CN207486768U - 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
- CN207486768U CN207486768U CN201721478763.2U CN201721478763U CN207486768U CN 207486768 U CN207486768 U CN 207486768U CN 201721478763 U CN201721478763 U CN 201721478763U CN 207486768 U CN207486768 U CN 207486768U
- Authority
- CN
- China
- Prior art keywords
- header
- heat
- steam
- transfer pipe
- reallocation
- 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.)
- Active
Links
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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model provides a kind of continuous steam generator of nuclear power station, including：Feed water distributor box, heat-transfer pipe, reallocation header and steam header；The feedwater distributor box, reallocation header and 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 utility model, it is different from traditional continuous steam generator, reallocation header is added 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 unevenness problem during Load Regulation, header of reallocating simultaneously is also provided with heat-transfer pipe manhole, it is operated convenient for the inservice inspection and plugging of heat-transfer pipe, which improves stabilization and the safety of steam generator operation.
Description
Technical field
The utility model is related to nuclear power station steam generators, and in particular to a kind of continuous steam generator of nuclear power station.
Background technology
In PWR nuclear power plant there are two types of widely used steam generators, 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
It is flowed in the tube bank of type pipe composition, steam-water separator and vapor drying plant is housed above tube bank.Saturated steam generator has
Have that heat transfer coefficient is big, the advantages that water storage volume is big, of 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 is typically superheated steam, has the higher thermal efficiency, its heat-transfer pipe is straight pipe type, and without steam-water separation
Device, vapor drying plant etc., convenient for manufacturing and assembling.But the secondary circuit water capacity of once through steam generator is small, to giving water control
The requirement of system is very high.
In recent years, Small reactor had obtained quick development, since once through steam generator has the small, thermal efficiency
The advantages that high, is widely adopted.But since Small reactor power is small, Load Regulation requirement is higher, and direct-flow steam is caused to be sent out
Flowing and heat exchange in raw device heat-transfer pipe is uneven more obvious.
Utility model content
The utility model in view of the deficiencies of the prior art, proposes a kind of continuous steam generator of nuclear power station.
The utility model provides a kind of continuous steam generator of nuclear power station, including：Feed water distributor box, heat-transfer pipe,
Reallocation header and steam header；The feedwater distributor box, reallocation header and steam header are sequentially communicated；Wherein, it is described to give
Water distributor box is connected by the heat-transfer pipe with the reallocation header, the reallocation header by the heat-transfer pipe with it is described
Steam header connects.
Preferably, heat-transfer pipe manhole is further included；The manhole and the reallocation header unicom, the manhole lead to
Cross flange seal.
Preferably, the feedwater distributor box is configured to evenly distribute feedwater to the biography connected with the reallocation header
Heat pipe.
Preferably, the steam header is configured to uniformly mix the steam for entering main steam line.
Compared with prior art, the utility model has the advantages that：
1st, the continuous steam generator of nuclear power station provided by the utility model, with traditional continuous steam generator not
Together, reallocation header is added 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 unevenness problem during Load Regulation, while reallocates header also
There is provided heat-transfer pipe manholes, are operated convenient for the inservice inspection and plugging of heat-transfer pipe, which improves steam generator operation
Stabilization and safety.
Description of the drawings
Fig. 1 is the continuous steam generator schematic diagram for the nuclear power station for meeting the preferred embodiment in the utility model.
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-connection of reallocating
Case；10-steam header；11-main steam.
Specific embodiment
Above-mentioned purpose, feature and advantage to enable the utility model are more obvious understandable, below in conjunction with the accompanying drawings and have
Body embodiment is described in further detail the utility model.
As shown in Figure 1, the continuous steam generator of nuclear power station it include：Feed water distributor box 6, heat-transfer pipe 7, connection of reallocating
Case 9 and steam header 10；The feedwater distributor box 6, reallocation header 9 and steam header 10 are sequentially communicated；Wherein, the feedwater
Distributor box 6 is connected by the heat-transfer pipe 7 with the reallocation header 9, the reallocation header 9 by the heat-transfer pipe 7 with
The steam header 10 connects.
The continuous steam generator of nuclear power station further includes heat-transfer pipe manhole 8, convenient for the inservice inspection of heat-transfer pipe and stifled
Pipe operates.Manhole 8 and 9 unicom of reallocation header, manhole 8 pass through flange seal
The feedwater distributor box 6 is configured to evenly distribute feedwater to the heat-transfer pipe connected with the reallocation header 9
7, feedwater is made to uniformly enter steam generator heat-transfer pipe.
The steam header 10 makes steam be uniformly mixed before entering main steam line, pressure stability.
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 is alleviated with steam quality unevenness problem during Load Regulation under low-power, this sets
Meter improves stabilization and the safety 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 is flowed out from reactor coolant outlet 4.Feedwater 5 enters feedwater distributor box 6, and feedwater uniformly enters heat-transfer pipe 7,
Enter reallocation header 9 after being heated, fluid enters next section of heat-transfer pipe after mixing in reallocation header 9, if any need
Will, multiple reallocation headers can be set, to alleviate the flow resistance problem of non-uniform brought due to the unevenness that flows and conduct heat, especially
It is to alleviate steam quality unevenness problem under low-power and during Load Regulation.Fluid enters steam after final stage heat-transfer pipe
Header 10 enters 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 of nuclear power station provided in this embodiment, with traditional continuous steam generator not
Together, reallocation header is added 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 unevenness problem during Load Regulation, while reallocates header also
There is provided heat-transfer pipe manholes, are operated convenient for the inservice inspection and plugging of heat-transfer pipe, which improves steam generator operation
Stabilization and safety.
Each embodiment is described by the way of progressive in this specification, the highlights of each of the examples are with other
The difference of embodiment, just to refer each other for identical similar portion between each embodiment.For system disclosed in embodiment
For, due to corresponding to the methods disclosed in the examples, 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 the scope of the utility model.
Obviously, it is new without departing from this practicality can to carry out utility model various modification and variations by those skilled in the art
The spirit and scope of type.If in this way, these modifications and variations of the present invention belong to the utility model claims and its
Within the scope of equivalent technologies, then the utility model is also intended to including these modification and variations.
Claims (4)
1. a kind of continuous steam generator of nuclear power station, which is characterized in that including：Feed water distributor box, heat-transfer pipe, connection of reallocating
Case and steam header；The feedwater distributor box, reallocation header and steam header are sequentially communicated；Wherein, the feedwater distributor box
It is 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 described in claim 1, which is characterized in that further include heat-transfer pipe maintenance
Hole；The manhole and the reallocation header unicom, the manhole pass through flange seal.
3. the continuous steam generator of nuclear power station as described in claim 1, which is characterized in that the feedwater distributor box is through matching
It puts with the heat-transfer pipe that evenly distributes to being connected with the reallocation header of feeding water.
4. the continuous steam generator of nuclear power station as described in claim 1, which is characterized 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 |
|---|---|---|---|
| CN201721478763.2U CN207486768U (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 |
|---|---|---|---|
| CN201721478763.2U CN207486768U (en) | 2017-11-08 | 2017-11-08 | A kind of continuous steam generator of nuclear power station |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN207486768U true CN207486768U (en) | 2018-06-12 |
Family
ID=62475811
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201721478763.2U Active CN207486768U (en) | 2017-11-08 | 2017-11-08 | A kind of continuous steam generator of nuclear power station |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN207486768U (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107631280A (en) * | 2017-11-08 | 2018-01-26 | 上海核工程研究设计院有限公司 | A kind of continuous steam generator of nuclear power station |
| CN112652414A (en) * | 2020-12-16 | 2021-04-13 | 中国人民解放军海军工程大学 | C-shaped tube bundle of reactor steam generator |
-
2017
- 2017-11-08 CN CN201721478763.2U patent/CN207486768U/en active Active
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107631280A (en) * | 2017-11-08 | 2018-01-26 | 上海核工程研究设计院有限公司 | A kind of continuous steam generator of nuclear power station |
| CN112652414A (en) * | 2020-12-16 | 2021-04-13 | 中国人民解放军海军工程大学 | C-shaped tube bundle of reactor steam generator |
| CN112652414B (en) * | 2020-12-16 | 2022-11-01 | 中国人民解放军海军工程大学 | C-shaped tube bundle of reactor steam generator |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| PH12014501575B1 (en) | Steam generating system using geothermal region as heat source, geothermal power generation equipment, and method for generating geothermal power | |
| CN204298062U (en) | A kind of sulfuric acid low temperature bootstrap system | |
| 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 | |
| CN202338891U (en) | Natural circulation waste heat boiler | |
| CN203731528U (en) | Steam heating system utilizing off-peak electricity as energy | |
| CN206019378U (en) | A kind of vapor-water heat exchanger with hydrophobic cooling section | |
| CN106556000A (en) | The light thermo-power station oil water heat exchange steam generating system and its method for generation of segmentation reheating | |
| CN206538377U (en) | Coke oven coke oven uprising tube raw coke oven gas waste heat recovery co-generation unit | |
| CN208204952U (en) | The tower type solar photo-thermal steam generating system adjusted using sloppy heat salt | |
| CN203429426U (en) | Condensed water recovery system for dyeing and finishing process | |
| CN107223194A (en) | A kind of blowdown deaerated feedwater system | |
| CN107631280A (en) | A kind of continuous steam generator of nuclear power station | |
| CN206449629U (en) | A kind of heat recovery system of utilization demineralized water and condensate | |
| CN211346477U (en) | Circulating mother liquor heat transfer device | |
| CN104406441A (en) | Heat exchanging U-shaped pipe with spiral flow mixing function | |
| CN204268942U (en) | A kind of heat exchange U-shaped pipe with spiral mixed flow function | |
| CN208205435U (en) | Boiler low pressure drum | |
| CN209341876U (en) | A kind of exhaust steam residual heat recycling condenser | |
| CN217928725U (en) | Boiler hot water recycling device | |
| CN105443508A (en) | Efficient hydraulic apparatus cooling device | |
| CN207247959U (en) | Overheat of steaming Integral vertical thin tubesheet waste heat recovery plant | |
| CN202532934U (en) | Heat exchanging heater | |
| CN207831988U (en) | A kind of air preheater | |
| CN206944771U (en) | A kind of heater |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| 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 Co.,Ltd. |