CN112098131A - Steam generator simulation device for simulating non-uniform incoming flow of nuclear main pump inlet - Google Patents
Steam generator simulation device for simulating non-uniform incoming flow of nuclear main pump inlet Download PDFInfo
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Abstract
The invention provides a steam generator simulation device for simulating non-uniform incoming flow of a nuclear main pump inlet, which comprises a lower end enclosure, a cylinder, an upper end enclosure, a guide plate, an upper-layer pore plate, a partition plate, a lower-layer pore plate, an inlet pipe and an outlet pipe, wherein the lower end enclosure is provided with a plurality of through holes; the upper end enclosure and the lower end enclosure are respectively connected to the upper end and the lower end of the cylinder body, and an inlet pipe and an outlet pipe are arranged on the lower end enclosure; the center of the cylinder body is provided with a partition plate, the partition plate extends to the lower end enclosure to divide the space between the cylinder body and the lower end enclosure into a left chamber and a right chamber, and the inlet pipe and the outlet pipe are respectively positioned in the left chamber and the right chamber; a guide plate is arranged in the upper end enclosure, an upper-layer pore plate is arranged on the upper portion of the right cavity, and a lower-layer pore plate is arranged on the lower portion of the right cavity. The upper-layer pore plate uniformly rectifies fluid, and the lower-layer pore plate enables the fluid to have the same flow velocity distribution as that of the outlet of the nuclear main pump, so that the non-uniform incoming flow of the inlet of the nuclear main pump is simulated, and the method can be used for researching the influence of the non-uniform incoming flow on the performance of the nuclear main pump.
Description
Technical Field
The invention relates to the technical field of nuclear power, in particular to a steam generator simulation device for simulating non-uniform incoming flow of an inlet of a nuclear main pump.
Background
The steam generator at the inlet of the nuclear main pump is directly connected with the two main pumps, so that the incoming flow of the main pump inlet is uneven. In order to research the influence of non-uniform incoming flow of the steam generator on the main pump, the construction shrinkage ratio is 1:2.3 main pump test bench. The steam generator simulation device can simulate an outlet non-uniform flow field generated by an actual steam generator and also provides a basis for subsequent other researches. In the steam generator plant in the nuclear power plant, a form of U-shaped pipe is used, which is expensive to manufacture and process. In most researches on non-uniform inflow of the inlet of the nuclear main pump, only the structure of the lower chamber of the steam generator is reserved mostly, so that the deviation of the flow field of the inlet of the nuclear main pump from the actual flow field is large.
Patent document CN104005963A discloses a main pump structure for a small nuclear power station, which is composed of an inlet guide vane, a sealing ring, an impeller, an outlet guide vane, a snap ring, a key, an impeller bolt, a bolt gasket, a piston ring, a set of fasteners, a main bolt, a main nut gasket, a rotating shaft, a driving device, a heat insulation sealing body, an inner cylinder of a double-layer sleeve of a pressure container, an outer cylinder of the double-layer sleeve of the pressure container, and the like. The pump is driven by the driving device to circulate the reactor coolant at a predetermined flow rate, and transfers heat generated by the reactor core to the two circuits through the steam generator. The steam generator in the scheme is connected in a loop of the nuclear main pump, the uniformity of fluid at an inlet of the nuclear main pump can be influenced, and the effect research of specific influence needs to be realized through a simulation device or is too high in cost. Therefore, designing a steam generator simulator for simulating non-uniform inflow of the inlet of the nuclear main pump is necessary for researching the influence of the non-uniform inflow of the nuclear main pump.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a steam generator simulation device for simulating non-uniform inflow of a nuclear main pump inlet.
The invention provides a steam generator simulation device for simulating non-uniform incoming flow of a nuclear main pump inlet, which comprises a lower end enclosure, a cylinder, an upper end enclosure, a guide plate, an upper-layer pore plate, a partition plate, a lower-layer pore plate, an inlet pipe and an outlet pipe, wherein the lower end enclosure is provided with a plurality of through holes;
the upper end enclosure and the lower end enclosure are respectively connected to the upper end and the lower end of the cylinder body, and an inlet pipe and an outlet pipe are arranged on the lower end enclosure;
the center of the cylinder body is provided with a partition plate, the partition plate extends to the lower end enclosure to divide the space between the cylinder body and the lower end enclosure into a left chamber and a right chamber, and the inlet pipe and the outlet pipe are respectively positioned in the left chamber and the right chamber;
a guide plate is arranged in the upper end enclosure, an upper-layer pore plate is arranged on the upper portion of the right cavity, and a lower-layer pore plate is arranged on the lower portion of the right cavity.
Preferably, the sealing device further comprises a bottom plate, the bottom plate is arranged at the bottom of the lower sealing head, and the upper part of the bottom plate is connected with the partition plate.
Preferably, still include the row's clean pipe, arrange clean pipe setting in low head minimum, arrange clean pipe intercommunication left cavity and right cavity.
Preferably, still include the blast pipe, the blast pipe sets up the top at the top of upper cover.
Preferably, the guide plate is arranged above the partition plate, the guide plate is arc-shaped, and the guide plate can guide and introduce the fluid in the left chamber into the right chamber to inhibit the formation of vortex.
Preferably, the openings on the upper-layer pore plate and the lower-layer pore plate are arranged in multiple rows, and the openings are distributed in a regular triangle form, that is, three adjacent openings which are not on the same straight line form a regular triangle.
Preferably, the upper layer orifice plate and the lower layer orifice plate can be detachably arranged in the right chamber of the cylinder body.
Preferably, the axial lengths of the openings on the upper-layer orifice plate are equal, and the flow velocity distribution of the fluid flowing through the upper-layer orifice plate tends to be uniform.
Preferably, the axial lengths of the holes on the lower-layer pore plate are different, and the flow velocity distribution of the fluid flowing through the lower-layer pore plate and the flow velocity distribution of the outlet of the simulated prototype nuclear main pump inlet steam generator meet the similar principle.
Preferably, the axial length of the opening on the lower-layer orifice plate is gradually increased from the side close to the partition plate to the side far away from the partition plate.
Compared with the prior art, the invention has the following beneficial effects:
1. the upper-layer pore plate uniformly rectifies fluid, and the lower-layer pore plate enables the fluid to have the same flow velocity distribution as that of the outlet of the nuclear main pump, so that the non-uniform incoming flow of the inlet of the nuclear main pump is simulated, and the method can be used for researching the influence of the non-uniform incoming flow on the performance of the nuclear main pump.
2. The invention gives consideration to the manufacturing feasibility and reduces the manufacturing cost on the basis of obtaining the outlet speed distribution meeting the requirement, and is favorable for researching the non-uniform incoming flow of the inlet of the nuclear main pump.
3. The invention forms a U-shaped structure through the baffle plate nuclear baffle plate, is used for simulating the structure of a real steam generator, and changes the fluid velocity after passing through the holes with different axial lengths on the lower-layer pore plate, thereby simulating the fluid flow velocity distribution at the outlet of the real steam generator.
Drawings
Other features, objects and advantages of the invention will become more apparent upon reading of the detailed description of non-limiting embodiments with reference to the following drawings:
FIG. 1 is a schematic structural diagram of the present invention.
FIG. 2 is a schematic top view of an upper or lower orifice plate of the present invention.
Fig. 3 is an enlarged view of a person in the area a in fig. 2.
Fig. 4 is an enlarged view of the region B in fig. 2.
Fig. 5 is a schematic longitudinal cross-section (or longitudinal section) of a lower orifice plate according to the present invention.
FIG. 6 is a Moody friction coefficient chart.
FIG. 7 is a graph showing the relationship between the axial length of holes and the hole row number of the lower hole plate according to the present invention.
The figures show that:
lower end socket 1 clapboard 7
Lower-layer pore plate 8 of cylinder 2
Upper head 3 inlet pipe 9
Deflector 4 outlet pipe 10
Detailed Description
The present invention will be described in detail with reference to specific examples. The following examples will assist those skilled in the art in further understanding the invention, but are not intended to limit the invention in any way. It should be noted that it would be obvious to those skilled in the art that various changes and modifications can be made without departing from the spirit of the invention. All falling within the scope of the present invention.
The invention aims to provide a steam generator simulation device capable of simulating non-uniform incoming flow of a nuclear main pump inlet, which is a device capable of simulating a non-uniform incoming flow field of the nuclear main pump inlet.
According to the steam generator simulation device for simulating the non-uniform incoming flow of the inlet of the nuclear main pump, as shown in fig. 1, the steam generator simulation device comprises a lower end enclosure 1, a cylinder 2, an upper end enclosure 3, a guide plate 4, an upper-layer pore plate 5, a partition plate 7, a lower-layer pore plate 8, an inlet pipe 9 and an outlet pipe 10; the upper end enclosure 3 and the lower end enclosure 1 are respectively connected to the upper end and the lower end of the cylinder 2, and the lower end enclosure 1 is provided with an inlet pipe 9 and an outlet pipe 10; a partition plate 7 is arranged in the center of the cylinder 2, the partition plate 7 extends to the lower end enclosure 1 to divide the space between the cylinder 2 and the lower end enclosure 1 into a left chamber and a right chamber, and the inlet pipe 9 and the outlet pipe 10 are respectively positioned in the left chamber and the right chamber; a guide plate 4 is arranged inside the upper end enclosure 3, an upper-layer pore plate 5 is arranged on the upper portion of the right cavity, and a lower-layer pore plate 8 is arranged on the lower portion of the right cavity.
Preferably, the cylinder 2 is connected with the upper seal head 3 and the lower seal head 1 by adopting container flanges. The related dimension of the lower end socket 1 is strictly designed by reducing the dimension by 1:2.3 according to the dimension of the lower cavity of the steam generator at the inlet of the simulated prototype nuclear main pump, so as to ensure the similarity of hydraulic models. The structural forms of the lower end socket 1 and the upper end socket 3 are spherical end sockets. The number of the outlet pipes 10 is two, and the two outlet pipes 10 are symmetrically arranged.
As shown in fig. 1, the sealing device further comprises a bottom plate 6, wherein the bottom plate 6 is arranged at the bottom of the lower sealing head 1, and the upper part of the bottom plate 6 is connected with a partition plate 7. Still include row's clean pipe 12, arrange clean pipe 12 and set up in low head 1 minimum, arrange clean pipe 12 intercommunication left cavity and right cavity. Still include exhaust pipe 11, exhaust pipe 11 sets up the top at last head 3. The guide plate 4 is arranged above the partition plate 7, the guide plate 4 is arc-shaped, and the guide plate 4 can guide the fluid in the left chamber into the right chamber, so that the formation of a vortex is inhibited, the flow resistance loss is reduced, and the rectification effect is achieved.
Preferably, the bottom plate 6 is inclined downward from the right chamber (the chamber where the outlet pipe 10 is located) to the left chamber (the chamber where the inlet pipe 9 is located), the inlet pipe 9 is positioned lower than the bottom plate 6, and the portion of the bottom plate 6 located in the right chamber is provided with through holes near the partition 7, so that the fluid in the right chamber enters below the bottom plate 6 through the through holes and is discharged through the discharge pipe 12.
As shown in fig. 1, 2-5 and 7, the openings of the upper-layer orifice plate 5 and the lower-layer orifice plate 8 are arranged in multiple rows, and the openings are distributed in a regular triangle form, that is, three adjacent openings which are not on the same straight line form a regular triangle. The upper-layer pore plate 5 and the lower-layer pore plate 8 can be detachably arranged in the right cavity of the cylinder 3. The axial lengths of the holes on the upper-layer pore plate 5 are equal, and the flow velocity distribution of the fluid after flowing through the upper-layer pore plate 5 tends to be uniform. As shown in fig. 5 and 7, the axial lengths of the openings of the lower-layer orifice plate 8 are different, and the flow velocity distribution of the fluid flowing through the lower-layer orifice plate 8 and the flow velocity distribution of the outlet of the inlet steam generator of the simulated prototype nuclear main pump satisfy a similar principle. The axial length of the opening on the lower-layer orifice plate 8 is gradually increased from the side close to the partition plate 7 to the side far away from the partition plate 7.
Preferably, the number of the upper-layer pore plates 5 is two, the speed of the fluid tends to be uniform after passing through the upper-layer pore plates 5, the number of the lower-layer pore plates 8 is one, and the speed distribution of the fluid after passing through the lower-layer pore plates 8 and the speed distribution of the outlet of the inlet steam generator of the simulated prototype nuclear main pump meet the similar principle. Preferably, the radial dimension of the openings in the upper layer of perforated plate 5 is the same, and the radial dimension of the openings in the lower layer of perforated plate 8 is the same.
A steam generator simulation device for simulating non-uniform inflow of an inlet of a nuclear main pump is connected into a loop, an inlet pipe 9 is connected with a loop pipeline, and an outlet pipe 10 is connected with a model main pump. Fluid medium in the loop enters from an inlet pipe 9 of the lower end enclosure 1, flows through a left chamber of the cylinder 2 and then enters a right chamber through the guide plate 4, when the fluid medium passes through the upper end enclosure 3, the guide plate 4 can inhibit the vortex formed at the position, then the fluid flows through the upper-layer pore plate 5, the upper-layer pore plate 5 has a rectification function, the overall flow of the fluid medium after passing through the upper-layer pore plate 5 is relatively uniform, then the fluid medium passes through the lower-layer pore plate 8 below the right cavity of the cylinder 2, the lower-layer pore plate 8 has pore channels with different axial lengths, different outlet speed distributions can be obtained by designing different pore channel sizes, and finally, after the desired flow field velocity profile (a flow field velocity profile satisfying a similar principle to that of the simulated prototype nuclear main pump inlet steam generator outlet) is obtained, the fluidic medium flow exits the outlet pipe 10 into the model main pump.
In order to simultaneously consider the simple structure of the equipment and simulate the linear distribution velocity field in the U-shaped pipe of the inlet steam generator of the prototype nuclear main pump, the invention designs the lower-layer pore plate 8 with pore canals with different lengths, and the design steps of the lower-layer pore plate 8 are as follows:
step 1: extracting a speed distribution curve function of an outlet of a U-shaped pipe of a steam generator at an inlet of a prototype nuclear main pump;
step 2: the lower layer orifice plate 8 is provided with holes;
and step 3: calculating the velocity distribution of the flow field of the lower-layer pore plate 8;
and 4, step 4: and calculating the distribution of the axial length (channel length) of the openings on the lower-layer pore plate 8.
The step 1 specifically comprises the following steps:
assuming that the outlet speed distribution of a U-shaped pipe of an inlet steam generator of a prototype nuclear main pump is a linear function, the hole row number x from the center to the edge of the U-shaped pipe is an abscissa, and the speed w is set as an ordinate, the method comprises the following steps:
w＝kmx+bm
wherein k ism，bmIs a constant.
The step 2 specifically comprises the following steps:
as shown in fig. 2-4, the lower-layer orifice plate 8 adopts regular triangle rows according to GB151, that is, three adjacent orifices which are not on the same straight line form a regular triangle, the diameter of the orifice is d, the center distance of the orifices is d1, n orifices are obtained, a rows of orifices are counted from the side close to the partition plate 7 to the side far from the partition plate 7, the orifice row number (row from the side close to the partition plate 7) is represented by i, i is 1, 2, 3 … a, and the distance from the first row to the center of the partition plate 7 is L.
The step 3 specifically comprises the following steps:
because the flow velocity distribution of the fluid after flowing through the lower-layer pore plate 8 and the flow velocity distribution of the outlet of the simulated prototype nuclear main pump inlet steam generator meet the similar principle, the flow field flow velocity distribution curve after flowing through the lower-layer pore plate 8 is also a linear function, namely v is ki + b, the openings on the outlet of the simulated prototype nuclear main pump inlet steam generator are m rows, and the gradient of the flow velocity distribution in the pipes is km(ii) a The holes on the lower layer orifice plate 8 are a rows, and the slope of the flow velocity distribution of the fluid after flowing through the lower layer orifice plate 8 is obtained according to the proportional relation
The relationship between the speed of the next row and the speed of the previous row is:
vi-vi-1＝k
the average velocity of the fluid after passing through the lower orifice plate 8 is:
wherein Q ismVolume flow through the lower orifice plate 8 in m3R is the pore radius in m;
the average flow rate multiplied by the total orifice number equals the sum of the velocities within each orifice:
wherein N isiThe number of the pore channels in the ith row is represented;
the speed value of the row of the pore canals with the highest speed is equal to the average speed multiplied by the total hole number minus the speed of each row of the rest pore canals with the highest speed multiplied by the corresponding pore canal number, and then divided by the maximum row of the pore canals:
then
b＝vmax-k×1
Finally, a specific functional relationship of v ═ ki + b can be obtained.
The step 4 specifically comprises the following steps:
the Reynolds number in the upper opening of the lower-layer pore plate 8 is:
wherein, ReiReynolds number, Re, of the ith row of holesmaxAt maximum Reynolds number, ReminIs the minimum Reynolds number, and ρ is the fluid density in kg/m3；viIs the flow velocity in the ith row of holes in units of m/s, v1Is the flow velocity in row 1 hole, vaIs the flow velocity in the a-th row of holes, d is the diameter of the holes, in m; mu is the kinematic viscosity of the fluid, in Pa · s;
relative roughness of
Wherein, taking 0.1 as absolute roughness to obtain relative roughness;
according to the Moody friction coefficient diagram (figure 6), the Reynolds numbers of different pore channels are different due to different lengths, and the Moody diagram is searched according to the calculated maximum Reynolds number and minimum Reynolds number to obtain friction factors corresponding to different pores; in the application, the friction factor values corresponding to different channels are similar and are positioned in a smoother section in the figure, and for the convenience of calculation, the friction factor value corresponding to the average flow rate is selected as the friction factor lambda value of each channel, wherein lambda is approximately equal to 0.027;
according to a straight pipe resistance formula:
wherein h isfIs the straight pipe resistance in m2/s2(ii) a λ is friction factor, 0.027 is taken; 1 is the length of the tube in mm; d is the pipe diameter in mm; zeta is a local resistance coefficient, and a formula is calculated and shown in the follow-up; u is the flow velocity in the tube, m/s.
According to the fact that head losses hf (representing the flow mechanical energy loss of fluid in unit weight, corresponding to a lower-layer pore plate, namely the mechanical energy loss when different pore channel fluids flow) of parallel pipelines are the same, for two different holes, the numbers of the holes are hole 1 and hole 2, the method comprises the following steps: h isf1＝hf2
Let ζ be1+ζ2ζ (wherein ζ)1＝1；ζ20.5, the former representing the local resistance coefficient due to the constriction when the fluid flows into the channel and the latter representing the local resistance coefficient due to the flare), then:
finally, assuming a first row of channels having a length of 50mm, a distribution of the lengths of the channels of the evaporator simulating assembly is obtained as shown in FIG. 7.
In one embodiment, the upper sealing head 3 is in the form of a spherical sealing head, the inner diameter of the spherical sealing head is 1932mm, the wall thickness of the spherical sealing head is 12mm, a flow guide plate 4 is arranged in the middle of the spherical sealing head and used for improving the flow field structure, the flow guide plate 4 is connected with the upper sealing head 3 in a welding mode, an exhaust pipe 11 is arranged on the top of the upper sealing head 3, and the upper sealing head 3 is connected with the barrel.
The internal diameter of cylindrical barrel 2 is 1932mm, and the wall thickness is 12mm, highly equals about 4m, is equipped with the baffle 7 that the wall thickness is 12mm in the middle of the barrel 2, baffle 7 and 1 bottom plate 6 sealing connection of low head, and baffle 7 is with barrel 2 and 1 inside two cavities that divide into of low head, left cavity feed liquor, and right cavity goes out the liquid, and barrel 2 and 1 adoption container flange joint of low head.
Three pore plates (two upper pore plates 5 and one lower pore plate 8) are placed in a right cavity of the cylinder 2, the pore plates are detachably connected, the two upper pore plates 5 above have a uniform effect on incoming flow, the lower pore plate 8 below can linearize the uniform flow field velocity distribution, the fluid flow velocity distribution at the outlet of the lower pore plate 8 and the velocity distribution at the outlet of the simulated prototype nuclear main pump inlet steam generator meet the similar principle, the holes of the upper pore plate 5 and the lower pore plate 8 adopt a regular triangle form according to GB151, the hole diameter d is 38mm, the hole distance d1 is 55mm, the axial length distribution of the holes on the lower pore plate 8 is shown in figure 7, and the hole row number is 19 rows from one end close to the partition plate 7.
The related dimension of the lower end socket 1 is strictly designed according to the dimension of the lower chamber of the original steam generator in a size reduction of 1:2.3, so that the similarity of hydraulic models is ensured. The structural form of the lower end enclosure 1 is a spherical end enclosure, the inner diameter is 1932mm, the wall thickness is 12mm, the bottom of the lower end enclosure 1 is provided with a bottom plate 6, the thickness is 12mm, liquid is reserved in a clean discharging container, the bottom of the lower end enclosure 1 is provided with a clean discharging pipe 12, and the lower end enclosure 1 is provided with an inlet pipe 9 and two symmetrically arranged outlet pipes 10.
In the description of the present application, it is to be understood that the terms "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", and the like indicate orientations or positional relationships based on those shown in the drawings, and are only for convenience in describing the present application and simplifying the description, but do not indicate or imply that the referred device or element must have a specific orientation, be constructed in a specific orientation, and be operated, and thus, should not be construed as limiting the present application.
The foregoing description of specific embodiments of the present invention has been presented. It is to be understood that the present invention is not limited to the specific embodiments described above, and that various changes or modifications may be made by one skilled in the art within the scope of the appended claims without departing from the spirit of the invention. The embodiments and features of the embodiments of the present application may be combined with each other arbitrarily without conflict.
Claims (10)
1. A steam generator simulation device for simulating non-uniform incoming flow of a nuclear main pump inlet is characterized by comprising a lower seal head (1), a barrel body (2), an upper seal head (3), a guide plate (4), an upper-layer pore plate (5), a partition plate (7), a lower-layer pore plate (8), an inlet pipe (9) and an outlet pipe (10);
the upper sealing head (3) and the lower sealing head (1) are respectively connected to the upper end and the lower end of the cylinder body (2), and an inlet pipe (9) and an outlet pipe (10) are arranged on the lower sealing head (1);
a partition plate (7) is arranged in the center of the cylinder body (2), the partition plate (7) extends to the lower end enclosure (1) to divide the space of the cylinder body (2) and the lower end enclosure (1) into a left chamber and a right chamber, and the inlet pipe (9) and the outlet pipe (10) are respectively positioned in the left chamber and the right chamber;
a guide plate (4) is arranged inside the upper end enclosure (3), an upper-layer pore plate (5) is arranged on the upper portion of the right chamber, and a lower-layer pore plate (8) is arranged on the lower portion of the right chamber.
2. The steam generator simulator for simulating the non-uniform inflow of the inlet of the nuclear main pump as claimed in claim 1, further comprising a bottom plate (6), wherein the bottom plate (6) is arranged at the bottom of the lower seal head (1), and a partition plate (7) is connected to the upper part of the bottom plate (6).
3. The steam generator simulator for simulating the non-uniform inflow of the inlet of the nuclear main pump as claimed in claim 1, further comprising a drain pipe (12), wherein the drain pipe (12) is arranged at the lowest point of the lower head (1), and the drain pipe (12) is communicated with the left chamber and the right chamber.
4. The steam generator simulator for simulating the non-uniform inflow of the inlet of the nuclear main pump as claimed in claim 1, further comprising an exhaust pipe (11), wherein the exhaust pipe (11) is arranged at the top end of the upper end enclosure (3).
5. The steam generator simulator for simulating the non-uniform inflow of the inlet of the nuclear main pump according to claim 1, wherein the guide plate (4) is arranged above the partition plate (7), the guide plate (4) is arc-shaped, and the guide plate (4) can guide and introduce the fluid in the left chamber into the right chamber to inhibit the formation of vortex.
6. The steam generator simulator for simulating the non-uniform inflow of the inlet of the nuclear main pump, as recited in claim 1, wherein the openings of the upper-layer orifice plate (5) and the lower-layer orifice plate (8) are arranged in multiple rows, and the openings are distributed in a regular triangle manner, that is, three adjacent openings which are not on the same straight line form a regular triangle.
7. The steam generator simulator for simulating the non-uniform inflow of the inlet of the nuclear main pump as claimed in claim 1, wherein the upper-layer orifice plate (5) and the lower-layer orifice plate (8) are detachably mounted in the right chamber of the cylinder (3).
8. The steam generator simulator for simulating the non-uniform inflow of the inlet of the nuclear main pump, as recited in claim 1, wherein the axial lengths of the openings of the upper-layer orifice plate (5) are equal, and the flow velocity distribution of the fluid flowing through the upper-layer orifice plate (5) tends to be uniform.
9. The steam generator simulator for simulating the non-uniform inflow of the nuclear main pump inlet according to claim 1, wherein the axial lengths of the holes on the lower-layer pore plate (8) are different, and the flow velocity distribution of the fluid flowing through the lower-layer pore plate (8) and the flow velocity distribution of the outlet of the steam generator at the inlet of the simulated prototype nuclear main pump meet the similar principle.
10. The steam generator simulator for simulating non-uniform inflow of the inlet of the nuclear main pump according to claim 9, wherein the axial length of the opening of the lower-layer orifice plate (8) is gradually increased from the side close to the partition plate (7) to the side far away from the partition plate (7).
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| CN112964894A (en) * | 2021-02-03 | 2021-06-15 | 青岛科技大学 | Water vapor simulation generator for gas field distribution measurement experiment |
| CN115050492A (en) * | 2022-05-07 | 2022-09-13 | 上海核工程研究设计院有限公司 | Steam generator hydroecium head and visual test piece of main pump case integration |
| CN115050492B (en) * | 2022-05-07 | 2024-05-10 | 上海核工程研究设计院股份有限公司 | Visual test piece of steam generator hydroecium head and main pump case integration |
Citations (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3898961A (en) * | 1972-06-26 | 1975-08-12 | Siemens Ag | Steam generator |
| US5056468A (en) * | 1990-01-31 | 1991-10-15 | Siemens Aktiengesellschaft | Steam generator |
| JPH06109202A (en) * | 1992-09-24 | 1994-04-19 | Hitachi Ltd | Steam generator |
| CN1649665A (en) * | 2002-04-14 | 2005-08-03 | 益达科技责任有限公司 | Steam reforming fuel processor, burner assembly, and methods of operating the same |
| CN101307897A (en) * | 2008-06-24 | 2008-11-19 | 清华大学 | Device for guaranteeing cooling air stack loop medium flow uniformity in steam generator |
| CN102049224A (en) * | 2009-10-27 | 2011-05-11 | 中国石油化工股份有限公司 | Flow field turbulator |
| JP2012063119A (en) * | 2010-09-17 | 2012-03-29 | Toshiba Corp | Moisture separating heating apparatus |
| CN203311741U (en) * | 2013-07-12 | 2013-11-27 | 中国核动力研究设计院 | Simulation structure of downward channel of steam generator |
| CN204177137U (en) * | 2014-09-04 | 2015-02-25 | 安徽食亿鲜食品有限公司 | A kind of cellular-type can cooling vacuum vapor drying plant |
| CN104508754A (en) * | 2012-04-25 | 2015-04-08 | Smr发明技术有限公司 | Nuclear steam supply system |
| CN105716061A (en) * | 2015-12-14 | 2016-06-29 | 美的集团股份有限公司 | Steam generator, steam generator system and household appliance |
| CN207990581U (en) * | 2017-12-08 | 2018-10-19 | 李尚福 | High performance vapor generator |
| CN110578915A (en) * | 2019-09-11 | 2019-12-17 | 常州大学 | Steam generator with preheater and superheater |
| CN210462964U (en) * | 2020-01-17 | 2020-05-05 | 北京民利储能技术有限公司 | Steam generator for fused salt energy storage |
-
2020
- 2020-09-15 CN CN202010969133.5A patent/CN112098131B/en active Active
Patent Citations (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3898961A (en) * | 1972-06-26 | 1975-08-12 | Siemens Ag | Steam generator |
| US5056468A (en) * | 1990-01-31 | 1991-10-15 | Siemens Aktiengesellschaft | Steam generator |
| JPH06109202A (en) * | 1992-09-24 | 1994-04-19 | Hitachi Ltd | Steam generator |
| CN1649665A (en) * | 2002-04-14 | 2005-08-03 | 益达科技责任有限公司 | Steam reforming fuel processor, burner assembly, and methods of operating the same |
| CN101307897A (en) * | 2008-06-24 | 2008-11-19 | 清华大学 | Device for guaranteeing cooling air stack loop medium flow uniformity in steam generator |
| CN102049224A (en) * | 2009-10-27 | 2011-05-11 | 中国石油化工股份有限公司 | Flow field turbulator |
| JP2012063119A (en) * | 2010-09-17 | 2012-03-29 | Toshiba Corp | Moisture separating heating apparatus |
| CN104508754A (en) * | 2012-04-25 | 2015-04-08 | Smr发明技术有限公司 | Nuclear steam supply system |
| CN203311741U (en) * | 2013-07-12 | 2013-11-27 | 中国核动力研究设计院 | Simulation structure of downward channel of steam generator |
| CN204177137U (en) * | 2014-09-04 | 2015-02-25 | 安徽食亿鲜食品有限公司 | A kind of cellular-type can cooling vacuum vapor drying plant |
| CN105716061A (en) * | 2015-12-14 | 2016-06-29 | 美的集团股份有限公司 | Steam generator, steam generator system and household appliance |
| CN207990581U (en) * | 2017-12-08 | 2018-10-19 | 李尚福 | High performance vapor generator |
| CN110578915A (en) * | 2019-09-11 | 2019-12-17 | 常州大学 | Steam generator with preheater and superheater |
| CN210462964U (en) * | 2020-01-17 | 2020-05-05 | 北京民利储能技术有限公司 | Steam generator for fused salt energy storage |
Non-Patent Citations (2)
| Title |
|---|
| ZHIEE JHIA OOI等: "Experimental dataset with high-speed visualization for vertical upward steam-water flow with transition from annulus to circular channel", 《INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER》 * |
| 刘振凤等: "CPR1000蒸汽发生器的结构分析", 《一重技术》 * |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112964894A (en) * | 2021-02-03 | 2021-06-15 | 青岛科技大学 | Water vapor simulation generator for gas field distribution measurement experiment |
| CN112964894B (en) * | 2021-02-03 | 2022-08-26 | 青岛科技大学 | Water vapor simulation generator for gas field distribution measurement experiment |
| CN115050492A (en) * | 2022-05-07 | 2022-09-13 | 上海核工程研究设计院有限公司 | Steam generator hydroecium head and visual test piece of main pump case integration |
| CN115050492B (en) * | 2022-05-07 | 2024-05-10 | 上海核工程研究设计院股份有限公司 | Visual test piece of steam generator hydroecium head and main pump case integration |
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