CN210108742U - Steam generator thermal hydraulic performance test simulator - Google Patents
Steam generator thermal hydraulic performance test simulator Download PDFInfo
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- CN210108742U CN210108742U CN201822267607.2U CN201822267607U CN210108742U CN 210108742 U CN210108742 U CN 210108742U CN 201822267607 U CN201822267607 U CN 201822267607U CN 210108742 U CN210108742 U CN 210108742U
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- 238000011056 performance test Methods 0.000 title claims abstract description 20
- 238000012546 transfer Methods 0.000 claims abstract description 32
- 238000005516 engineering process Methods 0.000 claims abstract description 11
- 239000012530 fluid Substances 0.000 claims description 20
- 238000007789 sealing Methods 0.000 claims description 16
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 13
- 238000005192 partition Methods 0.000 claims description 6
- 238000009529 body temperature measurement Methods 0.000 claims description 5
- 238000011010 flushing procedure Methods 0.000 claims description 3
- 238000012545 processing Methods 0.000 claims description 3
- 238000005070 sampling Methods 0.000 claims description 3
- 238000004088 simulation Methods 0.000 abstract description 18
- 238000012360 testing method Methods 0.000 abstract description 7
- 238000013461 design Methods 0.000 abstract description 5
- 238000000034 method Methods 0.000 abstract description 2
- 238000005259 measurement Methods 0.000 description 4
- 238000000926 separation method Methods 0.000 description 3
- 230000006872 improvement Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 238000009530 blood pressure measurement Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 238000011160 research Methods 0.000 description 1
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Abstract
The utility model belongs to the technical field of steam generator, concretely relates to steam generator thermal technology hydraulic performance test simulation body. The method includes the steps that a nuclear power steam generator prototype is simulated by a few tube bundles, in order to guarantee similarity, the straight section of a heat transfer pipe is as high as the prototype, the arrangement mode is the same as that of the prototype, and scaling is conducted only in the radial direction; the analog body adopts a descending pipe component to replace an annular descending channel of a steam generator prototype, a valve is arranged on the descending channel, and the resistance of the descending pipe is changed by adjusting the opening of the valve so as to realize the precise control of the circulation multiplying power. Compared with the prior art, the utility model discloses an experimental analogue body is for the thermal technology hydraulic characteristic to simulation nuclear power steam generator prototype and the utility model designs the test device, simulation steam generator secondary side flow field and thermal technology hydraulic performance that can be reasonable have realized the purpose of small-scale tube bank simulation steam generator prototype, greatly reduced the cost.
Description
Technical Field
The utility model belongs to the technical field of steam generator, concretely relates to steam generator thermal technology hydraulic performance test simulation body.
Background
The steam generator is a heat exchange device for generating steam required by a steam turbine, in a nuclear reactor, heat generated by nuclear fission is taken out by a coolant, and is transferred to a two-loop working medium through the steam generator, so that the steam generator generates steam with a certain temperature, a certain pressure and a certain dryness. The steam enters a steam turbine to do work and is converted into electric energy or mechanical energy. In this energy conversion process, the steam generator is a primary and a secondary loop device, and is therefore called a primary and secondary loop hub. The former is more widely applied in the nuclear power plants at home and abroad at present. The reliability of the steam generator has great influence on the safety, reliability and economic benefit of the nuclear power plant, and the steam generator plays an important role in accidents of the nuclear power plant according to the statistics and display of accidents of the pressurized water reactor nuclear power plant. Therefore, the research and improvement of the steam generator become an important link for the improvement and promotion of the nuclear power technology of the pressurized water reactor.
The thermal hydraulic performance of the steam generator is of great significance to the safe operation and the economy of the whole nuclear power plant. Before the various novel steam generator products are shaped, the comprehensive performance of the thermal engineering and hydraulic power of the novel steam generator products needs to be checked. Because the manufacturing and examination test cost of the steam generator is very high, a steam generator simulator needs to be designed for carrying out a thermotechnical hydraulic performance examination test in order to reduce the cost.
SUMMERY OF THE UTILITY MODEL
The utility model aims to provide a steam generator thermal technology hydraulic performance test simulation body to steam generator thermal technology hydraulic performance examination test's demand, reach the purpose of realizing simulation examination nuclear power steam generator prototype thermal technology hydraulic performance with lower cost.
The technical scheme of the utility model as follows:
a steam generator thermal hydraulic performance test simulator comprises a lower seal head assembly, a tube plate and tube bundle assembly, a lower cylinder assembly, an upper cylinder assembly, a steam-water separation assembly, a dryer assembly, an upper seal head assembly, a water supply assembly, a fluid temperature measuring assembly in a heat transfer tube and a support assembly, wherein the number and the arrangement height of support plates in the tube plate and the tube bundle assembly are the same as those of a steam generator prototype, drain holes are formed in the upper tube gallery area and the outer edge of each support plate, the drain holes are uniformly arranged, and the flow area of the drain holes is the same as that of plum blossom holes.
Furthermore, the heat transfer pipe in the pipe bundle assembly adopts the minimum bend radius which can be reached by the processing capacity on the premise of ensuring the pressure resistance.
Further, an annular cavity descending channel is connected to the lower end of the descending tube assembly before the lower end of the descending tube enters the tube bundle.
Furthermore, the downcomer outlets are symmetrically arranged and are in the same cross section with the center of the pipe gallery area, so that the main flushing of the pipe bundle area by fluid is realized.
Furthermore, a flow meter is arranged on the descending pipe of the descending pipe assembly, and the flow of the descending pipe is measured.
Furthermore, the fluid temperature measuring assembly in the heat transfer pipe comprises a sealing element a, a sealing element b, a high-pressure flange and a temperature sensor, wherein the temperature sensor penetrates through two pressure boundaries of the heat transfer pipe and the secondary side cylinder body, and high-pressure sealing of the two pressure boundaries is realized by adopting the sealing element a and the sealing element b.
Furthermore, pressure sampling pipes are arranged on the upper surface and the lower surface of the supporting plate at the positions of 50-100mm, at the interval of 90 degrees between the pipe gallery area, the cold side and the hot side, and are used for measuring the differential pressure of the supporting plate.
Further, temperature measuring points are arranged in the area below the first supporting plate and the third supporting plate of the supporting plate.
Furthermore, a partition plate is arranged in the middle of the lower end enclosure assembly, the lower end enclosure is divided into a cold side chamber and a hot side chamber, the two chambers are respectively provided with a primary side inlet and outlet connecting pipe, and the primary side inlet and outlet connecting pipe is directly connected with a system loop.
Furthermore, a descending pipe assembly is adopted to replace an annular descending channel of a steam generator prototype, the periphery of the partition plate is in full-welded sealing with the pipe plate and the lower end socket, a valve is arranged on the descending channel, and the resistance of the descending pipe is changed by adjusting the opening degree of the valve so as to realize the precise control of the circulation multiplying power.
Compared with the prior art, the beneficial effects of the utility model reside in that:
1. the utility model discloses an experimental analogue body is for the thermal technology hydraulic characteristic to simulation nuclear power steam generator prototype and the utility model designs a test device, simulation steam generator secondary side flow field and thermal technology hydraulic performance that can be reasonable have realized the purpose of small-scale tube bank simulation steam generator prototype, greatly reduced the cost.
2. The utility model discloses an experimental analog body has reduced secondary side fluid resistance through optimizing backup pad structure, can realize higher circulation multiplying power operation. Meanwhile, the circulation multiplying power can be continuously adjusted by adjusting the valve opening in the downcomer, and the operation control precision is high.
3. The utility model discloses an experimental simulation body, downcomer export symmetrical arrangement, and with the setting of pipe gallery district in same cross-section, through set up the annular chamber before the inlet of downcomer outlet tube bank, the tube bank entry flow field of simulation steam generator prototype that can be better.
4. The utility model discloses an experimental simulation body, the fluid temperature measurement subassembly has realized that temperature sensor runs through the two-layer pressure boundary of heat-transfer pipe and secondary side barrel in the heat-transfer pipe of design, reaches the purpose along the fluid temperature in the heat-transfer pipe of heat-transfer length direction direct measurement.
Drawings
FIG. 1 is a schematic diagram of a steam generator thermal hydraulic performance test simulator;
FIG. 2 is a schematic view of the front annular chamber of the inlet of the tube bundle at the bottom of the downcomer;
FIG. 3 is a schematic view of a support plate;
FIG. 4 is a schematic view of a fluid temperature measurement assembly within the heat transfer tube;
in the figure: 1. a lower seal head assembly; 2. a tube sheet and a tube bundle assembly; 3. a lower barrel assembly; 4. a drop tube assembly; 5. an upper barrel assembly; 6. a steam-water separation assembly; 7. a dryer assembly; 8. an upper end enclosure assembly; 9. a water supply assembly; 10. a fluid temperature measurement assembly within the heat transfer tube; 11. a seat assembly;
the fluid temperature measuring assembly in the heat transfer pipe comprises the following components: 101. a secondary side cylinder; 102. a sealing element a; 103. a sealing element b; 104. a high pressure flange; 105. a temperature sensor; 106. a heat transfer tube.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and specific embodiments.
The embodiment provides a steam generator thermal hydraulic performance test simulator, which adopts fewer tube bundles to simulate a nuclear steam generator prototype, and in order to ensure similarity, the specification and size of a heat transfer tube 106 in a tube plate and tube bundle assembly 6 are the same as the prototype, the straight section is as high as the prototype, the arrangement mode is the same as the prototype, and only the tube bundles are subjected to scaling in the radial direction.
The structure of the simulator is shown in fig. 1, and comprises a lower end enclosure assembly 1, a tube plate and tube bundle assembly 2, a lower barrel assembly 3, a downcomer assembly 4, an upper barrel assembly 5, a steam-water separation assembly 6, a dryer assembly 7, an upper end enclosure assembly 8, a water supply assembly 9, a heat transfer pipe internal fluid temperature measuring assembly 10, a support assembly 11 and other components. As shown in fig. 4, the structure of the fluid temperature measuring assembly 10 in the heat transfer pipe includes: a secondary side cylinder 101, a seal member a102, a seal member b103, a high-pressure flange 104, a temperature sensor 105, and a heat transfer pipe 106.
The fluid temperature measuring assembly 10 in the heat transfer pipe adopts a temperature sensor 105 to penetrate through two pressure boundaries of the heat transfer pipe 106 and the secondary side cylinder 101, and is directly arranged along the length direction of the heat transfer pipe 106 according to requirements for measurement. The temperature sensor 105 adopts a sealing element a102 and a sealing element b103 to realize high-pressure sealing of two layers of pressure boundaries. The temperature sensor 105 may be a sheathed thermocouple.
The tube plate and tube bundle assembly 2 adopts a few tube bundles to simulate a nuclear power steam generator prototype, in order to ensure similarity, the straight section of the heat transfer tube 106 is as high as the prototype, the arrangement mode is the same as the prototype, and scaling is carried out only in the radial direction. In order to facilitate measurement and adjustment of circulation multiplying power, a descending pipe is adopted to replace an annular descending channel, a valve is arranged on the descending channel, the opening of the descending pipe valve is continuously adjustable, and the resistance of the descending pipe is changed by adjusting the opening to realize accurate control of the circulation multiplying power; a flowmeter is arranged on the downcomer and used for measuring the flow of the downcomer; the flow meter can be a Venturi flow meter and can also be a non-contact ultrasonic flow meter.
The minimum bend radius of the heat transfer tube 106 that can be achieved by the processing capability on the premise of ensuring the pressure resistance is adopted for the heat transfer tube 106, and the minimum bend radius of the heat transfer tube 106 in the tube plate and tube bundle assembly 2 in this embodiment is 30 mm.
The lower end of the downcomer assembly 4 is connected with an annular chamber descending channel before entering the tube bundle, and the shape is shown in fig. 2; the outlets of the downcomer are symmetrically arranged and are positioned on the same section with the center of the pipe gallery area, so that the main flushing of the pipe bundle area by fluid is realized.
The supporting plates in the tube plate and tube bundle assembly 2 are schematically shown in FIG. 3, and the number and the arrangement height of the supporting plates are the same as those of a steam generator prototype; the pipe corridor area and the outer edge on the supporting plate are both provided with water flow holes, the water flow holes are uniformly arranged, and the flow area of the water flow holes is the same as that of the plum blossom holes. And temperature, pressure, differential pressure, flow and other measuring points are uniformly distributed on the primary side and the secondary side of the simulation body.
Considering the temperature distribution characteristics of the fluid on the secondary side, the secondary side of the simulation body is divided into a cold side, a hot side and a pipe gallery area, the temperature measuring points on the cold side are mainly arranged in the area below the third supporting plate, and the temperature measuring points on the hot side are mainly arranged in the area below the first supporting plate.
Pressure sampling pipes are arranged on the upper surface and the lower surface of each supporting plate of the simulator at 50-100mm positions in a pipe gallery area, a cold side and a hot side at intervals of 90 degrees to measure the differential pressure of the supporting plates. The differential pressure measurement adopts a differential pressure transmitter.
The lower end socket assembly 1 of the test body can be hemispherical or cylindrical, the hemispherical end socket is adopted in the embodiment, and a partition plate is arranged in the middle of the hemispherical end socket. The periphery of the middle partition plate of the lower end enclosure is fully welded with the lower end enclosure and the tube plate without leakage. The partition plate divides the lower end socket into a cold side chamber and a hot side chamber. The cold and hot side chambers are respectively provided with a primary side inlet and outlet connecting pipe, and the primary side inlet and outlet connecting pipes are directly connected with a system loop.
The steam generator thermal hydraulic performance test simulator of the embodiment is consistent with the design and operation parameters of a prototype. The steam generator thermal hydraulic performance test simulator can achieve the purpose of checking the thermal hydraulic performance of a nuclear power steam generator prototype at lower cost.
The test simulator of the embodiment reduces the secondary side fluid resistance by optimizing the supporting plate structure, and can realize higher circulation multiplying power operation. Meanwhile, the circulation multiplying power can be continuously adjusted by adjusting the valve opening in the downcomer, and the operation control precision is high.
The experimental simulation body of this embodiment, downcomer export symmetrical arrangement, and set up in same cross-section with the pipe gallery district, through set up the annular chamber before downcomer export tube bank entry, the tube bank entry flow field of the simulation steam generator prototype that can be better.
The experimental simulation body of this embodiment, the fluid temperature measurement subassembly in the heat-transfer pipe of design has realized that temperature sensor runs through the two-layer pressure boundary of heat-transfer pipe and secondary side barrel, reaches the purpose of the fluid temperature in the heat-transfer pipe of direct measurement along the heat-transfer length direction.
It will be apparent to those skilled in the art that various changes and modifications may be made without departing from the spirit and scope of the invention. It is intended that the present invention cover the modifications and variations of this invention provided they come within the scope of the appended claims and their equivalents.
Claims (10)
1. The utility model provides a steam generator thermal technology hydraulic performance test simulator, includes lower head subassembly (1), tube sheet and tube bank subassembly (2), lower barrel subassembly (3), downcomer subassembly (4), goes up barrel subassembly (5), catch water subassembly (6), desicator subassembly (7), upper head subassembly (8), water supply assembly (9), interior fluid temperature measurement subassembly (10) of heat-transfer pipe and support subassembly (11), its characterized in that: the number and the arrangement height of the support plates in the tube plate and tube bundle assembly (2) are the same as those of a steam generator prototype, drain holes are formed in the upper tube gallery area and the outer edge of each support plate, the drain holes are uniformly arranged, and the flow area of the drain holes is the same as that of the plum blossom holes.
2. The steam generator thermodynamic hydraulic performance test simulator of claim 1, wherein: the heat transfer pipe in the pipe bundle assembly (2) adopts the minimum bend radius which can be reached by the processing capacity on the premise of ensuring the pressure resistance.
3. The steam generator thermodynamic hydraulic performance test simulator of claim 1 or 2, wherein: an annular cavity descending channel is connected to the lower end of the descending pipe assembly (4) before the lower end of the descending pipe enters the pipe bundle.
4. The steam generator thermodynamic hydraulic performance test simulator of claim 3, wherein: the outlets of the downcomer are symmetrically arranged and are positioned on the same section with the center of the pipe gallery area, so that the main flushing of the pipe bundle area by fluid is realized.
5. The steam generator thermodynamic hydraulic performance test simulator of claim 3, wherein: and a flow meter is arranged on the descending pipe of the descending pipe assembly (4) and is used for measuring the flow of the descending pipe.
6. The steam generator thermodynamic hydraulic performance test simulator of claim 1 or 2, wherein: the fluid temperature measuring assembly (10) in the heat transfer pipe comprises a sealing element a (102), a sealing element b (103), a high-pressure flange (104) and a temperature sensor (105), wherein the temperature sensor (105) penetrates through two pressure boundaries of the heat transfer pipe (106) and a secondary side cylinder body (101), and the sealing element a (102) and the sealing element b (103) are adopted to realize high-pressure sealing of the two pressure boundaries.
7. The steam generator thermodynamic hydraulic performance test simulator of claim 6, wherein: and pressure sampling pipes are arranged on the upper surface and the lower surface of the supporting plate at the positions of 50-100mm, and are used for measuring the differential pressure of the supporting plate at intervals of 90 degrees in the pipe gallery area, the cold side and the hot side.
8. The steam generator thermodynamic hydraulic performance test simulator of claim 6, wherein: temperature measuring points are arranged in the area below the first supporting plate and the third supporting plate.
9. The steam generator thermodynamic hydraulic performance test simulator of claim 1 or 2, wherein: the middle of the lower end enclosure assembly (1) is provided with a partition plate which divides the lower end enclosure into a cold side chamber and a hot side chamber, the two chambers are respectively provided with a primary side inlet and outlet connecting pipe, and the primary side inlet and outlet connecting pipe is directly connected with a system loop.
10. The steam generator thermodynamic hydraulic performance test simulator of claim 1 or 2, wherein: the descending pipe assembly (4) is adopted to replace an annular descending channel of a steam generator prototype, a valve is installed on the descending channel, and the resistance of the descending pipe is changed by adjusting the opening of the valve so as to realize the precise control of the circulation multiplying power.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201822267607.2U CN210108742U (en) | 2018-12-28 | 2018-12-28 | Steam generator thermal hydraulic performance test simulator |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201822267607.2U CN210108742U (en) | 2018-12-28 | 2018-12-28 | Steam generator thermal hydraulic performance test simulator |
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| CN210108742U true CN210108742U (en) | 2020-02-21 |
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| CN201822267607.2U Withdrawn - After Issue CN210108742U (en) | 2018-12-28 | 2018-12-28 | Steam generator thermal hydraulic performance test simulator |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109540565A (en) * | 2018-12-28 | 2019-03-29 | 核动力运行研究所 | A kind of steam generator thermal-hydraulic performance test simulation body |
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2018
- 2018-12-28 CN CN201822267607.2U patent/CN210108742U/en not_active Withdrawn - After Issue
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109540565A (en) * | 2018-12-28 | 2019-03-29 | 核动力运行研究所 | A kind of steam generator thermal-hydraulic performance test simulation body |
| CN109540565B (en) * | 2018-12-28 | 2024-04-09 | 核动力运行研究所 | Steam generator thermal hydraulic performance test simulator |
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Granted publication date: 20200221 Effective date of abandoning: 20240409 |
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| AV01 | Patent right actively abandoned |
Granted publication date: 20200221 Effective date of abandoning: 20240409 |