CN114544209B - Thermal shock test device for verifying pipe plugging process of nuclear-grade steam generator - Google Patents
Thermal shock test device for verifying pipe plugging process of nuclear-grade steam generator Download PDFInfo
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- CN114544209B CN114544209B CN202111621970.XA CN202111621970A CN114544209B CN 114544209 B CN114544209 B CN 114544209B CN 202111621970 A CN202111621970 A CN 202111621970A CN 114544209 B CN114544209 B CN 114544209B
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- pipe
- thermal shock
- steam generator
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- 238000012360 testing method Methods 0.000 title claims abstract description 34
- 230000035939 shock Effects 0.000 title claims abstract description 30
- 238000000034 method Methods 0.000 title claims abstract description 27
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 68
- 238000010438 heat treatment Methods 0.000 claims abstract description 26
- 239000007921 spray Substances 0.000 claims abstract description 24
- 238000001816 cooling Methods 0.000 claims description 10
- 230000001105 regulatory effect Effects 0.000 claims description 8
- 238000012795 verification Methods 0.000 claims description 7
- 230000000694 effects Effects 0.000 claims description 3
- 238000005516 engineering process Methods 0.000 claims description 2
- 230000000903 blocking effect Effects 0.000 description 11
- 238000012546 transfer Methods 0.000 description 11
- 230000001276 controlling effect Effects 0.000 description 6
- 239000003595 mist Substances 0.000 description 6
- 238000005485 electric heating Methods 0.000 description 4
- 230000003993 interaction Effects 0.000 description 3
- 238000004880 explosion Methods 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 230000004888 barrier function Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000009991 scouring Methods 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 239000008399 tap water Substances 0.000 description 1
- 235000020679 tap water Nutrition 0.000 description 1
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
- G01M99/00—Subject matter not provided for in other groups of this subclass
- G01M99/002—Thermal testing
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N25/00—Investigating or analyzing materials by the use of thermal means
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Physics & Mathematics (AREA)
- General Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Chemical & Material Sciences (AREA)
- Analytical Chemistry (AREA)
- Biochemistry (AREA)
- General Health & Medical Sciences (AREA)
- Immunology (AREA)
- Pathology (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention provides a thermal shock test device for verifying a nuclear-grade steam generator pipe plugging process, which comprises a heating furnace, a water spray gun, a clamping moving device, a hollow connecting sleeve, a water inlet pipe and an air inlet pipe, wherein the water inlet pipe and the air inlet pipe are connected to the water spray gun, the water spray gun penetrates through the hollow connecting sleeve, the hollow connecting sleeve is arranged at the top of the clamping moving device, and the clamping end of the hollow connecting sleeve stretches into the heating furnace. The thermal shock test device for verifying the nuclear-grade steam generator pipe plugging process provided by the invention can simulate the reliability, stability and safety of the plug when a certain pipe plugging process is adopted under various limit working conditions.
Description
Technical Field
The invention relates to the technical field of maintenance of nuclear power station steam generators, in particular to a thermal shock test device for verifying a nuclear-grade steam generator pipe plugging process.
Background
The steam generator is core equipment of a steam power conversion system of a nuclear power station, heat generated by a primary side core is transferred to a secondary side through a heat transfer pipe, water vapor of a secondary loop is separated and dried, and then is transferred to a steam turbine to generate electricity, wherein the primary side is a part of a pressure boundary of an RSC system. The heat transfer tube is an important component of the pressure boundary of a circuit, is an important barrier for preventing radioactive fission products from leaking out, and is one of the weakest links of a circuit system. The heat transfer tube is subjected to mechanical or chemical damage under the high-temperature and high-pressure environment and the scouring of high-radiation dosage medium for a long time, and when the damage of the heat transfer tube reaches the damage maintenance standard, the heat transfer tube needs to be maintained so as to prevent the radioactive coolant material from leaking. The blocking pipe is to add plugs at two ends of the damaged heat transfer pipe respectively, so as to isolate the damaged heat transfer pipe from a loop medium effectively. Because of the particularity of nuclear power operation, the plugging process needs to ensure safety and reliability and stop the risk of plug failure during the operation of the nuclear power station, so that the plugging process needs to be verified and assessed, and the reliability, stability and safety of the plug when a certain plugging process is adopted under various limit working conditions are simulated.
Disclosure of Invention
The invention aims to overcome the defects in the prior art, and provides a thermal shock test device for verifying the pipe plugging process of a nuclear-grade steam generator, which can simulate the reliability, stability and safety of a plug when a certain pipe plugging process is adopted under various limiting working conditions.
In order to achieve the above object, the present invention provides the following technical solutions:
the utility model provides a thermal shock test device for stifled pipe technology verification of nuclear level steam generator, includes heating furnace, water spray gun, centre gripping mobile device, cavity adapter sleeve, inlet tube and intake pipe, the inlet tube with the intake pipe is connected to the water spray gun, the water spray gun wears to locate inside the cavity adapter sleeve, the cavity adapter sleeve install in centre gripping mobile device's top, the centre gripping end of cavity adapter sleeve stretches into the heating furnace.
As an implementation manner, the water inlet pipe is provided with an electromagnetic water valve and a water flow regulating valve.
As an implementation mode, the water inlet end of the water inlet pipe is provided with a water supply ball valve.
As an implementation manner, a first filter is arranged between the water supply ball valve and the electromagnetic water valve.
As an implementation mode, the air inlet pipe is provided with a plate heat exchanger, the plate heat exchanger is externally connected with a water chiller, and a pipeline at the outlet end of the plate heat exchanger is provided with an air storage tank.
As an embodiment, a pressure regulating valve is provided on the line at the inlet end of the plate heat exchanger.
As an implementation manner, the air inlet pipe is provided with a proportional electromagnetic flow valve.
As an implementation manner, the air inlet end of the air inlet pipe is sequentially provided with an air supply ball valve and a second filter.
As an embodiment, the hollow connecting sleeve is provided with a temperature sensor.
Compared with the prior art, the thermal shock test device for verifying the nuclear-grade steam generator pipe plugging process has the following beneficial effects:
the thermal shock test device for verifying the pipe plugging process of the nuclear-grade steam generator can realize temperature circulation from the ambient temperature to the set high temperature under certain pressure, control the temperature rise and fall time by controlling the temperature rise and fall speed, thereby realizing thermal shock on a heat transfer pipe plugging sample, simulating the working state of a plug under the limit working condition of the steam generator, and verifying the sealing effect of the plug under the working condition by repeatedly circulating the thermal shock working condition.
The thermal shock verification requirements of various pipe blocking processes such as explosion pipe blocking, welding pipe blocking, mechanical pipe blocking and pipe blocking of steam generators of different nuclear power units can be met by setting different thermal shock high temperature; the clamping moving device is designed to avoid the risk of scalding caused by direct contact of operators with the height Wen Yangjian; adopting a water mist spray gun cooling mode, and realizing accurate control of the cooling rate by matching with an electric control system; the man-machine interaction operation mode is designed, the automation is strong, and the operation is convenient.
Drawings
In order to more clearly illustrate the embodiments of the invention or the technical solutions in the prior art, the drawings that are required in the embodiments or the description of the prior art will be briefly described, it being obvious that the drawings in the following description are only some embodiments of the invention, and that other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
Fig. 1 is a schematic diagram of a thermal shock test device for verifying a pipe plugging process of a nuclear-grade steam generator according to an embodiment of the present invention.
Reference numerals illustrate:
1. a water supply ball valve; 2. a gas supply ball valve; 3. a first filter; 4. a second filter; 5. a pressure regulating valve; 6. a plate heat exchanger; 7. a water chiller; 8. a gas storage tank; 9. a heating furnace; 10. a temperature sensor; 11. a proportional electromagnetic flow valve; 12. an electromagnetic water valve; 13. a water flow regulating valve; 14. a water spray gun; 15. clamping the moving device; 16. a hollow connection sleeve; 17. a water inlet pipe; 18. and an air inlet pipe.
Detailed Description
While the thermal shock test apparatus for nuclear grade steam generator pipe plugging process verification of the present invention may be implemented in a number of different ways, exemplary embodiments will be described in detail herein with reference to the accompanying drawings, it being understood that the description herein should be considered as an illustration of the structure of the thermal shock test apparatus for nuclear grade steam generator pipe plugging process verification and is not intended to limit the scope of the invention to the exemplary embodiments. Accordingly, the drawings and description of the embodiments are to be regarded as illustrative in nature, and not as restrictive.
In the description of the present invention, it should be noted that, directions or positional relationships indicated by terms "upper", "lower", "left", "right", "front", "rear", "inner", "outer", "horizontal", "vertical", etc. herein are based on directions or positional relationships shown in the drawings, are merely for convenience of description and simplification of description, and do not indicate or imply that the apparatus or component in question must have a specific direction, be configured and operated in a specific direction, and thus should not be construed as limiting the present invention. Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
Further details are provided below with reference to the specific embodiments.
As shown in fig. 1, the invention provides a thermal shock test device for verifying a pipe plugging process of a nuclear-grade steam generator, which comprises a heating furnace 9, a water spray gun 14, a clamping moving device 15, a hollow connecting sleeve 16, a water inlet pipe 17 and an air inlet pipe 18, wherein the water inlet pipe 17 and the air inlet pipe 18 are connected to the water spray gun 14, the water spray gun 14 penetrates through the hollow connecting sleeve 16, the hollow connecting sleeve 16 is arranged at the top of the clamping moving device 15, and the clamping end of the hollow connecting sleeve 16 stretches into the heating furnace 9.
The water supply ball valve 1, the first filter 3, the electromagnetic water valve 12 and the water flow regulating valve 13 are sequentially arranged in the water inlet direction of the water inlet pipe 17 (i.e. in the direction from the water source to the water spray gun 14). The air inlet pipe 18 is sequentially provided with an air supply ball valve 2, a second filter 4, a pressure regulating valve 5, a plate heat exchanger 6, an air storage tank 8 and a proportional electromagnetic flow valve 11 in the air inlet direction. The water inlet pipe 17 and the air inlet pipe 18 are connected in parallel to the water spray gun 14, and the water spray gun 14 mostly penetrates inside the hollow connection sleeve 16, and the end (clamping end) of the hollow connection sleeve 16 for connecting the heat transfer pipe plug sample extends into the heating furnace 9.
Wherein, heating furnace 9 realizes heating heat transfer pipe stifled pipe sample, and the upper portion of centre gripping mobile device 15 designs a cavity adapter sleeve 16, and heat transfer pipe stifled pipe sample is installed in cavity adapter sleeve 16, has temperature sensor 10 to be used for control and feedback sample temperature in the cavity adapter sleeve 16, and power control cabinet control system controls furnace temperature.
And in the heating stage, the clamping moving device 15 drives the sample to be inserted into a heating hearth of the electric heating furnace to heat, and the sample is heated to a set temperature. In the cooling stage, the clamping moving device 15 drives the sample to move out of the heating furnace, the water inlet system and the air inlet system are started, the water mist spray gun 14 forms a water mist spray sample plug part, the sample plug is cooled, and the cooling rate is controlled by controlling the opening of the electromagnetic water valve 12 of the water inlet system and the opening of the proportional electromagnetic flow valve 11 of the air inlet system.
Further, the heat shock test device is additionally provided with the water chiller 7 and the plate heat exchanger 6, and the water chiller 7 and the plate heat exchanger 6 cool an air inlet source and strengthen the cooling effect on the sample plug. The automatic control and man-machine interaction of the device are realized by the power control cabinet, such as heating temperature setting, temperature rise and fall rate setting, thermal shock frequency setting, automatic stop in emergency and the like.
It is noted that the heating furnace 9 is used as a heat source of a sample to be heated, the power control of the heating furnace 9 is controlled by a control unit (for example, a PLC), the sample to be heated is installed on the clamping moving device 15, when a heating program is started, the clamping moving device 15 clamps the sample to be heated to stretch into the heating furnace 9, the sample to be heated is heated, meanwhile, the real-time temperature of the sample to be heated is collected and fed back to the control unit through the temperature sensor 10, and the control unit performs feedback adjustment on the heating of the sample to be heated by controlling the power of the heating furnace 9, so that the heating rate and the target temperature of the sample to be heated are controlled. When the temperature of the sample to be heated reaches the target temperature, the clamping moving device 15 clamps the sample to be heated to exit the heating furnace 9, meanwhile, the control unit starts the proportional electromagnetic flow valve 11 and the electromagnetic water valve 12, the water spray gun 14 is started to cool the sample to be heated, the control unit adjusts the flow of the water spray gun 14 by controlling the real-time opening of the proportional electromagnetic flow valve 11 and the electromagnetic water valve 12, and the cooling rate of the sample to be heated is accurately controlled by combining the temperature fed back by the temperature sensor 10, so that a heating and cooling cycle is completed.
The thermal shock verification requirements of various pipe blocking processes such as explosion pipe blocking, welding pipe blocking, mechanical pipe blocking and pipe blocking of steam generators of different nuclear power units can be met by setting different thermal shock high temperature; the clamping moving device is designed to avoid the risk of scalding caused by direct contact of operators with the height Wen Yangjian; adopting a water mist spray gun cooling mode, and realizing accurate control of the cooling rate by matching with an electric control system; the man-machine interaction operation mode is designed, the automation is strong, and the operation is convenient.
The operation and running steps of the thermal shock test device for verifying the pipe plugging process of the nuclear-grade steam generator provided by the invention are as follows:
(1) The device air supply ball valve 2 is opened to ensure the normal supply of compressed air.
(2) The water supply ball valve 1 of the equipment is opened to ensure the normal supply of tap water source.
(3) The test piece and the water mist spray gun 14 of the test piece tool are correctly connected and installed in the heating furnace 9.
(4) The test thermocouple 10 of the test piece is mounted.
(5) And electrifying the measuring instrument, opening the control unit, and displaying the measured value normally on the upper computer.
(6) And starting the electric heating furnace 9 according to the working condition requirement, and setting parameters such as temperature, temperature rise time, test cycle times and the like on an upper computer control interface according to the test working condition requirement.
(7) Starting a test starting program, heating the electric heating furnace 9 to a set temperature by switching on and switching off, automatically controlling the clamping moving device 15 by the control unit according to the test piece detection temperature to enable the test piece to move in/out of the electric heating furnace 9, automatically controlling the water mist spray gun 14 to operate, timely collecting data and generating a curve on the display.
(8) After the system temperature cycle meets the test setting requirement, selecting a certain pre-developed test working condition to perform automatic temperature cycle.
The foregoing is merely illustrative of the present invention, and the present invention is not limited thereto, and any changes or substitutions easily contemplated by those skilled in the art within the scope of the present invention should be included in the scope of the present invention. Therefore, the protection scope of the present invention shall be subject to the protection scope of the claims.
Claims (8)
1. The utility model provides a thermal shock test device for stifled pipe technology verification of nuclear level steam generator, its characterized in that, including heating furnace (9), water spray gun (14), centre gripping mobile device (15), cavity adapter sleeve (16), inlet tube (17) and intake pipe (18), inlet tube (17) with intake pipe (18) are connected to water spray gun (14), water spray gun (14) wear to locate inside cavity adapter sleeve (16), cavity adapter sleeve (16) install in the top of centre gripping mobile device (15), the centre gripping end of cavity adapter sleeve (16) stretches into heating furnace (9), be equipped with plate heat exchanger (6) on intake pipe (18), plate heat exchanger (6) external cold water machine (7), plate heat exchanger (6) with cold water machine (7) cool off the air supply, strengthen the cooling effect to the end cap of sample, be equipped with gas holder (8) on the pipeline of the exit end of plate heat exchanger (6).
2. The thermal shock test device for verifying the pipe plugging process of the nuclear grade steam generator according to claim 1, wherein the water inlet pipe (17) is provided with an electromagnetic water valve (12) and a water flow regulating valve (13).
3. The thermal shock test device for verifying the pipe plugging process of the nuclear grade steam generator according to claim 2, wherein the water inlet end of the water inlet pipe (17) is provided with a water supply ball valve (1).
4. A thermal shock test device for verification of a nuclear grade steam generator pipe plugging process according to claim 3, wherein a first filter (3) is arranged between the water supply ball valve (1) and the electromagnetic water valve (12).
5. The thermal shock test device for verifying the pipe plugging process of the nuclear grade steam generator according to claim 1, wherein a pressure regulating valve (5) is arranged on a pipeline at the inlet end of the plate heat exchanger (6).
6. The thermal shock test device for verifying the pipe plugging process of the nuclear-grade steam generator according to claim 1, wherein the air inlet pipe (18) is provided with a proportional electromagnetic flow valve (11).
7. The thermal shock test device for verifying the pipe plugging process of the nuclear-grade steam generator according to claim 1, wherein the air inlet end of the air inlet pipe (18) is sequentially provided with an air supply ball valve (2) and a second filter (4).
8. The thermal shock test device for verifying a pipe plugging process of a nuclear grade steam generator according to claim 1, wherein a temperature sensor (10) is arranged on the hollow connecting sleeve (16).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111621970.XA CN114544209B (en) | 2021-12-28 | 2021-12-28 | Thermal shock test device for verifying pipe plugging process of nuclear-grade steam generator |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111621970.XA CN114544209B (en) | 2021-12-28 | 2021-12-28 | Thermal shock test device for verifying pipe plugging process of nuclear-grade steam generator |
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| Publication Number | Publication Date |
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| CN114544209A CN114544209A (en) | 2022-05-27 |
| CN114544209B true CN114544209B (en) | 2024-01-12 |
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| CN202111621970.XA Active CN114544209B (en) | 2021-12-28 | 2021-12-28 | Thermal shock test device for verifying pipe plugging process of nuclear-grade steam generator |
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Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN115206562B (en) * | 2022-06-24 | 2024-07-16 | 中核武汉核电运行技术股份有限公司 | Pressure and temperature transient test device for pipe plugging process check |
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2021
- 2021-12-28 CN CN202111621970.XA patent/CN114544209B/en active Active
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| CN114544209A (en) | 2022-05-27 |
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