and steam generator 1 secondary pressure in a basic balance time, open emergence compensating water case outlet isolation valve 9, the subcooled water in emergence compensating water case 8 injects steam generator 1 under gravity.Subcooled water is become saturated vapour by thermal conversion in steam generator 1, some vapor enters emergence compensating water case 8 and maintains pressure equilibrium, remaining steam enters air by steam release valve 4 and steam discharge line 5, thus realize taking away reactor core decay heat, until the normal residual heat removal system of primary Ioops puts into operation.
After the cooling that emergence compensating water case 8 completes the first stage, as long-term cooling need be realized by secondary side residual heat removal system, then open heat exchanger inlets isolation valve 11 and outlet isolation valve 14 successively, at steam generator 1, main steam pipe 2, form natural convection loop between cool cycles pipeline 12 and water-supply line 18 for a long time, heat, by heat being entered air by pipe outer convection heat transfer in heat exchanger 13, realizes long-term Residual heat removal.
Said process utilizes non-active equipment and discharge of steam, and convection heat transfer takes away decay heat and the sensible heat of primary Ioops, realizes the cooling of primary Ioops, has good feasibility and reliability.
The connection of former components is only exemplary illustration of the present invention and non-limitative illustration, also can be other connected modes.
Although accompanying drawing describes example comprehensively, various diagram can illustrate exemplary architecture of the present disclosure or other configurations, and it is with helping understand the Characteristic and function that can comprise in the disclosure.The disclosure is not limited to the exemplary architecture that illustrates or configuration, but available various substituting framework and configuration are implemented.In addition, although describe the disclosure about various example and realization above, should be understood that various Characteristic and function of one or more description in the example shown are not limited to describe their specific examples in their applicability.But, one or more in other examples of the present disclosure, they can be employed individually or with certain combination, and no matter whether such example is described, and no matter such feature as the part of the example described by this place.Again, the scope of the present disclosure should not by any one restriction of above-mentioned example.
In this instructions, each embodiment adopts the mode of going forward one by one to describe, and what each embodiment stressed is the difference with other embodiments, between each embodiment identical similar portion mutually see.For system disclosed in embodiment, owing to corresponding to the method disclosed in Example, so description is fairly simple, relevant part illustrates see method part.
Those skilled in the art can use distinct methods to realize described function to each specifically should being used for, but this realization should not thought and exceeds scope of the present invention.
Obviously, those skilled in the art can carry out various change and modification to invention and not depart from the spirit and scope of the present invention.Like this, if these amendments of the present invention and modification belong within the scope of the claims in the present invention and equivalent technologies thereof, then the present invention is also intended to comprise these change and modification.
Claims (6)
1. the long-term residual heat removal system of a nuclear power station secondary side, it is characterized in that, comprise steam generator, described steam generator outlet connects steam discharge line by main steam pipe through steam release valve, the entrance of described steam generator is through feed water check valve, feedwater isolation valve is connected to water-supply line, emergence compensating water case is connected in parallel between described main steam pipe and described water-supply line, heat exchanger, the import of described emergence compensating water case is connected to main steam pipe by emergence compensating water case import isolation valve and emergence compensating water pipeline, described emergence compensating water case outlet is through anxious water supply tank outlet isolation valve, emergence compensating water case outlet non-return valve is connected to water-supply line, described heat exchanger inlets is by heat exchanger inlets isolation valve, cool cycles pipeline is connected to described main steam pipe, described heat exchanger outlet is by heat exchanger outlet isolation valve, heat exchanger outlet non-return valve is connected to water-supply line.
2. the long-term residual heat removal system of nuclear power station secondary side as claimed in claim 1, it is characterized in that, described main steam pipe is also connected to main steam isolation valve.
3. the long-term residual heat removal system of nuclear power station secondary side as claimed in claim 1, it is characterized in that, described emergence compensating water case is equipped with the subcooled water of initial press.
4. the long-term residual heat removal system of nuclear power station secondary side as claimed in claim 1, it is characterized in that, described system is at the Residual heat removal initial stage, and being injected by gravity by emergence compensating water case is steam generator moisturizing, and by steam discharge line to airborne release steam, to take away reactor core decay heat.
5. the long-term residual heat removal system of nuclear power station secondary side as claimed in claim 1, is characterized in that, described system at long-term cooling stage, by Natural Circulation by heat delivery heat exchanger, and by pipe outer air convection heat transfer by delivered heat to air.
6. the long-term residual heat removal system of nuclear power station secondary side as claimed in claim 1, is characterized in that, described system can be the system that safety is relevant, also can perform the non-safety-related system of depth defense function.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN201510548603.XA CN105070327A (en) | 2015-08-31 | 2015-08-31 | Nuclear power station secondary side long-term waste heat removal system |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201510548603.XA CN105070327A (en) | 2015-08-31 | 2015-08-31 | Nuclear power station secondary side long-term waste heat removal system |
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| CN105070327A true CN105070327A (en) | 2015-11-18 |
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| CN201510548603.XA Pending CN105070327A (en) | 2015-08-31 | 2015-08-31 | Nuclear power station secondary side long-term waste heat removal system |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105608979A (en) * | 2016-02-23 | 2016-05-25 | 中广核研究院有限公司 | Test device for simulating steam generator secondary side waste heat exhaust system and method |
| CN114914002A (en) * | 2022-04-11 | 2022-08-16 | 中广核研究院有限公司 | Passive heat export system of direct current steam generator |
| WO2023231358A1 (en) * | 2022-06-02 | 2023-12-07 | 中广核研究院有限公司 | Double-loop small pressurized water reactor emergency residual heat removal system |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN105608979A (en) * | 2016-02-23 | 2016-05-25 | 中广核研究院有限公司 | Test device for simulating steam generator secondary side waste heat exhaust system and method |
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| CN114914002A (en) * | 2022-04-11 | 2022-08-16 | 中广核研究院有限公司 | Passive heat export system of direct current steam generator |
| WO2023231358A1 (en) * | 2022-06-02 | 2023-12-07 | 中广核研究院有限公司 | Double-loop small pressurized water reactor emergency residual heat removal system |
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |
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| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20151118 |