CN111140830A - Vertical steam generator of pressurized water reactor nuclear power station and loose part trapping device thereof - Google Patents
Vertical steam generator of pressurized water reactor nuclear power station and loose part trapping device thereof Download PDFInfo
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- CN111140830A CN111140830A CN201911171908.8A CN201911171908A CN111140830A CN 111140830 A CN111140830 A CN 111140830A CN 201911171908 A CN201911171908 A CN 201911171908A CN 111140830 A CN111140830 A CN 111140830A
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- top plate
- steam generator
- water
- nuclear power
- steam
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/16—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour
- F22B1/162—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour in combination with a nuclear installation
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/22—Drums; Headers; Accessories therefor
- F22B37/225—Arrangements on drums or collectors for fixing tubes or for connecting collectors to each other
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/26—Steam-separating arrangements
- F22B37/268—Steam-separating arrangements specially adapted for steam generators of nuclear power plants
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/48—Devices for removing water, salt, or sludge from boilers; Arrangements of cleaning apparatus in boilers; Combinations thereof with boilers
- F22B37/483—Devices for removing water, salt, or sludge from boilers; Arrangements of cleaning apparatus in boilers; Combinations thereof with boilers specially adapted for nuclear steam generators
Abstract
The invention discloses a loose part trapping device for a steam generator of a pressurized water reactor nuclear power station, which is arranged on a top plate of a sludge collector, wherein a plurality of steam-water separator ascending cylinders are arranged on the top plate, trapping enclosing plates welded on the top plate are arranged between adjacent peripheral steam-water separator ascending cylinders, two ends of each trapping enclosing plate are respectively welded on the outer surfaces of the separator ascending cylinders, and one end of each trapping enclosing plate, which is far away from the top plate, is provided with a folded plate extending towards the center of the top plate. In addition, the invention also discloses a vertical steam generator of a pressurized water reactor nuclear power station, which adopts the loose part trapping device.
Description
Technical Field
The invention belongs to the technical field of nuclear power, and particularly relates to a vertical steam generator of a pressurized water reactor nuclear power station and a loose part trapping device thereof.
Background
The steam generator is a junction of a first loop and a second loop of the nuclear power station, and is used for transferring heat generated by the reactor to a secondary side to generate steam and transmitting the steam to a steam turbine to drive a generator to generate electricity.
The primary side pressure boundary of the steam generator comprises a lower end enclosure, a tube plate and a tube bundle, wherein the lower end enclosure is divided into an inlet water chamber and an outlet water chamber by a partition plate, and a reactor coolant enters through an inlet connecting pipe on the lower end enclosure of the steam generator, flows through a U-shaped heat transfer tube and then flows out through an outlet connecting pipe on the lower end enclosure.
The secondary side pressure boundary of the steam generator comprises a tube plate, a lower cylinder, a conical cylinder, an upper cylinder and an upper end enclosure. The feed water enters the steam generator through the feed water connecting pipe, enters the feed water ring pipe after passing through the feed water connecting pipe, is sprayed out through a nozzle on the feed water ring pipe, is mixed with the saturated water separated from the steam-water separation device, and then flows into an annular descending channel between the tube bundle sleeve and the shell to reach the secondary side surface of the tube plate. The water enters the tube bundle through a gap between the lower end of the sleeve and the secondary side surface of the tube plate, and when the water rises through the tube bundle, part of the water is heated and changed into steam to form a steam-water mixture. After the steam-water mixture flows out of the top of the tube bundle, the steam-water mixture enters a steam-water separator for coarse separation, then a dryer for fine separation, and finally dry saturated steam is output.
The steam generator tubes form a pressure-bearing boundary between the primary and secondary sides and serve to isolate the radioactive material of the primary coolant of the reactor. The heat transfer pipe is a seamless steel pipe with the wall thickness of about 1mm, but the integrity of the heat transfer pipe must be ensured so as to prevent the heat transfer pipe from cracking and leaking to cause serious pollution to the two-loop system.
It is well known that loose parts entering the steam generator through the feedwater system may cause damage to the heat transfer tubes. The loose parts are different in size and enter the steam generator through a J-shaped pipe or a spray header on the water supply ring pipe. Under the action of the fluid, the loose part enters the descending channel and contacts with the heat transfer pipe through the opening between the bottom of the tube bundle sleeve and the tube plate to form dents on the surface of the heat transfer pipe or continuous impact traces. The loose part smaller than the heat transfer pipe gap can enter the tube bundle and stay in the relative stagnation area of the fluid, and the staying loose part generates high-frequency small-amplitude motion under the micro acting force of the fluid to generate micro-motion abrasion on the heat transfer pipe, so that the pipe wall is thinned. Impact pitting and fretting wear can, in severe cases, cause heat transfer tube rupture, leading to unplanned nuclear power plant shutdown requiring costly repairs. Therefore, a device for preventing foreign loose parts from entering the steam generator and preventing the entered loose parts from migrating to the tube bundle is necessary.
At present, the existing device for preventing foreign matters from entering the steam generator mainly adopts a screening mode, namely, a J-shaped pipe with a small diameter or an I-shaped pipe with a spraying hole is arranged on a water supply ring pipe. When the size of the foreign matters is larger than the inner diameter of the J-shaped pipe or the diameter of the spray hole, the foreign matters can be intercepted in the water supply pipeline. However, foreign matter having a size smaller than the inside diameter of the J-tube or the diameter of the shower hole may still pass through and into the steam generator, and these loose parts, such as metal bars, welding rods, metal sheets, may still pose a threat to the integrity of the heat transfer tube.
In view of the above, there is a need for a reliable vertical steam generator for a pressurized water reactor nuclear power plant and a loose component capture device thereof, which can collect loose components entering the steam generator through a water supply loop during commissioning and operation of the nuclear power plant, prevent the loose components from entering a tube bundle region, and improve the working environment of heat transfer tubes.
Disclosure of Invention
The invention aims to: the defects in the prior art are overcome, and the reliable vertical steam generator of the pressurized water reactor nuclear power station and the loose part trapping device thereof are provided, so that the loose parts entering the steam generator through the water supply ring pipe can be collected in the debugging and running processes of the nuclear power station, the loose parts are prevented from entering the pipe bundle area, and the working environment of a heat transfer pipe is improved.
In order to achieve the purpose, the invention provides a loose part trapping device for a steam generator of a pressurized water reactor nuclear power station, which is arranged on a top plate of a sludge collector, wherein a plurality of steam-water separator ascending cylinders are arranged on the top plate, trapping enclosing plates fixedly connected to the top plate are arranged between adjacent peripheral steam-water separator ascending cylinders, two ends of each trapping enclosing plate are respectively and fixedly connected to the outer surface of each separator ascending cylinder, and one end of each trapping enclosing plate, which is far away from the top plate, is provided with a folded plate extending towards the center of the top plate.
As an improvement of the loose part trapping device for the steam generator of the pressurized water reactor nuclear power station, the trapping enclosing plate is welded on the top plate, and two ends of the trapping enclosing plate are respectively welded on the outer surface of the ascending cylinder of the separator.
As an improvement of the loose part trapping device for the steam generator of the pressurized water reactor nuclear power station, the folded plate and the trapping enclosing plate are in arc transition, and the transition radius is 5-25 mm.
As an improvement of the loose part trapping device for the steam generator of the pressurized water reactor nuclear power station, the included angle between the folded plate and the trapping enclosing plate is 30-150 degrees.
As an improvement of the loose part trapping device for the steam generator of the pressurized water reactor nuclear power station, the top plate is provided with a central area small hole and a peripheral circumferential area small hole, and the trapping surrounding plate is positioned on the inner side of the peripheral circumferential area small hole.
As an improvement of the loose part trapping device for the steam generator of the pressurized water reactor nuclear power station, the radius formed by the projection of the trapping coaming and the folded plate on the top plate is larger than the radius formed by the projection of a water supply circular pipe spray pipe or a J-shaped pipe arranged on the steam generator on the top plate.
In order to achieve the purpose, the invention also provides a vertical steam generator of a pressurized water reactor nuclear power station, which comprises an upper disc-shaped seal head, an upper barrel, a conical barrel, a lower barrel, a tube plate and a lower seal head, wherein the tube plate is provided with a plurality of tube holes, two ends of the tube bundle of the inverted U-shaped tube are inserted into the tube holes and are mechanically connected with the tube plate to form a tube bundle comprising a plurality of inverted U-shaped tubes, the periphery of the tube bundle is provided with a sleeve, a sleeve top plate is arranged above the tube bundle, the sleeve, the lower barrel, the sleeve top plate is provided with a sludge collector, the top plate of the sludge collector is provided with a loose part collecting device and a plurality of steam-water separator ascending cylinders, collecting enclosing plates fixedly connected to the top plate are arranged between the adjacent peripheral steam-water separator ascending cylinders, two ends of each collecting enclosing plate are fixedly connected to the outer surface of each separator ascending cylinder respectively, and one end, far away from the top plate, of each collecting enclosing plate is provided with a folded plate extending towards the center of the top plate.
As an improvement of the vertical steam generator of the pressurized water reactor nuclear power station, the collecting coaming is welded on the top plate, and two ends of the collecting coaming are respectively welded on the outer surface of the rising barrel of the separator.
The vertical steam generator of the pressurized water reactor nuclear power station is improved in that the top plate of the sleeve is provided with an opening, the opening is connected with a group of rising cylinders of steam-water separators in the same number, the inside of each rising cylinder is provided with a rotary vane, a steam-water two-phase mixture generated by boiling in the sleeve flows through the opening of the top plate of the sleeve and enters the rising cylinder, the steam-water generates spiral centrifugal motion under the action of the rotary vane, and the steam-water is separated under the action of centrifugal force.
The invention relates to an improvement of a vertical steam generator of a pressurized water reactor nuclear power station, which is characterized in that separated water enters a water pool arranged above a top plate of a sleeve again, wet steam separated by a primary separator continuously flows upwards and is separated and dried again by a dryer, and steam separated secondarily flows out of the steam generator through a flow restrictor arranged in the center of an upper disc-shaped seal head.
As an improvement of the vertical steam generator of the pressurized water reactor nuclear power station, the recirculated water separated from the steam-water separator and the water supply ring are mixed and enter the annular channel, the fluid flow speed of the annular channel is high, the fluid flow speed of the central area above the top plate of the sleeve is low, and the pressure difference exists between the central area and the peripheral circumferential area of the top plate.
As an improvement of the vertical steam generator of the pressurized water reactor nuclear power station, a water supply pipe is arranged above the sludge collector, is in an approximately circular structural form, has a diameter smaller than that of a sleeve top plate, and is horizontally arranged in the steam generator.
As an improvement of the vertical steam generator of the pressurized water reactor nuclear power station, the folded plate and the trapping enclosing plate are in arc transition, and the transition radius is 5-25 mm.
As an improvement of the vertical steam generator of the pressurized water reactor nuclear power station, the included angle between the folded plate and the trapping enclosing plate is 30-150 degrees.
As an improvement of the vertical steam generator of the pressurized water reactor nuclear power station, the top plate is provided with a central area small hole and a peripheral circumferential area small hole, and the collecting enclosing plate is positioned on the inner side of the peripheral circumferential area small hole.
As an improvement of the vertical steam generator of the pressurized water reactor nuclear power station, the radius formed by the projection of the collecting coaming and the folded plate on the top plate is larger than the radius formed by the projection of a water supply circular pipe spray pipe or a J-shaped pipe arranged on the steam generator on the top plate.
Compared with the prior art, the vertical steam generator of the pressurized water reactor nuclear power station and the loose part trapping device thereof have the advantages that: during a change, the secondary side of the steam generator will be emptied of water and the shroud and flaps provided can trap loose parts of the top plate from migrating into the annular channel under the influence of fluid. When the steam generator is emptied, water in the enclosing area of the enclosing plate and the folded plate can be emptied through the small hole in the central area of the top plate of the sludge collector, and the in-service work of the top plate of the sludge collector cannot be influenced. When water is injected into the empty steam generator, the arranged coaming and the folded plate can capture loose parts on the top plate so as to prevent the loose parts from migrating into the annular channel under the action of fluid, and therefore, the reliable operation of the vertical steam generator of the pressurized water reactor nuclear power station can be realized.
Drawings
The vertical steam generator of a pressurized water reactor nuclear power plant, the loose part trapping device thereof and the beneficial technical effects thereof will be described in detail with reference to the accompanying drawings and the detailed description.
FIG. 1 is a schematic structural view of a vertical steam generator of a pressurized water reactor nuclear power plant according to the present invention.
Fig. 2 is a schematic structural view of the sludge collector in fig. 1.
Fig. 3 is a schematic structural view of three different embodiments of the loose part trapping device in fig. 2.
Detailed Description
In order to make the objects, technical solutions and technical effects of the present invention more clear, the present invention will be described in further detail with reference to specific embodiments. It should be understood that the detailed description and specific examples, while indicating the preferred embodiment of the invention, are intended for purposes of illustration only and are not intended to limit the scope of the invention.
Referring to fig. 1, a schematic diagram of a vertical steam generator 10 of a pressurized water reactor nuclear power plant according to the present invention is shown. In the illustrated embodiment, the steam generator 10 is a vertical shell and tube heat exchanger that includes an upper dished head 12, an upper barrel 13, a conical barrel 14, a lower barrel 15, a tube sheet 16, and a lower head 17.
The tube plate 16 is provided with thousands of tube holes 18, and the two ends of the inverted U-shaped tube bundle 11 are inserted into the tube holes 18 and mechanically connected to the tube plate 16. The tube bundle 11 forms a heat transfer surface for heat exchange with a primary circuit, thereby transferring heat of a primary circuit coolant to a secondary side, and boiling water on the secondary side to generate steam.
The partition plate 19 divides the interior of the lower head 17 into two chambers 20 and 21, forming a pipe header of the inverted U-shaped pipe. The chamber 20 is a primary fluid inlet chamber which is connected to an inlet connection 22. The chamber 21 is a primary side fluid outlet chamber which is connected to an outlet connection 23. Thus, the reactor primary coolant enters the chamber 20 from the inlet connection 22, flows through the tubes of the inverted U-shaped tube bundle 11, enters the chamber 21, and exits the steam generator through the outlet connection 23.
The tube bundle 11 is provided with a sleeve 30 at the periphery, and the sleeve 30 forms an annular channel 31 with the lower cylinder 15 and the conical cylinder 14. The top of the sleeve 30 is provided with a sludge collector 50, the sludge collector 50 is provided with a group of open pores 40, the open pores 40 are connected with a group of steam-water separator ascending cylinders 41 with the same number, and the rotating blades 42 are arranged inside the ascending cylinders 41. The steam-water two-phase mixture generated by boiling in the sleeve 30 flows through the opening 40 on the sleeve top cover 32 and enters the ascending cylinder 41, the steam-water generates spiral centrifugal motion under the action of the rotary vane 42, and the steam-water is separated under the action of centrifugal force. The separated water re-enters the basin above the sludge collector 50. The wet steam separated by the primary separator continues to flow upward and passes through the dryer 60 for re-separation and drying, and the steam after secondary separation flows out of the steam generator through the flow restrictor 90 arranged in the center of the upper disc-shaped end enclosure 12.
The feed pipe 70 includes a feed annulus assembly 71 and a thermal sleeve assembly 72, the feed annulus assembly 71 being positioned above the thermal sleeve assembly 71 to mitigate the effects of thermal stratification of fluids within the pipe. The feed loop assembly 71 is in the form of an approximately circular structure and is arranged horizontally inside the steam generator 10. The feed water nozzle 73 is welded to the feed water loop assembly 71 and the number of openings 40 and nozzles 73 is determined by calculation based on the flow rate of the main feed water. The nozzle 73 is provided with a plurality of spray holes, and the diameter of each spray hole is 5-9 mm.
During normal operation and transient conditions of normal operation of the steam generator 10, the water level within the steam generator 10 needs to be guaranteed to submerge the feedwater outlet. The steam generator 10 main feed water enters the flow channels 71a in the feed water loop assembly 71 from the flow channels 72a in the hot tube assembly, flows through the flow channels 73a inside the nozzle into the interior of the steam generator 10. Meanwhile, since the diameter of the opening of the nozzle is small, foreign matters entering the feed water can be intercepted by the opening, and foreign matters larger than the inner diameter of the opening of the nozzle cannot enter the inside of the steam generator 10. The main feed water entering the steam generator through the feed water ring is mixed with the recirculating water from the separator and dryer, and enters the annular channel 31, then enters the tube bundle 11 through the opening 33 in the bottom of the sleeve 30, and is heated and boiled to produce steam.
Fig. 2 is a schematic structural diagram of the sludge collector 50. The ceiling 51 of the sludge collector 50 is provided with a plurality of central zone apertures 51a, peripheral zone apertures 51b, and a plurality of steam trap risers 41. The recirculating water separated from the steam-water separator enters the outer space of the steam-water separator riser 41, and most of the recirculating water is mixed with the feed water from the feed water ring 70 and enters the annular passage 31. The annular passage 31 has a greater fluid flow velocity and a slower fluid flow velocity over the top plate of the sleeve, with a pressure differential between the central region 51a and the peripheral circumferential region 51b of the top plate 51. The presence of the above-mentioned pressure differential causes a portion of the recirculating water to enter the sludge collector 50 through the apertures in the central region 51a of the roof and to exit through the apertures in the peripheral circumferential region 51 b. Inside the mud sediment collector 50, the recirculating water is radial from the center and flows along the direction that the radius is constantly grow, and fluid velocity reduces gradually for the mud sediment granule of suspension in the recirculating water deposits on the inside surface of mud sediment collector 50, accomplishes the deposit of mud sediment through passive mode.
The collecting coamings 80 are arranged between the adjacent peripheral steam-water separator ascending cylinders 41, the collecting coamings 80 are welded on the top plate 51, and the two ends of the collecting coamings 80 are welded on the outer surfaces of the separator ascending cylinders 41 (other fixed connection modes such as threaded connection or riveting can also be adopted). With the arrangement, the steam-water separator ascending barrel 41 and the collecting enclosing plate 80 on the periphery of the steam generator jointly enclose the outer periphery of the sludge collector top plate 51. The end of the enclosing plate 80 far away from the top plate 51 is provided with a folded plate 81 facing the center of the top cover of the sludge collector 50, and the included angle between the folded plate 81 and the enclosing plate 80 can be 90 degrees +/-60 degrees (30-150 degrees). In other embodiments of the present invention, an arc transition may be provided between the folded plate 81 and the enclosing plate 80, and the transition radius is 5-25 mm.
Fig. 3 is a schematic structural view of the loose part trapping device. The loose part catching device is set up on the top plate of the sludge collector 50 and comprises a coaming 80 and a flap 81 connected thereto, the flap 81 extending towards the center of the top plate 51 of the sludge collector 50. The shroud 80 is located inside the aperture of the peripheral region 51b of the top plate 51 of the sludge collector 50, and therefore the provision of the shroud 80 does not affect the pressure differential between the central region 51a and the peripheral region 51b of the top plate 51, and does not affect the normal operating function of the sludge collector.
In combination with the above description of the specific embodiment of the vertical steam generator of a pressurized water reactor nuclear power plant and the loose part trapping device thereof according to the present invention, it can be seen that the present invention has the following advantages over the prior art:
the radius formed by the projection of the coaming 80 and the folded plate 81 of the loose part trapping device on the top plate 51 is larger than the radius formed by the projection of the spray pipe or the J-shaped pipe of the water supply ring pipe on the top plate 51. Due to the relatively low velocity of the fluid in the center of the basin above the sludge collector 50, foreign matter, such as metal strips, welding rods, metal sheets, which are smaller in size than the inside diameter of the J-tube or the diameter of the spray holes, enter the steam generator and settle on the top plate 51 or are caught by the shroud 80 and the flap 81 before migrating to the annular channel 31, or under the action of gravity.
During a change, the steam generator secondary side water will be drained and the shroud 80 and flaps 81 provided to trap loose parts of the top panel 51 from migrating under the fluid into the annular channel 31. When the steam generator is emptied, the water in the area enclosed by the shroud 80 and the flap 81 can be emptied through the small hole in the central area 51a of the top plate 51 of the sludge collector 50 without affecting the in-service operation of the top plate 51 of the sludge collector 50. The provision of the shroud 80 and flap 81 allows loose parts of the top panel 51 to be captured from fluid migration into the annular channel 31 during filling of an empty steam generator.
The present invention can be modified and adapted appropriately from the above-described embodiments, according to the principles described above. Therefore, the present invention is not limited to the specific embodiments disclosed and described above, and some modifications and variations of the present invention should fall within the scope of the claims of the present invention. Furthermore, although specific terms are employed herein, they are used in a generic and descriptive sense only and not for purposes of limitation.
Claims (16)
1. The utility model provides a pressurized water reactor nuclear power station steam generator is with not hard up part entrapment device, sets up on the roof of mud sediment collector, is equipped with a plurality of catch water separator and rises a section of thick bamboo on the roof, its characterized in that lies in and all is equipped with the entrapment bounding wall of rigid coupling on the roof between the adjacent catch water separator that is peripheral rises a section of thick bamboo, and the both ends of every entrapment bounding wall rigid coupling is on the surface of a separator rises a section of thick bamboo respectively, and the one end that the roof was kept away from to the entrapment bounding wall is equipped with the folded.
2. The loose member capturing device according to claim 1, wherein the capturing collar is welded to the top plate, and both ends of the capturing collar are welded to an outer surface of the separator ascending tube, respectively.
3. The loose part trapping device according to claim 1, wherein the folded plate and the trapping enclosure are in arc transition with a transition radius of 5-25 mm.
4. A loose part trapping device according to claim 1, wherein the angle between the flap and the trapping enclosure is between 30 ° and 150 °.
5. The loose component capture device of claim 1, wherein the top plate is provided with a central zone aperture and a peripheral circumferential zone aperture, and the capture collar is located inboard of the peripheral circumferential zone aperture.
6. The loose parts trapping device according to claim 1, wherein the trapping enclosure and the folded plate are projected on the top plate to form a radius larger than that of a spray pipe or a J-shaped pipe of a water supply ring pipe arranged in the steam generator.
7. A vertical steam generator of a pressurized water reactor nuclear power station comprises an upper disc-shaped seal head, an upper barrel, a conical barrel, a lower barrel, a tube plate and a lower seal head, wherein a plurality of tube holes are formed in the tube plate, two ends of an inverted U-shaped tube bundle are inserted into the tube holes and are mechanically connected with the tube plate to form the tube bundle comprising a plurality of inverted U-shaped tubes, sleeves are arranged on the periphery of the tube bundle, sleeve top plates are arranged above the sleeves, the lower barrel and the conical barrel form an annular channel, the novel sludge collecting device is characterized in that a sludge collector is arranged on a top plate of the sleeve, a loose part collecting device and a plurality of steam-water separator ascending cylinders are arranged on the top plate of the sludge collector, collecting coamings fixedly connected to the top plate are arranged between adjacent peripheral steam-water separator ascending cylinders, two ends of each collecting coaming are fixedly connected to the outer surface of each separator ascending cylinder, and a folded plate extending towards the center of the top plate is arranged at one end, far away from the top plate, of each collecting coaming.
8. The vertical steam generator of a pressurized water reactor nuclear power station as claimed in claim 7, wherein the trap fence is welded to the top plate, and both ends of the trap fence are respectively welded to the outer surface of the separator riser.
9. The vertical steam generator of a pressurized water reactor nuclear power station as claimed in claim 7, wherein the top plate of the sleeve is provided with an opening, the opening is connected with a group of steam-water separator ascending cylinders with the same number, a rotary vane is arranged in the ascending cylinder, a steam-water two-phase mixture generated by boiling in the sleeve flows through the opening of the top plate of the sleeve and enters the ascending cylinder, the steam-water generates spiral centrifugal motion under the action of the rotary vane, and the steam-water is separated under the action of centrifugal force.
10. The vertical steam generator of the pressurized water reactor nuclear power station as claimed in claim 7, wherein the separated water enters the water pool above the top plate of the sleeve again, the wet steam separated by the primary separator continues to flow upwards and passes through the dryer for secondary separation and drying, and the steam after secondary separation flows out of the steam generator through the flow restrictor arranged in the center of the upper disc-shaped seal head.
11. The vertical steam generator of a pressurized water reactor nuclear power station as claimed in claim 10, wherein the recirculated water separated from the steam-water separator is mixed with the water supply ring and enters the annular passage, the fluid flow speed of the annular passage is high, the fluid flow speed of the central area above the top plate of the sleeve is low, and a pressure difference exists between the central area and the peripheral circumferential area of the top plate.
12. The vertical steam generator of a pressurized water reactor nuclear power station as claimed in claim 11, characterized in that a water feed pipe is arranged above the sludge collector, the water feed pipe is in an approximately circular structure, the diameter of the water feed pipe is smaller than that of the top plate of the sleeve, and the water feed pipe is horizontally arranged in the steam generator.
13. The vertical steam generator of the pressurized water reactor nuclear power station as claimed in any one of claims 7 to 12, wherein the folded plate and the capture enclosing plate are in circular arc transition, and the transition radius is 5-25 mm.
14. The vertical steam generator of any one of claims 7 to 12, wherein the angle between the flap and the capture shroud is between 30 ° and 150 °.
15. The vertical steam generator of any one of claims 7 to 12, wherein the top plate is provided with a central zone aperture and a peripheral circumferential zone aperture, the capture shroud being located inside the peripheral circumferential zone aperture.
16. The vertical steam generator of any one of claims 7 to 12, wherein the capturing coaming and the folded plate form a larger radius in the top plate projection than the radius in the top plate projection of a water supply loop shower pipe or a J-shaped pipe provided in the steam generator.
Priority Applications (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201911171908.8A CN111140830A (en) | 2019-11-26 | 2019-11-26 | Vertical steam generator of pressurized water reactor nuclear power station and loose part trapping device thereof |
| PCT/CN2019/121886 WO2021102885A1 (en) | 2019-11-26 | 2019-11-29 | Vertical type steam generator of pressurized water reactor nuclear power plant and loosening part capturing device therefor |
| EP19953742.4A EP4080115A4 (en) | 2019-11-26 | 2019-11-29 | Vertical type steam generator of pressurized water reactor nuclear power plant and loosening part capturing device therefor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201911171908.8A CN111140830A (en) | 2019-11-26 | 2019-11-26 | Vertical steam generator of pressurized water reactor nuclear power station and loose part trapping device thereof |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN111140830A true CN111140830A (en) | 2020-05-12 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201911171908.8A Pending CN111140830A (en) | 2019-11-26 | 2019-11-26 | Vertical steam generator of pressurized water reactor nuclear power station and loose part trapping device thereof |
Country Status (3)
| Country | Link |
|---|---|
| EP (1) | EP4080115A4 (en) |
| CN (1) | CN111140830A (en) |
| WO (1) | WO2021102885A1 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111928215A (en) * | 2020-07-02 | 2020-11-13 | 合肥通用机械研究院有限公司 | High-efficient compact steam generator |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN111928215A (en) * | 2020-07-02 | 2020-11-13 | 合肥通用机械研究院有限公司 | High-efficient compact steam generator |
| CN111928215B (en) * | 2020-07-02 | 2022-07-19 | 合肥通用机械研究院有限公司 | High-efficient compact steam generator |
Also Published As
| Publication number | Publication date |
|---|---|
| EP4080115A1 (en) | 2022-10-26 |
| WO2021102885A1 (en) | 2021-06-03 |
| EP4080115A4 (en) | 2024-03-20 |
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Application publication date: 20200512 |