CN203501137U - Multi-stage spherical water supply pipe capable of effectively relieving thermal stratification phenomenon for steam generator - Google Patents
Multi-stage spherical water supply pipe capable of effectively relieving thermal stratification phenomenon for steam generator Download PDFInfo
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- CN203501137U CN203501137U CN201320434972.2U CN201320434972U CN203501137U CN 203501137 U CN203501137 U CN 203501137U CN 201320434972 U CN201320434972 U CN 201320434972U CN 203501137 U CN203501137 U CN 203501137U
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Abstract
The utility model relates to a multi-stage spherical water supply pipe capable of effectively relieving a thermal stratification phenomenon for a steam generator. The multi-stage spherical water supply pipe is arranged between the secondary cooling water inlet of the steam generator and a water supply ring of the steam generator. The multi-stage spherical water supply pipe is characterized by comprising a plurality of spherical pipe segments which are connected integrally, wherein the small-pipe-diameter ends of the spherical pipe segments are connected in sequence; one end of the multi-stage spherical water supply pipe is communicated with the cooling water inlet, and the other end of the multi-stage spherical water supply pipe is communicated with the water supply ring. According to the multi-stage spherical water supply pipe for the steam generator disclosed by the utility model, a flow channel is reduced or expanded, so that local flow speed in the pipe is increased; moreover, the flow direction in a local structure is modified, so that blending of cold and hot fluids is reinforced, and the thermal stratification phenomenon in a water supply ring pipe under a low-power running condition is relieved.
Description
Technical field
The present invention relates to pressurized-water reactor nuclear power plant technical field, be specifically related to a kind of multistage spherical steam generator feed pipe that can effectively extenuate thermal stratification.
Background technology
PWR nuclear power plant (starts and shutdown process) under low power run operating mode, before steam generator puts into operation, high-temperature water heated feed water entrance horizontal segment in steam generator and the residual feedwater of elbow, reach unanimity temperature in residual feed temperature and steam generator secondary side.After steam generator puts into operation, the feedwater that temperature is lower flows into feedwater elbow and feed pipe horizontal segment by feed pipe.In feedwater endless tube, original residual feed temperature is relatively high, in the situation that feedwater low discharge injects, because cold and hot fluid lacks fully, mixes, and in feedwater endless tube, residual feed temperature is high, and density is little, occupies the top of feedwater endless tube; The temperature of feedwater is low, and density is large, occupies the bottom of feedwater endless tube.In the case, between cold water layer and hot water layer, just formed cold fluid and hot fluid interface.In engineering, above-mentioned phenomenon is called to steam generator feedwater endless tube thermal stratification.
The thermal stratification of steam generator feedwater endless tube inner fluid makes feed pipe inner fluid top higher than the temperature of bottom, in feedwater endless tube cross section, produces additional overall crooked thermal stress; In addition, thermally stratified layer produces significant hot line vibration on cold fluid and hot fluid interface while occurring, and this oscillation action, in inner-walls of duct face, causes localized heat stress.After the stack of two kinds of stress, can produce the harm such as pipeline cracking, displacement, heat fatigue, bending and support unit load is excessive, in service life that may restriction conduit, steam generator be carried out to its function composing and necessarily threaten.
Summary of the invention
The technical problem that will solve of the present invention is to provide a kind of by special feed pipe structure, strengthen the degree of mixing of steam generator feed-water intake cold fluid and hot fluid under low power run operating mode, extenuate the multistage spherical steam generator feed pipe of the thermal stratification in feedwater endless tube.
In order to solve the problems of the technologies described above, technical scheme of the present invention is, a kind of multistage spherical steam generator feed pipe that can effectively extenuate thermal stratification, be arranged on described steam generator secondary cooling water entrance and steam generator between water ring, it is characterized in that: comprise several bulb tube pipeline sections that integral type connects, the pipe with small pipe diameter end of described several bulb tube pipeline sections connects successively; One end of described multistage spherical feed pipe is communicated with described cooling water inlet, and the other end is communicated with to water ring with described.
The pipeline maximum inner diameter of each bulb tube pipeline section is 1:0.85 with the ratio of minimum diameter.
Beneficial effect of the present invention:
Multistage spherical steam generator feed pipe contracting of the present invention, expansion runner, improved local velocity in pipe, and changed partial structurtes flow direction, strengthens cold fluid and hot fluid and mix, and extenuated the thermal stratification feeding water in endless tube under low power run operating mode.
Accompanying drawing explanation
Fig. 1 is pressurized water reactor nuclear power station steam generator schematic diagram;
Fig. 2 is a kind of stairstepping steam generator feed pipe schematic diagram that can effectively extenuate thermal stratification of the present invention.
In figure: 1-steam generator, 101-steam generator shell, 102-steam-water separator, 103-drier, 104-steam (vapor) outlet, 105-is to water ring, 106-secondary cooling water entrance, 107-tube bank, 108-primary cooling water enters chamber, 109-primary cooling water output chamber, 110-primary cooling water entrance, the outlet of 111-primary cooling water, 2-case side is taken over, the multistage spherical feed pipe of 3-, the spherical convergent pipeline section of the 301-first order, the spherical flaring pipeline section in the 302-second level, the spherical convergent pipeline section in the 303-second level, the spherical flaring pipeline section of the 304-third level, the spherical convergent pipeline section of the 305-third level, the spherical flaring pipeline section of the 306-fourth stage, the 4-threeway of feeding water, 5-J shape pipe.
The specific embodiment
Below in conjunction with drawings and Examples, the present invention is described further.
In Fig. 1, show a kind of example of steam generator, this steam generator 1 comprises tube bank 107, and this tube bank 107 is arranged on the bottom of steam generator shell 101 inner sides, and is immersed in secondary cooling water.Tube bank 107 is made into inverted U-shaped, one end thereof is connected on primary cooling water inlet plenum 108 with fluid mode of communicating, and another one end is connected on primary cooling water output chamber 109 with fluid mode of communicating, described primary cooling water enters chamber 108 and is communicated with reactor heat pipe section by primary cooling water entrance 110, and described primary cooling water output chamber 109 exports 111 by primary cooling water and is communicated with reactor cold leg.A plurality of centrifugal steam purifiers 102 are arranged on the top of steam generator shell 101 inner sides, are positioned at the top of tube bank 107, are especially arranged in the surface of the secondary cooling water that is contained in steam generator shell 101.A drier 103 is arranged on the top of steam-water separator 102, has applied waveform carbonated drink separating plate of the present invention on this drier 103.
The primary cooling water of high temperature is fed into primary cooling water and enters in chamber 108, and this primary cooling water is heated by reactor core in nuclear reactor.Primary cooling water enters chamber 108 from primary cooling water and flows to primary cooling water output chamber 109 by restraining 107.On the contrary, secondary cooling water is by secondary cooling water entrance 106 and be imported into the surrounding of the interior tube bank 107 of steam generator shell 101 to water ring 105, and wherein, secondary cooling water entrance 106 is arranged on steam generator shell 101.At primary cooling water, flow through in the process of tube bank 107, by carrying out heat exchange with primary cooling water, the secondary cooling water being contained in steam generator shell 101 is heated.Thus, by secondary cooling water, produce steam.
In Fig. 2, can find out that the case side adapter 2 that is arranged on described secondary cooling water entrance 106 is connected by multistage spherical feed pipe 3 to water ring 105 with steam generator is interior, described multistage spherical feed pipe 3 comprises several bulb tube pipeline sections that integral type connects, and the pipe with small pipe diameter end of described several bulb tube pipeline sections connects successively; One end of described multistage spherical feed pipe 3 is communicated with described cooling water inlet 106, and the other end is communicated with the described water ring 105 of giving; Should be to being provided with several reversed J shape pipes on water ring 105;
The pipeline maximum inner diameter of each bulb tube pipeline section is 1:0.85 with the ratio of minimum diameter;
Particularly, the feed pipe that is positioned at the level of steam generator shell 101 inner sides is designed to multi-stage ball structure, be followed successively by from steam generator shell 101 to the spherical convergent pipeline section 301 of the first order, the spherical flaring pipeline section 302 in the second level, the spherical convergent pipeline section 303 in the second level, the spherical flaring pipeline section 304 of the third level, the spherical convergent pipeline section 305 of the third level, the spherical flaring pipeline section 306 of the fourth stage to water ring 105, the spherical convergent pipeline section 301 of the first order is taken over 2 with case side and is connected, and the spherical flaring pipeline section 306 of the fourth stage is connected with feedwater threeway 4.Such structure relies on contracting, expands runner, has improved velocity in pipes, strengthens cold fluid and hot fluid and mixes, and has extenuated the thermal stratification feeding water in endless tube under low power run operating mode.
Claims (2)
1. the multistage spherical steam generator feed pipe that can effectively extenuate thermal stratification, be arranged on described steam generator secondary cooling water entrance and steam generator between water ring, it is characterized in that: comprise several bulb tube pipeline sections that integral type connects, the pipe with small pipe diameter end of described several bulb tube pipeline sections connects successively; One end of described multistage spherical feed pipe is communicated with described cooling water inlet, and the other end is communicated with to water ring with described.
2. according to the multistage spherical steam generator feed pipe that can effectively extenuate thermal stratification claimed in claim 1, it is characterized in that: the pipeline maximum inner diameter of each bulb tube pipeline section is 1:0.85 with the ratio of minimum diameter.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320434972.2U CN203501137U (en) | 2013-07-22 | 2013-07-22 | Multi-stage spherical water supply pipe capable of effectively relieving thermal stratification phenomenon for steam generator |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320434972.2U CN203501137U (en) | 2013-07-22 | 2013-07-22 | Multi-stage spherical water supply pipe capable of effectively relieving thermal stratification phenomenon for steam generator |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN203501137U true CN203501137U (en) | 2014-03-26 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201320434972.2U Expired - Lifetime CN203501137U (en) | 2013-07-22 | 2013-07-22 | Multi-stage spherical water supply pipe capable of effectively relieving thermal stratification phenomenon for steam generator |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN203501137U (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105841134A (en) * | 2016-05-19 | 2016-08-10 | 上海核工程研究设计院 | Steam generator steam-water separation device of small reactor |
| CN109798510A (en) * | 2019-01-11 | 2019-05-24 | 中广核工程有限公司 | A kind of main feed water pipe device for pressurized water reactor nuclear power station steam generator |
-
2013
- 2013-07-22 CN CN201320434972.2U patent/CN203501137U/en not_active Expired - Lifetime
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105841134A (en) * | 2016-05-19 | 2016-08-10 | 上海核工程研究设计院 | Steam generator steam-water separation device of small reactor |
| CN109798510A (en) * | 2019-01-11 | 2019-05-24 | 中广核工程有限公司 | A kind of main feed water pipe device for pressurized water reactor nuclear power station steam generator |
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Granted publication date: 20140326 |
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