CN211370762U - Reactor coolant pump whole-plant outage accident working condition test system - Google Patents
Reactor coolant pump whole-plant outage accident working condition test system Download PDFInfo
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- CN211370762U CN211370762U CN201922309267.XU CN201922309267U CN211370762U CN 211370762 U CN211370762 U CN 211370762U CN 201922309267 U CN201922309267 U CN 201922309267U CN 211370762 U CN211370762 U CN 211370762U
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Abstract
The utility model relates to a reactor coolant pump outage accident operating mode test system of whole factory, driving motor 1 is located test device 2, driving motor 1 passes through the shaft coupling and is connected with test device 2's test rotor, tertiary fluid dynamic pressure is sealed to be the same and establish ties water lubrication fluid dynamic pressure mechanical seal 10 of being in the same place by tertiary structure and constitutes, the rotating ring is installed on the rotor, quiet ring is installed on the guide ring, 2 inner chambers of test device are installed to tertiary fluid dynamic pressure is sealed to adopt the cylindric lock, high pressure cooler system 8 is connected with test device 2 through the injected water pipeline. The utility model discloses the outage operating mode of complete simulation nuclear power station whole plant, tertiary fluid dynamic pressure mechanical seal independently bear the impact of high temperature, highly compressed a return circuit cooling water, can verify static seal durability, have guaranteed the credibility of experimental conclusion.
Description
The technical field is as follows:
the utility model relates to a reactor coolant pump outage accident operating mode test system of whole factory.
Background art:
the existing reactor coolant pump sealing test only carries out a single-stage sealing performance delivery test, a whole test loop system adopts high pressure and room temperature design, the system pressure and the injection water flow rate are controlled by adjusting a plunger pump, an injection water heating system is not arranged, a test device (2) is a mechanical assembly for installing a sealing system, the test device (2) can test a complete reactor coolant pump shaft sealing system, and a cavity body can only be provided with a one-stage mechanical seal for carrying out a functional test. Under the working condition of a power failure accident of a whole plant, the mechanical seal of the main pump is required to maintain the structural integrity within 72 hours, and the leakage of a coolant cannot be generated, so that the existing test device cannot meet the new technical requirements of nuclear power design, and the integrity requirements of the three-stage seal under the high-temperature and high-pressure working condition and the high-temperature resistance requirements of static seal cannot be verified before a unit is in service.
The invention content is as follows:
the utility model aims at disclosing a reactor coolant pump outage accident operating mode test system of whole factory that the reliability is high, the maintenance cost is low, convenient to use. The technical scheme of the utility model is that: the utility model provides a reactor coolant pump outage accident operating mode test system of whole factory which characterized by: the driving motor (1) is positioned on the testing device (2), the driving motor (1) is connected with a testing rotor of the testing device (2) through a coupler, a three-stage fluid dynamic pressure seal is composed of water lubrication fluid dynamic pressure mechanical seals (10) which have the same three-stage structure and are connected in series, a movable ring is installed on the rotor, a static ring is installed on a guide ring, the three-stage fluid dynamic pressure seal is installed in the inner cavity of the testing device (2) through a cylindrical pin, a high-pressure cooler system (8) is connected with the testing device (2) through a water injection pipeline, an electric heater system (3) is connected with the testing device (2) through the water injection pipeline to form a primary side loop (11) of the testing system, a filtering device (6) is an independent device and is connected with a water storage system (4) loop through a pipeline and a flange to form a water supply system of the testing device, a low-temperature cooler (7) is connected with a, the cooling water tank (5) is connected with the water storage system (4) through a pipeline to form a cooling loop; the motor bearing cooling pipe and the water storage system (4) form a closed cooling loop through a cooling water pipeline (13); the bearing oil supply system (9) is connected with a motor bearing chamber through an oil supply pipeline (14) to form a bearing oil supply loop.
The utility model discloses the theory of operation:
the test rig is a mechanical assembly for mounting the sealing system. The testing device can test a complete reactor coolant pump shaft sealing system, and the system comprises a three-stage hydrodynamic mechanical sealing system, a leakage system and a shutdown sealing system. The test device is provided with deionized water equipment, and the treated test water is stored in a water storage tank for test. And the test medium in the water storage tank enters the sealing system to be tested after passing through the filter. The test unit has two independent water injection circuits, namely a cold water circuit and a hot water circuit. The cold water circuit is connected directly to the test unit. The hot water circuit is heated in two steps, firstly, the heat exchanger preheats the test water by using the hot water of the leakage system of the test device, and then the test water is heated to the required temperature by the electric heater between the heat exchanger and the sealed system to be tested. The test water returns to the water storage tank through a sealing system to be tested (a leakage pipeline, balance sealing leakage, pressurization bypass and low-pressure sealing leakage), hot water in the leakage pipeline and the pressurization bypass must be cooled and then returns to the water storage tank, the hot water is firstly cooled through a heat exchanger for preheating the test water and then is cooled through another heat exchanger by using tap water, and the second heat exchanger can cool steam to liquid water. And lubricating a rolling bearing at the upper part of the sealing system to be tested by an oil supply system. A heat exchanger is arranged in the water storage tank, the heat exchanger continuously supplies cooling water to ensure that the temperature of the water in the water storage tank is constant, and the cooling capacity is realized by adjusting the amount of the cooling water. The shutdown sealing system was shut down by nitrogen pressure supply. All electrical equipment required to operate and control the test rig is located in the four control cabinets and data can be collected, recorded, analyzed and displayed during the test run.
The utility model has the advantages that:
(1) at present conventional seal test device does not possess hot working condition, the utility model discloses increased heating device to and temperature control device, the outage operating mode of complete simulation nuclear power station whole factory, tertiary fluid dynamic pressure mechanical seal independently bears the impact of high temperature, highly compressed a return circuit cooling water.
(2) The utility model discloses a temperature control device who sets up can guarantee that the system keeps high temperature, high pressure operating mode 72h or longer time, can verify static seal durability, has guaranteed the credibility of experimental conclusion.
(3) The test device is a nuclear main pump whole-plant power-off working condition test which is carried out for the first time in China, verifies the resistance of the shaft seal type nuclear main pump in China, and provides complete data support for the redundancy of a main pump unit under the whole-plant power-off accident working condition.
Drawings
FIG. 1 is a system diagram of a reactor coolant pump plant blackout accident condition testing system
Detailed Description
As shown in figure 1, a reactor coolant pump plant blackout accident working condition test system, a driving motor 1 is positioned on a test device 2, the driving motor 1 is connected with a test rotor of the test device 2 through a coupler, a three-stage fluid dynamic pressure seal is composed of water lubrication fluid dynamic pressure mechanical seals 10 which have the same three-stage structure and are connected in series, a moving ring is installed on the rotor, a static ring is installed on a guide ring, the three-stage fluid dynamic pressure seal is installed in an inner cavity of the test device 2 through a cylindrical pin, a high-pressure cooler system 8 is connected with the test device 2 through a water injection pipeline, an electric heater system 3 is connected with the test device 2 through the water injection pipeline to form a primary side loop 11 of the test system, a filter device 6 is an independent device and is connected with a water storage system 4 loop through a pipeline and a flange to form a water supply system of the test device, a low-temperature cooler 7 is, the cooling water tank 5 is connected with the water storage system 4 through a pipeline to form a cooling loop; the motor bearing cooling pipe and the water storage system 4 form a closed cooling loop through a cooling water pipeline 13; the bearing oil supply system 9 is connected with a motor bearing chamber through an oil supply pipeline 14 to form a bearing oil supply loop.
The test rig is a mechanical assembly for mounting the sealing system. The testing device can test a complete reactor coolant pump shaft sealing system, and the system comprises a three-stage hydrodynamic mechanical sealing system, a leakage system and a shutdown sealing system. The test device is provided with deionized water equipment, and the treated test water is stored in a water storage tank for test. And the test medium in the water storage tank enters the sealing system to be tested after passing through the filter. The test unit has two independent water injection circuits, namely a cold water circuit and a hot water circuit. The cold water circuit is connected directly to the test unit. The hot water circuit is heated in two steps, firstly, the heat exchanger preheats the test water by using the hot water of the leakage system of the test device, and then the test water is heated to the required temperature by the electric heater between the heat exchanger and the sealed system to be tested. The test water returns to the water storage tank through a sealing system to be tested (a leakage pipeline, balance sealing leakage, pressurization bypass and low-pressure sealing leakage), hot water in the leakage pipeline and the pressurization bypass must be cooled and then returns to the water storage tank, the hot water is firstly cooled through a heat exchanger for preheating the test water and then is cooled through another heat exchanger by using tap water, and the second heat exchanger can cool steam to liquid water. And lubricating a rolling bearing at the upper part of the sealing system to be tested by an oil supply system. A heat exchanger is arranged in the water storage tank, the heat exchanger continuously supplies cooling water to ensure that the temperature of the water in the water storage tank is constant, and the cooling capacity is realized by adjusting the amount of the cooling water. The shutdown sealing system was shut down by nitrogen pressure supply. All electrical equipment required to operate and control the test rig is located in the four control cabinets and data can be collected, recorded, analyzed and displayed during the test run.
The test is divided into three stages: an initial phase, a test phase and an evaluation phase.
The following data were tested during the plant blackout test:
● System pressure (P1)
● System temperature (T1)
● axle speed
● axial displacement
● sealed water injection
Sealing injection water pressure (P1)
Sealing injection water temperature (T1)
Sealed injection water flow (Q1)
● high pressure leakage pressure (P-HD)
High pressure leakage temperature (T-HD)
High pressure leakage flow (Q-HD)
● low pressure leakage
Low pressure leakage temperature (T-ND)
Low pressure leakage flow (Q-ND)
● shaft seal
Pressure between first and second seals (P2)
Temperature between first and second stage seals (T2)
Pressure between second and third stage seals (P3)
Temperature between second and third stage seals (T3)
Claims (1)
1. The utility model provides a reactor coolant pump outage accident operating mode test system of whole factory which characterized by: the driving motor (1) is positioned on the testing device (2), the driving motor (1) is connected with a testing rotor of the testing device (2) through a coupler, a three-stage fluid dynamic pressure seal is composed of water lubrication fluid dynamic pressure mechanical seals (10) which have the same three-stage structure and are connected in series, a movable ring is installed on the rotor, a static ring is installed on a guide ring, the three-stage fluid dynamic pressure seal is installed in the inner cavity of the testing device (2) through a cylindrical pin, a high-pressure cooler system (8) is connected with the testing device (2) through a water injection pipeline, an electric heater system (3) is connected with the testing device (2) through the water injection pipeline to form a primary side loop (11) of the testing system, a filtering device (6) is an independent device and is connected with a water storage system (4) loop through a pipeline and a flange to form a water supply system of the testing device, a low-temperature cooler (7) is connected with a, the cooling water tank (5) is connected with the water storage system (4) through a pipeline to form a cooling loop; the motor bearing cooling pipe and the water storage system (4) form a closed cooling loop through a cooling water pipeline (13); the bearing oil supply system (9) is connected with a motor bearing chamber through an oil supply pipeline (14) to form a bearing oil supply loop.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201922309267.XU CN211370762U (en) | 2019-12-20 | 2019-12-20 | Reactor coolant pump whole-plant outage accident working condition test system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201922309267.XU CN211370762U (en) | 2019-12-20 | 2019-12-20 | Reactor coolant pump whole-plant outage accident working condition test system |
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| Publication Number | Publication Date |
|---|---|
| CN211370762U true CN211370762U (en) | 2020-08-28 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201922309267.XU Active CN211370762U (en) | 2019-12-20 | 2019-12-20 | Reactor coolant pump whole-plant outage accident working condition test system |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111306075A (en) * | 2019-12-20 | 2020-06-19 | 哈尔滨电气动力装备有限公司 | Reactor coolant pump whole-plant outage accident working condition test system |
-
2019
- 2019-12-20 CN CN201922309267.XU patent/CN211370762U/en active Active
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111306075A (en) * | 2019-12-20 | 2020-06-19 | 哈尔滨电气动力装备有限公司 | Reactor coolant pump whole-plant outage accident working condition test system |
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