CN206541632U - A kind of secondary side residual heat removal system - Google Patents
A kind of secondary side residual heat removal system Download PDFInfo
- Publication number
- CN206541632U CN206541632U CN201621058471.9U CN201621058471U CN206541632U CN 206541632 U CN206541632 U CN 206541632U CN 201621058471 U CN201621058471 U CN 201621058471U CN 206541632 U CN206541632 U CN 206541632U
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- China
- Prior art keywords
- steam
- secondary side
- water
- heat removal
- residual heat
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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 utility model provides a kind of secondary side residual heat removal system, and it is included：Steam jet pump, it is arranged between the main steam pipe of once through steam generator and water-supply line, is configured to provide feedwater；And starting water tank, it is arranged on the water-supply line of once through steam generator.The voltage-stablizer spraying system for the nuclear power station that the utility model is provided, on the basis of traditional nuclear power station provides spraying using reactor coolant pump, adds steam jet pump spraying loop；When reactor coolant pump is out of service, the saturated vapor provided by voltage-stablizer as jet pump driving source, jet pump absorbs water for cold section from reactor coolant pipe, injection voltage-stablizer air space after boosted, so as to realize the purpose of reduction voltage-stablizer pressure, spraying system can therefore still can use in the case of some dead electricity, the reliability of spraying system is greatly increased.
Description
Technical field
The utility model is related to nuclear power station safety full guard system, and in particular to a kind of direct-flow steam for nuclear power station occurs
The secondary side residual heat removal system of device.
Background technology
The secondary side residual heat removal system of presurized water reactor is used when losing main feedwater.Under the breakdown operating mode of power station, two
Secondary side residual heat removal system is used for maintaining power station hot shutdown operating mode with time enough, and reactor is cooled into normal waste heat
The state that discharge system can put into operation.Non-security relevant startup water supply system is provided with AP1000 presurized water reactors, this is
System is arranged in conventional island, in losing main feedwater and losing the electric event of normal communication, is absorbed water from condensate tank to steam generation
Device provides feedwater, so as to realize the depth defense function of discharge reactor coolant loop heat, prevents passive safety system
Action.In above process, the heat of reactor coolant loop passes to secondary coolant circuit system, secondary circuit by steam generator
System is by taking heat out of to turbine bypass system or air discharge.
Utility model content
The utility model in view of the shortcomings of the prior art, proposes a kind of secondary side residual heat removal system.
Secondary side residual heat removal system includes：
Steam jet pump, it is arranged between the main steam pipe of once through steam generator and water-supply line, is configured to
Feedwater is provided；And
Start water tank, it is arranged on the water-supply line of once through steam generator.
Preferably, the startup water tank is provided with pressurized gas lines, is configured to maintain startup water tank to keep necessarily
Pressure.
Preferably, in addition to main steam pipe, it is configured to, when losing normal feedwater, in time be isolated.
Preferably, the startup water tank is configured to be pressurized backward once through steam generator water filling, and the steam of generation is
Jet pump provides driving steam, and feedwater is provided to steam generator.
Preferably, regulating valve is provided with driving steam pipe line, is configured for use in regulation quantity of steam to control feedwater
Flow.
Preferably, the system is used for the once through steam generator of nuclear power station.
Compared with prior art, the utility model has the advantages that：
1st, the secondary side residual heat removal system that the utility model is provided, is set on the water-supply line of once through steam generator
The startup water tank of pressurization, when losing normal feedwater, isolates main steam pipe in time, by the startup water tank of pressurization to direct current
Steam generator water filling, the steam of generation provides driving steam for jet pump, provides feedwater to steam generator, and pass through steam
Discharge pipe line discharge steam takes away heat, and some vapor circulation is as driving steam, so as to constantly provide feedwater to take away reactor core
Decay heat, makes the secondary side residual heat removal system of nuclear power station more safe and reliable.
Brief description of the drawings
The secondary side residual heat removal system flow letter of the once through steam generator for the nuclear power station that Fig. 1 provides for the utility model
Figure.
Wherein, 1-reactor pressure vessel；2-reactor coolant pump；Cold section of 3-reactor coolant pipe；4—
Reactor coolant pipe hot arc；5-once through steam generator；6-main steam pipe；7-release pipeline；8-pressure-relief valve；
9-main steam isolation valve；10-jet pump steam inlet pipe line；11-driving steam control valve；12-jet pump back with water inlet line；13—
Spray pump water inlet isolating valve；14-jet pump；15-feed water check valve；16-water-supply line；17-pressurized gas lines；18—
Gas-pressurized isolating valve；19-gas-pressurized check-valves；20-start water tank；21-waterflood-transmission line；22-waterflood-transmission line is isolated
Valve；23-waterflood-transmission line check-valves.
Embodiment
To enable above-mentioned purpose of the present utility model, feature and advantage more obvious understandable, below in conjunction with the accompanying drawings and tool
Body embodiment is described in further detail to the utility model.
As shown in figure 1, secondary side residual heat removal system includes：Steam jet pump, it is arranged on once through steam generator
Between main steam pipe and water-supply line, it is configured to provide feedwater；And starting water tank, it is arranged on once through steam generator
On water-supply line.The startup water tank is provided with pressurized gas lines, is configured to maintain to start the pressure that water tank keeps certain.
Secondary side residual heat removal system also includes main steam pipe, is configured to, when losing normal feedwater, in time be isolated.It is described to open
Dynamic water tank is configured to be pressurized backward once through steam generator water filling, and the steam of generation provides driving steam for jet pump, to
Steam generator provides feedwater.Drive and regulating valve is provided with steam pipe line, be configured for use in regulation quantity of steam to control
Feedwater flow.The system is used for the once through steam generator of nuclear power station.
The secondary side residual heat removal system of the once through steam generator of nuclear power station, including main steam pipe, start water tank, plus
Calm the anger fluid line, jet pump and water-supply line.Under normal operation, driving steam control valve 11, injection pump water inlet isolating valve
13 and gas-pressurized isolating valve 18 close, by main feed system be once through steam generator 5 feedwater is provided.When startup water tank 20
When pressure is reduced to below setting value, gas-pressurized isolating valve 18 is opened, is inflated to water tank is started.
When occurring to lose main water supply accident, main steam isolation valve 9 is closed in time.Waterflood-transmission line isolating valve is opened simultaneously
22nd, driving steam control valve 11 and injection pump water inlet isolating valve 13, start the reclaimed water of water tank 20 under pressure through water-supply line
16 injection once through steam generators 5.Feedwater is transformed into after steam enters jet pump 14 through jet pump steam inlet pipe line 10, by jet pump
After fluid suction mixing boosting in back with water inlet line 12, once through steam generator 5 is injected through water-supply line 16, is transformed into after steam
Into main steam pipe 6, pressure-relief valve 8 is opened in good time, and some vapor is discharged into air by release pipeline 7 and takes away reactor core heat, portion
Steam is divided to enter jet pump steam inlet pipe line 10, continuing as the offer driving of jet pump 14 steam, there is provided feedwater.
Compared with prior art, the present embodiment has the advantages that：
1st, the secondary side residual heat removal system that the present embodiment is provided, is provided with the water-supply line of once through steam generator
The startup water tank of pressurization, when losing normal feedwater, isolates main steam pipe, is steamed by the startup water tank of pressurization to direct current in time
Vapour generator water filling, the steam of generation provides driving steam for jet pump, provides feedwater to steam generator, and arrange by steam
Put pipeline discharge steam and take away heat, some vapor circulation is declined as driving steam so as to constantly provide feedwater with taking away reactor core
Heating, makes the secondary side residual heat removal system of nuclear power station more safe and reliable.
The embodiment of each in this specification is described by the way of progressive, and what each embodiment was stressed is and other
Between the difference of embodiment, each embodiment identical similar portion mutually referring to.For system disclosed in embodiment
For, due to corresponding to the method disclosed in Example, so description is fairly simple, related part is referring to method part illustration
.
Those skilled in the art can realize described function to each specific application using distinct methods, but
It is this realize it is not considered that beyond scope of the present utility model.
Obviously, those skilled in the art can be new without departing from this practicality to the various changes of utility model progress and modification
The spirit and scope of type.So, if these modifications and variations of the present utility model belong to the utility model claim and its
Within the scope of equivalent technologies, then the utility model is also intended to including these changes and modification.
Claims (6)
1. a kind of secondary side residual heat removal system, it is characterised in that including：
Steam jet pump, it is arranged between the main steam pipe of once through steam generator and water-supply line, is configured to provide
Feedwater；And
Start water tank, it is arranged on the water-supply line of once through steam generator.
2. secondary side residual heat removal system according to claim 1, it is characterised in that the startup water tank is provided with pressurization
Gas line, is configured to maintain to start the pressure that water tank keeps certain.
3. secondary side residual heat removal system according to claim 1, it is characterised in that also including main steam pipe, through with
Put, when losing normal feedwater, in time to be isolated.
4. secondary side residual heat removal system according to claim 1, it is characterised in that the startup water tank be configured to by
Pressurize backward once through steam generator water filling, the steam of generation provides driving steam for jet pump, is supplied to steam generator
Water.
5. secondary side residual heat removal system according to claim 1, it is characterised in that be provided with and adjust on driving steam pipe line
Valve is saved, is configured for use in regulation quantity of steam to control feedwater flow.
6. secondary side residual heat removal system according to claim 1, it is characterised in that the system is used for the straight of nuclear power station
Flow steam generator.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201621058471.9U CN206541632U (en) | 2016-09-14 | 2016-09-14 | A kind of secondary side residual heat removal system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201621058471.9U CN206541632U (en) | 2016-09-14 | 2016-09-14 | A kind of secondary side residual heat removal system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN206541632U true CN206541632U (en) | 2017-10-03 |
Family
ID=59936811
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201621058471.9U Active CN206541632U (en) | 2016-09-14 | 2016-09-14 | A kind of secondary side residual heat removal system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN206541632U (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108766599A (en) * | 2018-04-17 | 2018-11-06 | 哈尔滨工程大学 | A kind of nuclear power station passive residual heat removal system using spraying technique |
| CN113380433A (en) * | 2021-05-07 | 2021-09-10 | 苏州热工研究院有限公司 | Passive special safety system and water supply system for nuclear power plant |
| CN113421667A (en) * | 2021-05-10 | 2021-09-21 | 中广核研究院有限公司 | Reactor primary loop spraying system |
-
2016
- 2016-09-14 CN CN201621058471.9U patent/CN206541632U/en active Active
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108766599A (en) * | 2018-04-17 | 2018-11-06 | 哈尔滨工程大学 | A kind of nuclear power station passive residual heat removal system using spraying technique |
| CN113380433A (en) * | 2021-05-07 | 2021-09-10 | 苏州热工研究院有限公司 | Passive special safety system and water supply system for nuclear power plant |
| CN113421667A (en) * | 2021-05-10 | 2021-09-21 | 中广核研究院有限公司 | Reactor primary loop spraying system |
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Legal Events
| Date | Code | Title | Description |
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| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| CP01 | Change in the name or title of a patent holder | ||
| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |