CN219841529U - Nuclear power unit economizer - Google Patents
Nuclear power unit economizer Download PDFInfo
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- CN219841529U CN219841529U CN202320428540.4U CN202320428540U CN219841529U CN 219841529 U CN219841529 U CN 219841529U CN 202320428540 U CN202320428540 U CN 202320428540U CN 219841529 U CN219841529 U CN 219841529U
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- 239000003638 chemical reducing agent Substances 0.000 claims abstract description 38
- 238000002955 isolation Methods 0.000 claims abstract description 23
- 230000009467 reduction Effects 0.000 claims abstract description 11
- 230000001105 regulatory effect Effects 0.000 claims description 21
- 230000006837 decompression Effects 0.000 claims description 7
- 230000000087 stabilizing effect Effects 0.000 claims description 6
- 238000004134 energy conservation Methods 0.000 abstract description 3
- 238000005265 energy consumption Methods 0.000 abstract 1
- 238000011084 recovery Methods 0.000 abstract 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 46
- 238000010438 heat treatment Methods 0.000 description 17
- 238000011010 flushing procedure Methods 0.000 description 6
- 238000000605 extraction Methods 0.000 description 5
- 239000000126 substance Substances 0.000 description 4
- 238000001514 detection method Methods 0.000 description 3
- 230000006872 improvement Effects 0.000 description 3
- 238000005507 spraying Methods 0.000 description 3
- 239000002699 waste material Substances 0.000 description 3
- 238000009423 ventilation Methods 0.000 description 2
- 238000004378 air conditioning Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
- 239000007921 spray Substances 0.000 description 1
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Abstract
The utility model relates to an energy-saving device of a nuclear power unit, and belongs to the field of energy conservation. The utility model discloses an energy-saving device, comprising: the device comprises a steam generator, a temperature and pressure reducer connected with a steam generator pipeline, a deaerator connected with the temperature and pressure reducer pipeline and an auxiliary steam header connected with the temperature and pressure reducer pipeline; and a steam isolation structure is arranged on a pipeline connected with the temperature and pressure reducer. The device can effectively reduce the emission of redundant main steam during starting and debugging through the bypass system, provide working medium recovery efficiency, greatly reduce the operation time of the auxiliary electric boiler, save operation cost and play a role in energy conservation and consumption reduction.
Description
Technical Field
The utility model relates to the field of energy conservation, in particular to an energy-saving device for a nuclear power unit.
Background
The nuclear power unit is different from a common conventional thermal power unit, various tests are required to be carried out during the starting and debugging of the unit, the starting and debugging period of the unit is long, the load of a steam turbine is lower than 20% for a long time, and an auxiliary steam source cannot be provided. If the auxiliary steam source is provided by the electric boiler for a long time, the operation cost is high, and the operation reliability of the auxiliary electric boiler system is also high.
The method for providing steam during the starting and debugging of the nuclear power unit by adopting the auxiliary electric boiler has the advantages that the starting and debugging period of the nuclear power unit is longer, a large amount of electric energy is consumed, the auxiliary electric boiler runs for a long time, and the service life and reliability requirements on equipment are higher.
During the cold start of the unit in the prior art, because sufficient steam cannot be generated in the initial stage of the unit, the heating pipe of the unit and the heating of the feed water are required, and therefore external steam is required to supply the heating pipe and the deaerator steam for the unit so as to preheat a pipeline and deaerate the feed water by heating. The newly-built nuclear power unit is generally provided with an electric boiler, and auxiliary steam and steam turbine shaft seal steam are provided for the cold start period of the unit. The auxiliary steam system mainly functions as follows:
(1) Providing deaerator starting and stopping steam: in the starting and stopping stages of the unit, an auxiliary steam system provides a stable steam source for constant-pressure operation of the deaerator through a pressure-stabilizing regulating valve so as to heat water supply and deaerate, improve the running efficiency of the unit and reduce the oxidation corrosion of pipelines and equipment;
(2) Heating general steam: ensuring main factory building heating, turbine room BOP heating, factory front area heating, nuclear island BOP heating and nuclear island heating air-conditioning system steam in a heating season;
(3) Steam is used by a three-waste system of the nuclear island;
(4) Chemical steam: when the hydraulic working water temperature of the desalted water treatment system is less than 15 ℃, the steam consumption of the chemical system is ensured so as to prepare desalted water required by the unit.
The auxiliary steam system is a common system of the whole plant, and the steam source can come from a second-stage steam extraction of the steam turbine and an auxiliary electric boiler. And in the unit starting operation stage, an auxiliary steam system steam source is from an auxiliary boiler. When the load of the turbine generally reaches more than 20%, and the second-stage extraction pressure of the turbine reaches 0.147 MPa (a), the heating steam source of the deaerator can be switched from auxiliary steam to the second-stage extraction of the turbine.
When the load of the unit is between 20% and 75%, the steam supply source is stripped by the steam users of the three wastes of the heating and ventilation system, the chemical steam users and the nuclear island through the auxiliary electric boiler.
When the unit load is more than 75%, the users of the heating and ventilation system, the chemical steam and the nuclear island three wastes use steam sources through the second-stage steam extraction and supply of the steam turbine, and at the moment, the second-stage steam extraction and supply of the steam to the electric isolation door of the auxiliary steam header is started, and the auxiliary boiler is stopped. The auxiliary boiler is in a hot standby state.
The auxiliary steam source is provided by the electric boiler for a long time, and because the electric boiler has higher power, if the electric boiler runs for a long time, the running cost is extremely high, the running cost of a nuclear power unit is about up to 5 tens of millions in a starting and debugging period of less than one month, and the auxiliary steam source is provided by the auxiliary boiler for a long time, so that higher requirements are provided for the running reliability of an auxiliary electric boiler system, once the electric boiler is stopped, the steam source cannot be provided, and the unit is stopped and equipment damage can be caused.
In order to solve the above problems, an energy saving device for a nuclear power unit needs to be designed.
Disclosure of Invention
The utility model aims to solve at least one technical problem in the background art and provides an energy-saving device of a nuclear power unit.
In order to achieve the aim, the utility model provides an energy-saving device of a nuclear power unit, which comprises a steam generator, a temperature and pressure reducer connected with a pipeline of the steam generator, a deaerator connected with the pipeline of the temperature and pressure reducer, and an auxiliary steam header connected with the pipeline of the temperature and pressure reducer;
and a steam isolation structure is arranged on a pipeline connected with the temperature and pressure reducer.
According to one aspect of the utility model, the steam isolation structure comprises a plurality of steam isolation valves, one ends of the steam isolation valves are connected with the steam generator through pipelines, and the other ends of the steam isolation valves are connected with the temperature and pressure reducers.
According to one aspect of the utility model, the desuperheater pressure reducer comprises: the system comprises a decompression system consisting of a decompression regulating valve and a noise reduction orifice plate, a safety valve and a temperature reduction system adopting a high-pressure difference constant-speed adjustable nozzle.
According to one aspect of the utility model, the device further comprises a pressure temperature detector connected with the temperature and pressure reducer pipeline.
According to one aspect of the utility model, the pressure temperature detector includes a redundantly configured pressure transmitter, pressure gauge, temperature sensing thermal resistor, and thermometer.
According to one aspect of the utility model, a plurality of control valves are arranged on a pipeline connecting the temperature and pressure reducing device and the deaerator, and the control valves comprise a steam regulating valve, an isolating valve and a pressure stabilizing regulating valve.
According to one aspect of the utility model, an auxiliary steam isolation valve is arranged on a pipeline connecting the temperature and pressure reducer and the auxiliary steam header.
According to one aspect of the utility model, a condenser is connected with the steam generator pipeline, and a control valve is arranged on the pipeline connected with the steam generator.
According to one aspect of the present utility model, further comprising: and the hydraulic cylinder is connected with the steam generator pipeline.
According to one aspect of the utility model, the hydraulic cylinder is a high pressure cylinder or a low pressure cylinder.
The utility model has the beneficial effects that:
(1) The device can effectively reduce redundant main steam during starting and debugging and improve the running efficiency of the nuclear power unit through the bypass system;
(2) The operation time of the auxiliary electric boiler is reduced to a great extent, and the operation cost is saved;
(3) Energy saving and consumption reduction.
Drawings
FIG. 1 schematically illustrates a block diagram of an energy saving device for a nuclear power unit in accordance with the present utility model;
FIG. 2 schematically illustrates a unit steam generator outlet and unit start-up curve according to the present utility model;
in the figure: 1. a steam generator; 2. a high-pressure cylinder; 3. a low pressure cylinder; 4. a temperature and pressure reducer; 5. a deaerator; 6. auxiliary steam header.
Detailed Description
The present disclosure will now be discussed with reference to exemplary embodiments. It should be understood that the embodiments discussed are merely to enable those of ordinary skill in the art to better understand and thus practice the teachings of the present utility model and do not imply any limitation on the scope of the utility model.
As used herein, the term "comprising" and variants thereof are to be interpreted as meaning "including but not limited to" open-ended terms. The term "based on" is to be interpreted as "based at least in part on". The terms "one embodiment" and "an embodiment" are to be interpreted as "at least one embodiment.
According to one embodiment of the utility model, a nuclear power unit energy saving device includes: the device comprises a steam generator 1, a temperature and pressure reducer 4 connected with the pipeline of the steam generator 1, a deaerator 5 connected with the pipeline of the temperature and pressure reducer 4 and an auxiliary steam header 6 connected with the pipeline of the temperature and pressure reducer 4;
a steam isolation structure is arranged on a pipeline connected with the temperature and pressure reducer 4 of the steam generator 1.
In this embodiment, as shown in fig. 1, the main steam source of the loop system is generated by the steam generator 1 system, the conventional island main water supply system transmits water with required pressure and flow to the steam generator 1 system, and the water level required by the steam generator 1 is maintained under the working conditions of hot standby, starting, running, stopping and the like of the re-unit. The water supply of the steam generator 1 during normal operation of the unit is provided by the main water supply system. In the initial stage of starting the unit, the water supply required by the steam generator 1 can be provided by a starting water supply system, the starting water supply system can maintain the water supply flow rate of the unit under about 10% of rated load at maximum, and when the unit load exceeds 10%, the water supply of the steam generator 1 is required to be automatically transited from the starting water supply system to the water supply system.
The main water supply and the starting water supply source are both from the deaerator 5, the heating steam source for the deaerator 5 water supply is from an auxiliary steam system, and the steam in the auxiliary steam header 6 is provided after passing through the pressure stabilizing regulating valve. In an initial stage, the steam source of the auxiliary steam system is provided by an auxiliary electric boiler system.
When the unit power is raised to a certain level, the high-pressure system is put into operation, and the main water supply system heats the main water supplied to the steam generator 1 through the high-pressure heater so as to obtain higher water supply temperature.
Along with the improvement of reactor power, the main steam flow of the two-loop system is continuously increased, various tests can be carried out on the unit during the period, the whole period is longer, and all generated steam is discharged to the condenser through the bypass system. When the main steam parameters reach a certain parameter, the steam turbine generator unit can be started to perform the flushing rotation, the grid connection and the initial load are realized, and the power is directly and gradually increased to the full load. During the period of the flushing, the grid connection and the initial load, except the steam entering the turbine for doing work, the redundant steam is discharged through a bypass system, the bypass system is gradually closed along with the improvement of the power of the turbine, at the moment, all the steam enters the turbine for doing work, and the bypass system is in an over-power protection state.
In another embodiment, as shown in fig. 2, the utility model is applied to a certain nuclear power engineering, the outlet of a certain unit steam generator 1 and the unit starting curve are shown in fig. 2, the rated parameter before the main steam generator of the unit is about 13.24MPa (a), the initial water supply flow, namely the main steam flow, is about 36kg/s, the steam required by the unit flushing is about 5.6kg/s, and the steam flow is about 16.2kg/s under the initial load. The steam parameters of the electric boiler are 1.25MPa (gauge pressure), 193.4 ℃ (35 t/h about 10 kg/s), and the curve and the corresponding parameters show that the steam quantity generated by the unit is far higher than required during the starting, flushing and loading of the unit, and the redundant steam is discharged to the condenser through the bypass system.
The whole starting and debugging period of the unit is about 70 days, for example, auxiliary steam is provided by an electric boiler, the initial overall cost is estimated to be about 1 hundred million yuan, and the energy-saving device is additionally arranged for reducing the operation cost.
When the main steam parameter is raised to 400 ℃ and the operation is stable, two main steam isolation valves can be opened, the system is put into, and after the main steam passes through a temperature and pressure reducing device, the temperature and pressure of the steam are reduced to 1.35MPa (a) and 200 ℃, and the steam is led to an auxiliary steam header 6 to provide an auxiliary steam source. When the equipment is running stably, the auxiliary electric boiler can be stopped, so that the electricity consumption of the auxiliary electric boiler is saved.
When the power of the nuclear power unit needs to be increased, the steam generator 1 needs to heat the water supply to more than 160 ℃, the steam generator is limited by the load of a steam turbine, the high-pressure operation still cannot be carried out, a device can be started to a pressure reducing loop of the deaerator 5, the pressure after valve adjustment is controlled to be about 0.63MPa (a), the steam parameter is far higher than the constant-pressure operation of the deaerator 5 in the initial stage, and the saturated water is arranged in the deaerator 5, so that the water supply temperature can be greatly increased without the need of the high-pressure operation.
The load of the random set is lifted, the bypass is gradually closed, and at the moment, the main steam system provides the steam turbine acting steam and the device starts to use the steam.
According to one embodiment of the utility model, the steam isolation structure comprises a plurality of steam isolation valves, one ends of which are connected with the steam generator 1 through pipelines, and the other ends of which are connected with the temperature and pressure reducer 4.
In this embodiment, one end of the steam isolation valve is connected to the main steam main pipe, and the other end is connected to the temperature and pressure reducer 4, and when the reactor power is raised to a certain level, the steam isolation valve can be opened manually to introduce the main steam to the temperature and pressure reducer 4. The steam isolation valve is configured, so that the energy-saving device can be completely isolated from main steam, and the operation safety is ensured.
According to one embodiment of the utility model, the temperature-reducing and pressure-reducing device 4 comprises: the system comprises a decompression system consisting of a decompression regulating valve and a noise reduction orifice plate, a safety valve and a temperature reduction system adopting a high-pressure difference constant-speed adjustable nozzle.
In the present embodiment, the temperature and pressure reducer 4 may include a pressure reducing system, a safety valve, a temperature reducing system. The pressure reducing system comprises a pressure reducing regulating valve and a noise reducing orifice plate; the setting pressure of the safety valve is generally 1.08-1.1 times of the pressure of the secondary steam, when the operating pressure exceeds the allowable value, the safety valve automatically acts to remove all steam with rated flow, so that the safety of equipment is ensured; the temperature reducing system adopts a high pressure difference constant speed adjustable nozzle. The adjustable nozzle can change the spraying amount of the desuperheating water by changing the spraying area of the desuperheating water. The water sprayed by the temperature-reducing and pressure-reducing device 4 is led to the existing condensate system.
According to one embodiment of the utility model, a pressure temperature detector is also included in line connection with the temperature and pressure reducer 4.
In this embodiment, the temperature and pressure reducer 4 may further include a pressure and temperature detector connected to the temperature and pressure reducer 4 through a pipeline. The main steam firstly completes decompression in the temperature and pressure reducing device, and then completes temperature reduction; the pressure temperature detector is used for adjusting the opening of the temperature and pressure reducing device pressure reducing regulating valve to obtain the required steam pressure, and the temperature detector is used for adjusting the opening of the temperature and pressure reducing device temperature and pressure reducing regulating valve to adjust the temperature and water spraying flow.
According to one embodiment of the utility model, the pressure temperature detector includes a redundant configuration of a pressure transmitter, a pressure gauge, a temperature sensing thermal resistor, and a thermometer.
In this embodiment, the temperature and pressure reducer 4 may further include a pressure transmitter and a temperature detection resistor which are configured redundantly, and are installed on a pipe greater than 2 meters behind the temperature and pressure reducer to ensure accuracy of detection parameters. The main steam is decompressed in the temperature and pressure reducing device, and then the temperature reduction is finished. According to the redundant pressure transmitter signals, the opening degree of the pressure reducing and reducing device pressure reducing and regulating valve is regulated to obtain the required steam pressure, and the pressure set value can be calculated according to the design pressure parameters of the existing auxiliary steam system and by considering partial pipeline pressure drop. According to the set temperature detection thermal resistance, the opening of a temperature-reducing and pressure-reducing device temperature-reducing regulating valve is regulated to regulate the temperature-reducing water spray flow, and the temperature set value can be set according to the design temperature parameters of the existing auxiliary steam system.
According to one embodiment of the utility model, a plurality of control valves are arranged on a pipeline connecting the temperature and pressure reducer 4 and the deaerator 5, and the control valves comprise a steam regulating valve, an isolation valve and a pressure stabilizing regulating valve.
In the embodiment, a plurality of control valves are arranged on a pipeline connecting the temperature and pressure reducer 4 and the deaerator 5, and each control valve comprises a steam regulating valve, an isolating valve and a pressure stabilizing regulating valve; the steam is led to an auxiliary steam isolating valve and a corresponding pipeline, and the valve and the pipeline are used for leading the steam which accords with auxiliary steam parameters to an auxiliary steam header 6 after temperature and pressure reduction, thereby providing steam for a deaerator 5, a shaft seal, a heating pipe and the like. The pipe connection can be directly opened in the auxiliary steam header 6 alone or can be connected to the steam pipe originally led from the auxiliary electric boiler by three-way connection.
According to one embodiment of the utility model, an auxiliary steam isolation valve is provided on the line connecting the desuperheater pressure reducer 4 and the auxiliary steam header 6.
In the embodiment, an auxiliary steam isolation valve is arranged on a pipeline connecting the temperature and pressure reducer 4 and the auxiliary steam header 6; the water supply of the steam generator 1 during normal operation of the nuclear power unit is provided by a main water supply system. In the initial stage of starting the unit, the water supply required by the steam generator 1 can be provided by a starting water supply system or a main water supply system, the starting water supply system can only maintain the water supply flow rate of the unit under about 10% of rated load at maximum, and when the unit load exceeds 10%, the water supply of the steam generator 1 is required to be automatically transited from the starting water supply system to the main water supply system.
The main water supply and the starting water supply source are both from the deaerator 5, the heating steam source for the deaerator 5 water supply is from the auxiliary steam system, the auxiliary steam isolation valve is opened, and the steam in the auxiliary steam header 6 is provided after passing through the pressure stabilizing regulating valve. In an initial stage, the steam source of the auxiliary steam system is provided by an auxiliary electric boiler system.
According to one embodiment of the utility model, a condenser is connected with a pipeline of the steam generator 1, and a control valve is arranged on the pipeline of the condenser connected with the steam generator 1.
In this embodiment, with the increase of the reactor power, the main steam flow of the two-loop system is continuously increased, during which the nuclear power unit can perform various tests, and the overall period is longer, and the control valve arranged on the pipeline of the steam generator 1 is opened, so that all the generated steam is discharged to the condenser by the bypass system. When the main steam parameters reach a certain parameter, the steam turbine generator unit can be started to perform the flushing rotation, the grid connection and the initial load are realized, and the power is directly and gradually increased to the full load. During the period of the flushing, the grid connection and the initial load, except the steam entering the turbine for doing work, the redundant steam is discharged through a bypass system, the bypass system is gradually closed along with the improvement of the power of the turbine, at the moment, all the steam enters the turbine for doing work, and the bypass system is in an over-power protection state.
According to one embodiment of the present utility model, further comprising: and a hydraulic cylinder connected with the pipeline of the steam generator 1.
In the embodiment, the hydraulic cylinder can dispense with a speed reducer, has no transmission gap, moves stably, saves cost and ensures the running safety of the nuclear power unit.
According to one embodiment of the utility model, the hydraulic cylinder is either a high pressure cylinder 2 or a low pressure cylinder 3.
In the present embodiment, the high pressure cylinder 2 or the low pressure cylinder 3 is provided to separate the steam from the atmosphere. The low-pressure cylinder 3 can well balance axial thrust, the pressure of steam discharged by the low-pressure cylinder 3 is very low, and the low-pressure cylinder can be directly connected with a condenser.
Finally, it is noted that the above-mentioned preferred embodiments are only intended to illustrate rather than limit the utility model, and that, although the utility model has been described in detail by means of the above-mentioned preferred embodiments, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the scope of the utility model as defined by the appended claims.
Claims (10)
1. An energy saving device for a nuclear power unit, comprising: the device comprises a steam generator, a temperature and pressure reducer connected with a steam generator pipeline, a deaerator connected with the temperature and pressure reducer pipeline and an auxiliary steam header connected with the temperature and pressure reducer pipeline;
and a steam isolation structure is arranged on a pipeline connected with the temperature and pressure reducer.
2. The nuclear power unit economizer of claim 1 wherein the vapor isolation structure includes a plurality of vapor isolation valves having one end connected to the vapor generator and the other end connected to the temperature and pressure reducer.
3. The nuclear power unit economizer of claim 1 wherein the temperature and pressure reducer comprises: the system comprises a decompression system consisting of a decompression regulating valve and a noise reduction orifice plate, a safety valve and a temperature reduction system adopting a high-pressure difference constant-speed adjustable nozzle.
4. The nuclear power unit economizer of claim 1 further comprising a pressure temperature detector connected to the reduced temperature and pressure vessel line.
5. The nuclear power unit economizer of claim 4 wherein the pressure and temperature detector comprises a redundant configuration of pressure transmitters, pressure gauges, temperature sensing thermal resistors and thermometers.
6. The energy saving device of a nuclear power unit according to claim 1, wherein a plurality of control valves are arranged on a pipeline connecting the temperature and pressure reducing device and the deaerator, and the control valves comprise a steam regulating valve, an isolating valve and a pressure stabilizing regulating valve.
7. The energy saving device of a nuclear power unit according to claim 1, wherein an auxiliary steam isolation valve is arranged on a pipeline connecting the temperature and pressure reducer and the auxiliary steam header.
8. The nuclear power unit economizer of claim 1 further comprising: and the condenser is connected with the steam generator pipeline, and a control valve is arranged on the pipeline connected with the steam generator.
9. The nuclear power unit economizer of any one of claims 1-8 further comprising: and the hydraulic cylinder is connected with the steam generator pipeline.
10. The nuclear power unit economizer of claim 9 further comprising: the hydraulic cylinder is a high-pressure cylinder or a low-pressure cylinder.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202320428540.4U CN219841529U (en) | 2023-03-01 | 2023-03-01 | Nuclear power unit economizer |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202320428540.4U CN219841529U (en) | 2023-03-01 | 2023-03-01 | Nuclear power unit economizer |
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| Publication Number | Publication Date |
|---|---|
| CN219841529U true CN219841529U (en) | 2023-10-17 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202320428540.4U Active CN219841529U (en) | 2023-03-01 | 2023-03-01 | Nuclear power unit economizer |
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| Country | Link |
|---|---|
| CN (1) | CN219841529U (en) |
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2023
- 2023-03-01 CN CN202320428540.4U patent/CN219841529U/en active Active
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