CN105070329A - Nuclear power station secondary side passive residual heat removal system - Google Patents
Nuclear power station secondary side passive residual heat removal system Download PDFInfo
- Publication number
- CN105070329A CN105070329A CN201510548746.0A CN201510548746A CN105070329A CN 105070329 A CN105070329 A CN 105070329A CN 201510548746 A CN201510548746 A CN 201510548746A CN 105070329 A CN105070329 A CN 105070329A
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- emergence compensating
- water case
- steam
- compensating water
- power station
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 75
- 238000002955 isolation Methods 0.000 claims abstract description 30
- 239000007788 liquid Substances 0.000 claims description 12
- 230000008676 import Effects 0.000 claims description 6
- 230000003020 moisturizing effect Effects 0.000 claims description 5
- 230000005574 cross-species transmission Effects 0.000 claims description 3
- 230000007123 defense Effects 0.000 claims description 3
- 230000005484 gravity Effects 0.000 claims description 3
- 238000002347 injection Methods 0.000 claims description 2
- 239000007924 injection Substances 0.000 claims description 2
- 238000000034 method Methods 0.000 description 7
- 239000002826 coolant Substances 0.000 description 4
- 230000008569 process Effects 0.000 description 4
- 230000004048 modification Effects 0.000 description 3
- 238000012986 modification Methods 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
- 238000001816 cooling 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
- 239000000203 mixture Substances 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
- 230000001052 transient effect Effects 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
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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention provides a nuclear power station secondary side passive residual heat removal system, which comprises a steam generator and a emergency make-up water tank, wherein an outlet of the steam generator is connected on one end of the emergency make-up water tank through a main steam pipeline by passing through an emergency make-up water tank isolation valve, the other end of the emergency make-up water tank is connected with an inlet of the steam generator through the emergency make-up water pipeline by passing through an emergency make-up water tank outlet isolation valve and an emergency make-up water tank outlet check valve, the main steam pipeline is further connected onto a steam discharge pipeline through a steam discharge valve, and the emergency make-up water pipeline is further connected onto a water supply pipeline through a water supply check valve and a water supply isolation valve.
Description
Technical field
The present invention relates to nuclear power station safety full guard field, relate to a kind of nuclear power station Passive 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 invention provides a kind of nuclear power station Passive residual heat removal system, comprise steam generator, emergence compensating water case, the outlet of described steam generator is connected to one end of emergence compensating water case through emergence compensating water case import isolation valve by main steam pipe, the other end of described emergence compensating water case exports isolation valve by emergence compensating water pipeline through emergence compensating water case, emergence compensating water case outlet non-return valve connects the entrance of steam generator, described main steam pipe is also connected to steam discharge line through steam release valve, described emergence compensating water pipeline is also through feed water check valve, feedwater isolation valve is connected to water-supply line.
Further, described main steam pipe is also connected to main steam isolation valve.
Further, described emergence compensating water case is the equipment of initial press, and original pressure is less than steam generator secondary side operating pressure.
Further, described system enters by main steam the pressure equilibrium that emergence compensating water case sets up emergence compensating water case and steam generator secondary side, and realizes moisturizing requirement by gravity injection.
Further, described emergence compensating water case outlet isolation valve is connected with liquid level control loop.Controlled the keying of emergence compensating water case outlet isolation valve by steam generator secondary side liquid level instrument, realize moisturizing requirement and prevent steam generator spill-over.
Further, described system take air as ultimate heat sink, by steam discharge line to airborne release steam, to take away reactor core decay heat.
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 nuclear power station Passive residual heat removal system general flow chart.
Reference numeral
1-steam generator 2-liquid level gauge 3-main steam pipe 4-main steam isolation valve
5-steam release valve 6-steam discharge line 7-emergence compensating water case import isolation valve
8-emergence compensating water pipeline 9-emergence compensating water case 10-emergence compensating water case outlet isolation valve
11-liquid level control loop 12-emergence compensating water case outlet non-return valve 13-feed water check valve
14-feedwater isolation valve 15-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, composition graphs 1 is described further Passive residual heat removal system of the present invention.As shown in Figure 1, a kind of nuclear power station Passive residual heat removal system provided by the invention, comprise steam generator 1, emergence compensating water case 9, one end of emergence compensating water case 9 is received in the outlet of described steam generator 1 through emergence compensating water case import isolation valve 7 by main steam pipe 3, the other end of described emergence compensating water case 9 passes through emergence compensating water pipeline through 8, emergence compensating water case outlet isolation 10, emergence compensating water case outlet non-return valve 12 connects the entrance of steam generator 1, described main steam pipe 3 is also connected to steam discharge line 6 through steam release valve 5, described emergence compensating water pipeline 8 is also through feed water check valve 13, feedwater isolation valve 14 is connected to water-supply line 15.
Passive residual heat removal system is arranged on outside the containment of reactor, and under normal operation, Passive residual heat removal system is in stand-by state, is full of high pressure subcooled water in emergence compensating water case.Itself and main steam pipe 3 and water-supply line 15 are isolated with outlet isolation valve 10 and non-return valve 12 by the import isolation valve 7 of emergence compensating water case.In one embodiment, steam generator is connected with liquid level gauge 2,
When occurring to lose main water supply accident, main steam isolation valve 4 and feedwater isolation valve 14 are closed, and steam release valve 5 is opened.Open emergence compensating water case import isolation valve 7 simultaneously, pressure in emergence compensating water case 9 and steam generator 1 secondary pressure in a basic balance time, open emergence compensating water case outlet isolation valve 10, the subcooled water in emergence compensating water case 9 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 9 and maintains pressure equilibrium, remaining steam enters air by steam release valve 5 and steam discharge line 6, thus realize taking away reactor core decay heat, until the normal residual heat removal system of primary Ioops puts into operation.
In operational process, liquid level control loop 11 implements the liquid level of monitoring steam generator 1, the paramount liquid level setting valve if steam generator 1 liquid level rises, then close emergence compensating water case outlet isolation valve 10, when liquid level drops to setting value, reopen emergence compensating water case outlet isolation valve 10, realize non-active water filling, thus ensure the moisturizing requirement of steam generator 1, and prevent steam generator 1 from spill-over occurring.
Said process utilizes non-active equipment and discharge of steam to take 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 (7)
1. a nuclear power station Passive residual heat removal system, it is characterized in that, comprise steam generator, emergence compensating water case, the outlet of described steam generator is connected to one end of emergence compensating water case through emergence compensating water case import isolation valve by main steam pipe line, the other end of described emergence compensating water case exports isolation valve by emergence compensating water pipeline through emergence compensating water case, emergence compensating water case outlet non-return valve connects the entrance of steam generator, described main steam pipe is also connected to steam discharge line through steam release valve, described emergence compensating water pipeline is also through feed water check valve, feedwater isolation valve is connected to water-supply line.
2. nuclear power station Passive residual heat removal system as claimed in claim 1, it is characterized in that, described main steam pipe is also connected to main steam isolation valve.
3. nuclear power station Passive residual heat removal system as claimed in claim 1, it is characterized in that, described emergence compensating water case is the equipment of initial press, and original pressure is less than steam generator secondary side operating pressure.
4. nuclear power station Passive residual heat removal system as claimed in claim 1, it is characterized in that, described system enters by main steam the pressure equilibrium that emergence compensating water case sets up emergence compensating water case and steam generator secondary side, and realizes moisturizing requirement by gravity injection.
5. nuclear power station Passive residual heat removal system as claimed in claim 1, is characterized in that, described emergence compensating water case outlet isolation valve is connected with liquid level control loop.Controlled the keying of emergence compensating water case outlet isolation valve by steam generator secondary side liquid level instrument, realize moisturizing requirement and prevent steam generator spill-over.
6. nuclear power station Passive residual heat removal system as claimed in claim 1, it is characterized in that, described system take air as ultimate heat sink, by steam discharge line to airborne release steam, to take away reactor core decay heat.
7. nuclear power station Passive residual heat removal system 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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| CN201510548746.0A CN105070329A (en) | 2015-08-31 | 2015-08-31 | Nuclear power station secondary side passive residual heat removal system |
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| CN201510548746.0A CN105070329A (en) | 2015-08-31 | 2015-08-31 | Nuclear power station secondary side passive residual heat removal system |
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| CN105070329A true CN105070329A (en) | 2015-11-18 |
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| CN201510548746.0A Pending CN105070329A (en) | 2015-08-31 | 2015-08-31 | Nuclear power station secondary side passive residual heat removal system |
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107644693A (en) * | 2017-08-01 | 2018-01-30 | 中广核研究院有限公司 | Naval reactor and once through steam generator Passive residual heat removal system |
| CN107665742A (en) * | 2017-08-21 | 2018-02-06 | 中广核研究院有限公司 | It is active with the passive naval reactor being combined meet an urgent need residual heat removal system |
| CN108447570A (en) * | 2018-05-15 | 2018-08-24 | 中广核研究院有限公司 | Naval reactor and its Passive residual heat removal system |
| CN110021447A (en) * | 2018-01-10 | 2019-07-16 | 中广核（北京）仿真技术有限公司 | A kind of secondary side passive residual heat deriving system |
| CN110148480A (en) * | 2019-05-28 | 2019-08-20 | 中广核研究院有限公司 | A kind of nuclear power secondary coolant circuit system |
| 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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| CN204229849U (en) * | 2014-11-18 | 2015-03-25 | 上海核工程研究设计院 | The non-active emergency feedwater supply system of a kind of nuclear power station |
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2015
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107644693A (en) * | 2017-08-01 | 2018-01-30 | 中广核研究院有限公司 | Naval reactor and once through steam generator Passive residual heat removal system |
| CN107665742A (en) * | 2017-08-21 | 2018-02-06 | 中广核研究院有限公司 | It is active with the passive naval reactor being combined meet an urgent need residual heat removal system |
| CN107665742B (en) * | 2017-08-21 | 2019-11-15 | 中广核研究院有限公司 | It is active to meet an urgent need residual heat removal system with the passive naval reactor that combines |
| CN110021447A (en) * | 2018-01-10 | 2019-07-16 | 中广核（北京）仿真技术有限公司 | A kind of secondary side passive residual heat deriving system |
| CN110021447B (en) * | 2018-01-10 | 2021-06-11 | 中广核（北京）仿真技术有限公司 | Secondary side passive waste heat deriving system |
| CN108447570A (en) * | 2018-05-15 | 2018-08-24 | 中广核研究院有限公司 | Naval reactor and its Passive residual heat removal system |
| CN108447570B (en) * | 2018-05-15 | 2023-12-26 | 中广核研究院有限公司 | Marine reactor and secondary side passive waste heat discharging system thereof |
| CN110148480A (en) * | 2019-05-28 | 2019-08-20 | 中广核研究院有限公司 | A kind of nuclear power secondary coolant circuit system |
| 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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