CN107631280A - A kind of continuous steam generator of nuclear power station - Google Patents
A kind of continuous steam generator of nuclear power station Download PDFInfo
- Publication number
- CN107631280A CN107631280A CN201711090922.6A CN201711090922A CN107631280A CN 107631280 A CN107631280 A CN 107631280A CN 201711090922 A CN201711090922 A CN 201711090922A CN 107631280 A CN107631280 A CN 107631280A
- Authority
- CN
- China
- Prior art keywords
- header
- heat
- reallocation
- steam
- transfer pipe
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 238000012546 transfer Methods 0.000 claims abstract description 38
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 12
- 238000007689 inspection Methods 0.000 abstract description 7
- 230000033228 biological regulation Effects 0.000 abstract description 6
- 238000013461 design Methods 0.000 abstract description 3
- 230000006641 stabilisation Effects 0.000 abstract description 3
- 238000011105 stabilization Methods 0.000 abstract description 3
- 239000002826 coolant Substances 0.000 description 7
- 239000012530 fluid Substances 0.000 description 4
- 238000000034 method Methods 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000001035 drying Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000011161 development Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 230000000750 progressive effect Effects 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 238000003860 storage Methods 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
Abstract
The present invention provides a kind of continuous steam generator of nuclear power station, and it includes：Feed water distributor box, heat-transfer pipe, reallocation header and steam header；Feedwater distributor box, reallocation header and the steam header are sequentially communicated；Wherein, the feedwater distributor box is connected by the heat-transfer pipe with the reallocation header, and the reallocation header is connected by the heat-transfer pipe with the steam header.The continuous steam generator of nuclear power station provided by the invention, it is different from traditional continuous steam generator, reallocation header is set up in once through steam generator, for alleviating due to the uneven flow resistance problem of non-uniform brought that flows and conduct heat, particularly alleviate under low-power and steam quality inequality problem during Load Regulation, header of reallocating simultaneously is also provided with heat-transfer pipe manhole, the inservice inspection and plugging operation, the design for being easy to heat-transfer pipe improve the stabilization and security of steam generator operation.
Description
Technical field
The present invention relates to nuclear power station steam generator, and in particular to a kind of continuous steam generator of nuclear power station.
Background technology
Widely used steam generator has two kinds in PWR nuclear power plant, and a kind of is that the saturation with steam-water separator is steamed
Vapour generator, one kind are continuous steam generators.For saturation type steam generator, primary Ioops water is in the U connected by tube sheet
Flowed in the tube bank of type pipe composition, steam-water separator and vapor drying plant are housed above tube bank.Saturated steam generator has
Have that heat transfer coefficient is big, the advantages that water storage volume is big, less demanding to feedwater and steam control system, but saturated-steam temperature and
Pressure is relatively low, and corresponding secondary circuit efficiency is low, and steam generator is complicated in addition, and volume is big.Single flow steam generation
What device exported to obtain is typically superheated steam, there is the higher thermal efficiency, and its heat-transfer pipe is straight pipe type, and without steam-water separation
Device, vapor drying plant etc., it is easy to manufacture and assembles.But the secondary circuit water capacity of once through steam generator is small, to water control
The requirement of system is very high.
In recent years, Small reactor had obtained quick development, because once through steam generator has small volume, the thermal efficiency
The advantages that high, is widely adopted.But because Small reactor power is small, Load Regulation requires higher, causes direct-flow steam to be sent out
Flowing and heat exchange in raw device heat-transfer pipe is uneven more obvious.
The content of the invention
The present invention in view of the shortcomings of the prior art, proposes a kind of continuous steam generator of nuclear power station.
The present invention provides a kind of continuous steam generator of nuclear power station, and it includes：Feedwater distributor box, heat-transfer pipe, divide again
With header and steam header；Feedwater distributor box, reallocation header and the steam header are sequentially communicated；Wherein, it is described to give moisture
Connected with case by the heat-transfer pipe with the reallocation header, the reallocation header passes through the heat-transfer pipe and the steam
Header connects.
Preferably, in addition to heat-transfer pipe manhole；The manhole leads to the reallocation header UNICOM, the manhole
Cross flange seal.
Preferably, the feedwater distributor box is configured to the biography evenly distributed to being connected with the reallocation header that feeds water
Heat pipe.
Preferably, the steam header is configured to uniformly mix the steam for entering main steam line.
Compared with prior art, the invention has the advantages that：
1st, the continuous steam generator of nuclear power station provided by the invention, it is different from traditional continuous steam generator,
Reallocation header is set up in once through steam generator, for alleviating because the uneven flow resistance brought that flows and conduct heat is uneven
Even problem, particularly alleviates under low-power and steam quality inequality problem during Load Regulation, while header of reallocating is also set up
Heat-transfer pipe manhole, is easy to the inservice inspection and plugging operation of heat-transfer pipe, and the design improves the steady of steam generator operation
Fixed and security.
Brief description of the drawings
Fig. 1 is the continuous steam generator schematic diagram for the nuclear power station for meeting the preferred embodiment of the present invention.
Wherein：1-reactor coolant entrance；2-reactor coolant runner；3-continuous steam generator；4—
Reactor coolant exports；5-feedwater；6-feedwater distributor box；7-heat-transfer pipe；8-heat-transfer pipe inspection hole；9-reallocation connection
Case；10-steam header；11-main steam.
Embodiment
In order to facilitate the understanding of the purposes, features and advantages of the present invention, it is below in conjunction with the accompanying drawings and specific real
Applying mode, the present invention is further detailed explanation.
As shown in figure 1, the continuous steam generator of nuclear power station it include：Feed water distributor box 6, heat-transfer pipe 7, reallocation connection
Case 9 and steam header 10；Feedwater distributor box 6, reallocation header 9 and the steam header 10 are sequentially communicated；Wherein, the feedwater
Distributor box 6 by the heat-transfer pipe 7 with it is described reallocation header 9 connect, it is described reallocation header 9 by the heat-transfer pipe 7 with
The steam header 10 connects.
The continuous steam generator of nuclear power station also includes heat-transfer pipe manhole 8, is easy to the inservice inspection of heat-transfer pipe and blocks up
Pipe operates.Manhole 8 passes through flange seal with reallocation header 9 UNICOM, manhole 8
The feedwater distributor box 6 is configured to the heat-transfer pipe evenly distributed to being connected with the reallocation header 9 that feeds water
7, feedwater is uniformly entered steam generator heat-transfer pipe.
The steam header 10, steam is set to enter well mixed, pressure stability before main steam line.
Reallocation header 9 in the continuous steam generator of nuclear power station, for alleviating due to the uneven band that flows and conduct heat
The flow resistance problem of non-uniform come, particularly alleviate with steam quality inequality problem during Load Regulation under low-power, this sets
Meter improves the stabilization and security of steam generator operation.
Specifically, as shown in figure 1, the continuous steam generator of the nuclear power station of the present embodiment, main to include feedwater distribution
Case 6, heat-transfer pipe 7, reallocation header 9, heat-transfer pipe inspection hole 8 and steam header 10.Under normal operation, reactor coolant
Hot fluid enters reactor coolant runner 2 from reactor coolant entrance 1, transfers heat to continuous steam generator 3
Afterwards, cold fluid flows out from reactor coolant outlet 4.Feedwater 5 enters feedwater distributor box 6, and feedwater uniformly enters heat-transfer pipe 7,
Be heated after enter reallocation header 9, fluid in header 9 of reallocate be well mixed after enter next section of heat-transfer pipe, if any need to
Will, multiple reallocation headers can be set, to alleviate the flow resistance problem of non-uniform brought due to the inequality that flows and conduct heat, especially
It is to alleviate steam quality inequality problem under low-power and during Load Regulation.Fluid enters steam after final stage heat-transfer pipe
Header 10, enter main steam line after mixed stability.When needing to overhaul heat-transfer pipe or plugging operates, heat-transfer pipe is opened
Manhole 8 carries out inservice inspection and plugging.
Compared with prior art, the present embodiment has the advantages that：
1st, the continuous steam generator for the nuclear power station that the present embodiment provides, with traditional continuous steam generator not
Together, reallocation header is set up in once through steam generator, for alleviating due to the uneven flow resistance brought that flows and conduct heat
Problem of non-uniform, particularly alleviates under low-power and steam quality inequality problem during Load Regulation, while reallocates header also
There is provided heat-transfer pipe manhole, is easy to the inservice inspection and plugging operation of heat-transfer pipe, and the design improves steam generator operation
Stabilization and security.
Each embodiment is described by the way of progressive in this specification, what each embodiment stressed be and other
The difference of embodiment, between 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 using distinct methods to each specific application, but
It is this realization it is not considered that beyond the scope of this invention.
Obviously, those skilled in the art can carry out the spirit of various changes and modification without departing from the present invention to invention
And scope.So, if these modifications and variations of the present invention belong to the claims in the present invention and its equivalent technologies scope it
Interior, then the present invention is also intended to including these changes and modification.
Claims (4)
- A kind of 1. continuous steam generator of nuclear power station, it is characterised in that including：Feed water distributor box, heat-transfer pipe, reallocation connection Case and steam header；Feedwater distributor box, reallocation header and the steam header are sequentially communicated；Wherein, the feedwater distributor box Connected by the heat-transfer pipe with the reallocation header, the reallocation header passes through the heat-transfer pipe and the steam header Connection.
- 2. the continuous steam generator of nuclear power station as claimed in claim 1, it is characterised in that also overhauled including heat-transfer pipe Hole；The manhole passes through flange seal with the reallocation header UNICOM, the manhole.
- 3. the continuous steam generator of nuclear power station as claimed in claim 1, it is characterised in that the feedwater distributor box is through matching somebody with somebody Put so that feedwater is evenly distributed to the heat-transfer pipe connected with the reallocation header.
- 4. the continuous steam generator of nuclear power station as claimed in claim 1, it is characterised in that the steam header is configured Uniformly to be mixed to the steam for entering main steam line.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201711090922.6A CN107631280A (en) | 2017-11-08 | 2017-11-08 | A kind of continuous steam generator of nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201711090922.6A CN107631280A (en) | 2017-11-08 | 2017-11-08 | A kind of continuous steam generator of nuclear power station |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN107631280A true CN107631280A (en) | 2018-01-26 |
Family
ID=61108351
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201711090922.6A Pending CN107631280A (en) | 2017-11-08 | 2017-11-08 | A kind of continuous steam generator of nuclear power station |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN107631280A (en) |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1064504A (en) * | 1964-08-11 | 1967-04-05 | Siemens Ag | A steam generator for a nuclear power plant |
| CN101539287A (en) * | 2009-05-06 | 2009-09-23 | 清华大学 | Steam generator |
| CN202630717U (en) * | 2012-06-21 | 2012-12-26 | 山西阳煤丰喜肥业(集团)有限责任公司 | Steam condenser |
| CN102840596A (en) * | 2011-06-22 | 2012-12-26 | 张志宇 | Water supply heating medium type air preheater |
| CN103954152A (en) * | 2014-05-03 | 2014-07-30 | 张伟 | Inner multi-tube heating exchanger of round tube type header shell tube water storage and production process thereof |
| CN207486768U (en) * | 2017-11-08 | 2018-06-12 | 上海核工程研究设计院有限公司 | A kind of continuous steam generator of nuclear power station |
-
2017
- 2017-11-08 CN CN201711090922.6A patent/CN107631280A/en active Pending
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1064504A (en) * | 1964-08-11 | 1967-04-05 | Siemens Ag | A steam generator for a nuclear power plant |
| CN101539287A (en) * | 2009-05-06 | 2009-09-23 | 清华大学 | Steam generator |
| CN102840596A (en) * | 2011-06-22 | 2012-12-26 | 张志宇 | Water supply heating medium type air preheater |
| CN202630717U (en) * | 2012-06-21 | 2012-12-26 | 山西阳煤丰喜肥业(集团)有限责任公司 | Steam condenser |
| CN103954152A (en) * | 2014-05-03 | 2014-07-30 | 张伟 | Inner multi-tube heating exchanger of round tube type header shell tube water storage and production process thereof |
| CN207486768U (en) * | 2017-11-08 | 2018-06-12 | 上海核工程研究设计院有限公司 | A kind of continuous steam generator of nuclear power station |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN106123086B (en) | Cogeneration units and its peak regulating method with regenerative apparatus | |
| PH12014501575B1 (en) | Steam generating system using geothermal region as heat source, geothermal power generation equipment, and method for generating geothermal power | |
| CN108625911A (en) | A kind of therrmodynamic system promoting thermal power plant unit electricity output regulating power | |
| CN107940538A (en) | A kind of classification hold over system and its peak regulating method for cogeneration units | |
| CN103162282B (en) | Method and system of producing superheated steam | |
| CN207486768U (en) | A kind of continuous steam generator of nuclear power station | |
| CN108458329A (en) | A kind of tower type solar photo-thermal steam generating system adjusted using sloppy heat salt | |
| CN108194156A (en) | A kind of zero output heating system of low pressure (LP) cylinder and method of no cooling steam bypass | |
| CN106556000A (en) | The light thermo-power station oil water heat exchange steam generating system and its method for generation of segmentation reheating | |
| CN104061027B (en) | The high temperature steam-extracting cooling system of Double reheat steam turbine thermodynamic system | |
| CN105570861B (en) | A kind of cascaded utilization of energy apparatus and method for extraction for heat supply system | |
| CN202338891U (en) | Natural circulation waste heat boiler | |
| CN204534505U (en) | Solar energy thermo-power station molten salt heater device | |
| CN104456519B (en) | A kind of new and effective water supply heat back system for double reheat power generation sets | |
| CN206538377U (en) | Coke oven coke oven uprising tube raw coke oven gas waste heat recovery co-generation unit | |
| CN107631280A (en) | A kind of continuous steam generator of nuclear power station | |
| CN208204952U (en) | The tower type solar photo-thermal steam generating system adjusted using sloppy heat salt | |
| CN106642040B (en) | A kind of uniform compact steam generator of assignment of traffic | |
| CN107223194A (en) | A kind of blowdown deaerated feedwater system | |
| CN206449629U (en) | A kind of heat recovery system of utilization demineralized water and condensate | |
| CN108952859A (en) | A kind of system and method for promoting electricity power output regulating power based on steam flow | |
| CN211346477U (en) | Circulating mother liquor heat transfer device | |
| CN207033511U (en) | A kind of coal unit is provided multiple forms of energy to complement each other control system | |
| CN211119308U (en) | Steam-steam conversion system for radioactive site | |
| CN208889338U (en) | A kind of nuclear power plant's nested type reactor coolant pipe |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| CB02 | Change of applicant information | ||
| CB02 | Change of applicant information |
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 Co.,Ltd. |