CN115389104A - Steam leakage simulation test system and test method for main steam pipeline of power plant - Google Patents
Steam leakage simulation test system and test method for main steam pipeline of power plant Download PDFInfo
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- CN115389104A CN115389104A CN202110564616.1A CN202110564616A CN115389104A CN 115389104 A CN115389104 A CN 115389104A CN 202110564616 A CN202110564616 A CN 202110564616A CN 115389104 A CN115389104 A CN 115389104A
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- 238000012360 testing method Methods 0.000 title claims abstract description 29
- 238000004088 simulation Methods 0.000 title claims abstract description 24
- 238000010998 test method Methods 0.000 title claims abstract description 11
- 239000008367 deionised water Substances 0.000 claims abstract description 31
- 229910021641 deionized water Inorganic materials 0.000 claims abstract description 31
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 31
- 230000001105 regulatory effect Effects 0.000 claims description 25
- 238000012544 monitoring process Methods 0.000 claims description 10
- 238000005259 measurement Methods 0.000 claims description 8
- 238000010438 heat treatment Methods 0.000 claims description 6
- 239000010963 304 stainless steel Substances 0.000 claims description 3
- 229910000589 SAE 304 stainless steel Inorganic materials 0.000 claims description 3
- 238000002474 experimental method Methods 0.000 claims description 3
- 229910001220 stainless steel Inorganic materials 0.000 claims description 3
- 239000010935 stainless steel Substances 0.000 claims description 3
- 238000000034 method Methods 0.000 claims 1
- 238000005516 engineering process Methods 0.000 description 3
- 238000001514 detection method Methods 0.000 description 2
- 238000010793 Steam injection (oil industry) Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
- G01M3/00—Investigating fluid-tightness of structures
- G01M3/007—Leak detector calibration, standard leaks
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- 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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Abstract
The invention aims to disclose a steam leakage simulation test system and a test method for a main steam pipeline of a power plant, which comprises an open loop, wherein the open loop comprises a deionized water tank, a plunger pump, a spiral pipe steam generator, a Venturi flowmeter, a pressure container and a condenser which are connected by adopting a plurality of pipelines; compared with the prior art, the mode that a spiral tube steam generator of a direct-current power supply is connected with a pressure container in series is used as a steam source, so that the device has the advantages of high temperature rise rate, stable pressure, stable steam flow and greatly increased adjustability, and the test efficiency is greatly improved; the power load can be accurately adjusted according to the steam parameter requirement, the operation cost of the rack is greatly reduced, and the aim of the invention is realized.
Description
Technical Field
The invention relates to a thermal hydraulic experimental device and a test method, in particular to a steam leakage simulation test system and a test method for a main steam pipeline of a power plant.
Background
The LBB (Leak Before Break) technology is an advanced design technology for ensuring the operation safety and reliability of a reactor, and the basic idea is that when a pipeline leaks, the leakage amount can be monitored by a specially-arranged leakage monitoring system when reaching a certain degree.
The LBB technology is more and more widely applied, but no engineering practical application of LBB adopted by a main steam pipeline exists in China at present.
Therefore, a steam leakage simulation test system and a test method for a main steam pipeline of a power plant are particularly needed to solve the existing problems.
Disclosure of Invention
The invention aims to provide a steam leakage simulation test system and a steam leakage simulation test method for a main steam pipeline of a power plant, which aim at the defects of the prior art, have the steam required by the generated working condition and provide an environmental background for simulating steam leakage for testing the performance of a steam leakage detection device.
The technical problem solved by the invention can be realized by adopting the following technical scheme:
the invention provides a steam leakage simulation test system for a main steam pipeline of a power plant, which comprises an open loop, wherein the open loop comprises a deionized water tank, a plunger pump, a spiral pipe steam generator, a venturi flowmeter, a pressure container and a condenser which are connected by adopting a plurality of pipelines;
the outlet of the deionized water tank is connected with the inlet of the plunger pump, the deionized water tank and the outlet of the plunger pump are connected with each other to form a first bypass, the deionized water tank and the outlet of the spiral tube steam generator are connected with each other to form a second bypass, the outlet of the pressure container is divided into a main path and a branch path, and the main path of the outlet of the pressure container is sequentially connected with a condenser and the deionized water tank; a branch of an outlet of the pressure container is sequentially connected with the valve group and the main steam pipeline through a Venturi flowmeter; the spiral tube steam generator adopts a direct current power supply to heat deionized water flowing through the spiral tube steam generator.
In one embodiment of the invention, an electric control valve TF1 is arranged on a first bypass pipeline between the deionized water tank and the plunger pump, and an electric control valve TF2 is arranged on a second bypass pipeline between the deionized water tank and the plunger pump; an electric valve TF3 is arranged on a main path on the outlet side of the spiral tube steam generator; an electric valve TF4 is arranged between the outlet of the pressure container and the condenser; an electric valve TF5 is arranged at the rear end of the Venturi flowmeter on the branch of the outlet of the pressure container; the back end of the electric valve TF5 is provided with a valve group TF6, a valve group TF7, a valve group TF8, a valve group TF9 and a valve group TF10 which are connected in parallel.
In an embodiment of the present invention, the valve set TF6, the valve set TF7, the valve set TF8, the valve set TF9 and the valve set TF10 and the pipelines connected thereto respectively correspond to simulated leakage points at different positions of the main steam pipeline.
In one embodiment of the present invention, the spiral tube steam generator uses DN20 304 stainless steel tubing wound in 20 layers with a radius of 500 mm.
In one embodiment of the invention, the inlet and the outlet of the spiral tube steam generator are respectively connected with the positive pole and the negative pole of a direct current power supply.
In one embodiment of the invention, the spiral tube steam generator is heated by applying direct current, and the heating power reaches 300KW.
In an embodiment of the invention, a temperature measuring point is arranged between the deionized water tank and the plunger pump, a temperature measuring point is arranged on the pressure vessel, and the temperature measuring point is an armored K-type thermocouple.
In one embodiment of the invention, a pressure measuring point is arranged between the plunger pump and the spiral tube steam generator, a pressure measuring point is arranged on the pressure container, and the pressure measuring point adopts a cross river EJA530E pressure transmitter.
In an embodiment of the present invention, a flow measurement point is disposed between the plunger pump and the spiral tube steam generator, a flow measurement point is disposed between the spiral tube steam generator and the pressure vessel, a flow measurement point is disposed between the pressure vessel and the valve set, and the flow measurement point employs a venturi flow meter.
In one embodiment of the invention, the deionized water tank and the plunger pump are connected by a stainless steel 304 pipeline.
The invention provides a test method of a steam leakage simulation test system of a main steam pipeline of a power plant, which comprises the following steps:
before the experiment begins, the electric regulating valve TF2 on the second bypass is opened, and the other valves are closed;
if the test is carried out, the plunger pump is started, the opening of the electric regulating valve TF2 is slowly regulated, the whole open loop is boosted, the direct-current power supply is started, the heating power of the spiral tube steam generator is regulated through the power regulator, and the temperature measured by a temperature measuring point T2 at the outlet of the spiral tube steam generator and the pressure measured by a pressure measuring point P1 at the plunger outlet are monitored; the pressure of the opening regulating loop of the electric regulating valve TF2 is continuously regulated to meet the working condition requirement; gradually increasing power to a heater of the spiral tube steam generator, gradually closing an electric regulating valve TF2 on a second bypass and simultaneously gradually opening an electric regulating valve TF3 after the outlet of the spiral tube steam generator reaches a superheated steam state by monitoring the temperature of a temperature measuring point T2 at the outlet of the spiral tube steam generator and the system pressure of a pressure measuring point P1, and allowing the superheated steam to enter a pressure container through the electric regulating valve TF3; monitoring a temperature measuring point T3 and a pressure measuring point P2, gradually opening the electric valve TF4 when the pressure in the pressure container reaches 1MPa, and keeping the temperature and the pressure in the pressure container stable by adjusting the opening degree of the electric valve TF4 after the temperature and the pressure in the pressure container rise to the requirements of working conditions; and then opening one of a valve group TF6, a valve group TF7, a valve group TF8, a valve group TF9 and a valve group TF10 according to the working condition requirement, then slowly opening the electric valve TF5, monitoring a Venturi flowmeter between the pressure container and the valve group, and continuously adjusting the opening degree of the electric valve TF5 to enable the flow to reach the working condition requirement.
In one embodiment of the invention, the pressure of the open circuit is in the range of 0.1-20MPa and the spiral tube steam generator is heated to a maximum operating temperature of the open circuit of 350 ℃.
Compared with the prior art, the steam leakage simulation test system and the test method for the main steam pipeline of the power plant adopt the mode that the spiral pipe steam generator of the direct-current power supply is connected with the pressure container in series as the steam source, have the advantages of high temperature rise rate, stable pressure, stable steam flow and greatly increased adjustability, and greatly improve the test efficiency; the power load can be accurately adjusted according to the steam parameter requirement, the operation cost of the rack is greatly reduced, and the aim of the invention is realized.
The features of the present invention will be apparent from the accompanying drawings and from the detailed description of the preferred embodiments which follows.
Drawings
Fig. 1 is a schematic structural diagram of a steam leakage simulation test system for a main steam pipeline of a power plant according to the present invention.
Detailed Description
In order to make the technical means, the creation characteristics, the achievement purposes and the effects of the invention easy to understand, the invention is further explained below by combining the specific drawings.
Examples
As shown in fig. 1, the steam leakage simulation test system for the main steam pipeline of the power plant comprises an open loop, wherein the open loop comprises a deionized water tank 1, a plunger pump 2, a spiral pipe steam generator 4, a venturi flowmeter, a pressure vessel 6 and a condenser 7 which are connected by adopting a plurality of pipelines;
an outlet of the deionized water tank 1 is connected with an inlet of the plunger pump 2, outlets of the deionized water tank 1 and the plunger pump 2 are connected with each other to form a first bypass, an outlet of the deionized water tank 1 and an outlet of the spiral tube steam generator 4 are connected with each other to form a second bypass, an outlet of the pressure container 6 is divided into a main path and a branch path, and the main path of the outlet of the pressure container 6 is sequentially connected with the condenser 7 and the deionized water tank 1; the branch of the outlet of the pressure container 6 is connected with the valve group and the main steam pipeline 9 in sequence through a Venturi flowmeter; the spiral tube steam generator 4 heats the deionized water flowing through it by using a direct current power supply.
An electric control valve TF1 is arranged on a first bypass pipeline between the deionized water tank 1 and the plunger pump 2, and an electric control valve TF2 is arranged on a second bypass pipeline between the deionized water tank 1 and the plunger pump 2; an electric valve TF3 is arranged on a main path at the outlet side of the spiral tube steam generator 4; an electric valve TF4 is arranged between the outlet of the pressure container 6 and the condenser 7; an electric valve TF5 is arranged at the rear end of the Venturi flowmeter 8 on the branch of the outlet of the pressure container 6; the back end of the electric valve TF5 is provided with a valve group TF6, a valve group TF7, a valve group TF8, a valve group TF9 and a valve group TF10 which are connected in parallel.
The valve group TF6, the valve group TF7, the valve group TF8, the valve group TF9, the valve group TF10 and pipelines connected with the valve group TF correspond to simulated leakage points of different positions of the main steam pipeline 9 respectively.
The spiral tube steam generator 4 adopts a 304 stainless steel tube of DN20 and winds 20 layers with the radius of 500 mm; the inlet and the outlet of the spiral tube steam generator 4 are respectively connected with the anode and the cathode of a direct current power supply; the spiral-tube steam generator 4 is heated by means of direct current, and the heating power reaches 300KW.
A temperature measuring point T1 is arranged between the deionized water tank 1 and the plunger pump 2, a temperature measuring point T2 is arranged on the pressure vessel 6, and the temperature measuring point T1 and the temperature measuring point T2 adopt armored K-type thermocouples.
A pressure measuring point P1 is arranged between the plunger pump 2 and the spiral tube steam generator 4, a pressure measuring point P2 is arranged on the pressure container 6, and the pressure measuring point P1 and the pressure measuring point P2 adopt a river EJA530E pressure transmitter.
A flow measuring point is arranged between the plunger pump 2 and the spiral tube steam generator 4, and the flow measuring point adopts a Venturi flowmeter 3; a flow measuring point is arranged between the spiral tube steam generator 4 and the pressure container 6, and the flow measuring point adopts a Venturi flowmeter 5; and a flow measuring point is arranged between the pressure container 6 and the valve group, and the flow measuring point adopts a Venturi flowmeter 8.
The deionized water tank 1 and the plunger pump 2 are connected by a stainless steel 304 pipeline.
The invention discloses a test method of a steam leakage simulation test system of a main steam pipeline of a power plant, which comprises the following steps:
before the experiment begins, the electric control valve TF2 on the second bypass is opened, and other valves are closed;
if the test is carried out, the plunger pump 2 is started, the opening of the electric regulating valve TF2 is slowly regulated, the whole open loop is boosted to 2MPa, the direct-current power supply is started, the heating power of the spiral tube steam generator 4 is regulated through the power regulator, and the temperature measured by a temperature measuring point T2 at the outlet of the spiral tube steam generator 4 and the pressure measured by a pressure measuring point P1 at the plunger outlet are monitored; the pressure of an opening adjusting loop of the electric adjusting valve TF2 is continuously adjusted to 8.66MPa, so that the pressure meets the working condition requirement; gradually increasing power to a heater of the spiral tube steam generator 4, gradually closing an electric regulating valve TF2 on a second bypass and simultaneously gradually opening an electric regulating valve TF3 after the temperature of a temperature measuring point T2 at the outlet of the spiral tube steam generator reaches 300.6 ℃ and the system pressure of a pressure measuring point P1 by monitoring the temperature of the temperature measuring point T2 at the outlet of the spiral tube steam generator until the outlet of the spiral tube steam generator reaches the state of superheated steam, and allowing the superheated steam to enter a pressure container 6 through the electric regulating valve TF3; monitoring a temperature measuring point T3 and a pressure measuring point P2, gradually opening an electric valve TF4 when the pressure in the pressure container reaches 1MPa, and keeping the temperature and the pressure in the pressure container stable by adjusting the opening of the electric valve TF4 after the temperature and the pressure in the pressure container rise to 300.6 ℃ and 8.66 MPa; and then opening one of a valve group TF6, a valve group TF7, a valve group TF8, a valve group TF9 and a valve group TF10 according to the working condition requirement, then slowly opening an electric valve TF5, monitoring a Venturi flowmeter 8 between the pressure container 6 and the valve group, and continuously adjusting the opening of the electric valve TF5 to enable the flow to reach 20kg/h of the working condition requirement, so that the steam injection working condition is realized, and the performance of the steam leakage detection device is tested.
The pressure range of the open loop is 0.1-20MPa, and the spiral tube steam generator heats the open loop to ensure that the maximum operating temperature of the open loop can reach 350 ℃.
The foregoing shows and describes the general principles and broad features of the present invention and advantages thereof. It will be understood by those skilled in the art that the present invention is not limited to the embodiments described above, which are merely illustrative of the principles of the invention, but various changes and modifications may be made without departing from the spirit and scope of the invention, which is defined by the appended claims and their equivalents.
Claims (12)
1. A steam leakage simulation test system for a main steam pipeline of a power plant is characterized by comprising an open loop, wherein the open loop comprises a deionized water tank, a plunger pump, a spiral pipe steam generator, a Venturi flowmeter, a pressure vessel and a condenser which are connected by adopting a plurality of pipelines;
the outlet of the deionized water tank is connected with the inlet of the plunger pump, the deionized water tank and the outlet of the plunger pump are connected with each other to form a first bypass, the deionized water tank and the outlet of the spiral tube steam generator are connected with each other to form a second bypass, the outlet of the pressure container is divided into a main path and a branch path, and the main path of the outlet of the pressure container is sequentially connected with a condenser and the deionized water tank; a branch of an outlet of the pressure container is sequentially connected with the valve group and the main steam pipeline through a Venturi flowmeter; the spiral tube steam generator adopts a direct current power supply to heat deionized water flowing through the spiral tube steam generator.
2. The power plant main steam pipeline steam leakage simulation test system according to claim 1, wherein an electric control valve TF1 is arranged on a first bypass pipeline between the deionized water tank and the plunger pump, and an electric control valve TF2 is arranged on a second bypass pipeline between the deionized water tank and the plunger pump; an electric valve TF3 is arranged on a main path on the outlet side of the spiral tube steam generator; an electric valve TF4 is arranged between the outlet of the pressure container and the condenser; an electric valve TF5 is arranged at the rear end of the Venturi flowmeter on the branch of the outlet of the pressure container; the back end of the electric valve TF5 is provided with a valve group TF6, a valve group TF7, a valve group TF8, a valve group TF9 and a valve group TF10 which are connected in parallel.
3. The steam leakage simulation test system for the main steam pipeline of the power plant according to claim 1, wherein the valve group TF6, the valve group TF7, the valve group TF8, the valve group TF9, the valve group TF10 and the pipelines connected thereto correspond to simulated leakage points at different positions of the main steam pipeline respectively.
4. The power plant main steam line steam leak simulation test system of claim 1, wherein the spiral tube steam generator employs DN20 304 stainless steel tubing wound in 20 layers with a radius of 500 mm.
5. The power plant main steam pipeline steam leak simulation test system of claim 1, wherein an inlet and an outlet of the spiral pipe steam generator are connected to a positive pole and a negative pole of a direct current power supply, respectively.
6. The power plant main steam line steam leak simulation test system of claim 1, wherein the spiral tube steam generator is heated by applying direct current with a heating power of up to 300KW.
7. The power plant main steam pipeline steam leakage simulation test system according to claim 1, wherein a temperature measuring point is arranged between the deionized water tank and the plunger pump, a temperature measuring point is arranged on the pressure vessel, and the temperature measuring point is an armored K-type thermocouple.
8. The power plant main steam pipeline steam leakage simulation test system of claim 1, wherein a pressure measuring point is arranged between the plunger pump and the spiral pipe steam generator, a pressure measuring point is arranged on the pressure vessel, and the pressure measuring point adopts a cross river EJA530E pressure transmitter.
9. The power plant main steam pipeline steam leakage simulation test system according to claim 1, wherein a flow measurement point is arranged between the plunger pump and the spiral pipe steam generator, a flow measurement point is arranged between the spiral pipe steam generator and the pressure vessel, a flow measurement point is arranged between the pressure vessel and the valve set, and a venturi flowmeter is adopted as the flow measurement point.
10. The power plant main steam pipeline steam leakage simulation test system of claim 1, wherein the deionized water tank and the plunger pump are connected by a stainless steel 304 pipeline.
11. A test method of a steam leakage simulation test system of a main steam pipeline of a power plant is characterized by comprising the following steps:
before the experiment begins, the electric control valve TF2 on the second bypass is opened, and other valves are closed;
if the test is carried out, the plunger pump is started, the opening degree of the electric regulating valve TF2 is slowly regulated, the whole open loop is boosted, the direct-current power supply is turned on, the heating power of the spiral tube steam generator is regulated through the power regulator, and the temperature measured by a temperature measuring point T2 at the outlet of the spiral tube steam generator and the pressure of a pressure measuring point P1 at the outlet of the plunger are monitored; the pressure of the opening regulating loop of the electric regulating valve TF2 is continuously regulated to meet the working condition requirement; gradually increasing power to a heater of the spiral tube steam generator, gradually closing an electric regulating valve TF2 on a second bypass and simultaneously gradually opening an electric regulating valve TF3 after the outlet of the spiral tube steam generator reaches a superheated steam state by monitoring the temperature of a temperature measuring point T2 at the outlet of the spiral tube steam generator and the system pressure of a pressure measuring point P1, and allowing the superheated steam to enter a pressure container through the electric regulating valve TF3; monitoring a temperature measuring point T3 and a pressure measuring point P2, gradually opening the electric valve TF4 when the pressure in the pressure container reaches 1MPa, and keeping the temperature and the pressure in the pressure container stable by adjusting the opening degree of the electric valve TF4 after the temperature and the pressure in the pressure container rise to the requirements of working conditions; and then opening one of a valve group TF6, a valve group TF7, a valve group TF8, a valve group TF9 and a valve group TF10 according to the working condition requirement, then slowly opening the electric valve TF5, monitoring a Venturi flowmeter between the pressure container and the valve group, and continuously adjusting the opening degree of the electric valve TF5 to enable the flow to reach the working condition requirement.
12. The method of claim 11, wherein the open circuit pressure is in the range of 0.1-20MPa, and the spiral tube steam generator is heated to a maximum operating temperature of 350 ℃ in the open circuit.
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| CN202110564616.1A CN115389104A (en) | 2021-05-24 | 2021-05-24 | Steam leakage simulation test system and test method for main steam pipeline of power plant |
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2021
- 2021-05-24 CN CN202110564616.1A patent/CN115389104A/en active Pending
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