CN111271603A - Nuclear power station valve diaphragm maintenance method - Google Patents
Nuclear power station valve diaphragm maintenance method Download PDFInfo
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- CN111271603A CN111271603A CN202010053750.0A CN202010053750A CN111271603A CN 111271603 A CN111271603 A CN 111271603A CN 202010053750 A CN202010053750 A CN 202010053750A CN 111271603 A CN111271603 A CN 111271603A
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F17—STORING OR DISTRIBUTING GASES OR LIQUIDS
- F17D—PIPE-LINE SYSTEMS; PIPE-LINES
- F17D1/00—Pipe-line systems
- F17D1/08—Pipe-line systems for liquids or viscous products
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F17—STORING OR DISTRIBUTING GASES OR LIQUIDS
- F17D—PIPE-LINE SYSTEMS; PIPE-LINES
- F17D1/00—Pipe-line systems
- F17D1/08—Pipe-line systems for liquids or viscous products
- F17D1/14—Conveying liquids or viscous products by pumping
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/04—Pumping arrangements
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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
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Abstract
The invention relates to the field of nuclear auxiliary cooling water systems of nuclear power plants, and discloses a nuclear power plant valve diaphragm maintenance method which comprises the steps of isolating a pipeline area to be maintained of a nuclear power plant, wherein the pipeline area to be maintained comprises a main pipeline, a plurality of branch pipelines and working point pipelines, the branch pipelines are communicated with the main pipeline, the working point pipelines are communicated with the main pipeline, and working point valves are arranged on the working point pipelines; opening a working point valve, and judging whether the water yield of the working point valve is less than a preset water yield threshold value or not; and if the water yield of the valve at the working point is less than the preset water yield threshold value, maintaining the valve diaphragm of the specified valve in the pipeline area to be maintained according to a preset maintenance program. The method provided by the invention realizes the drainage-free maintenance of the valve in the pipeline area to be maintained, greatly improves the working efficiency of maintenance, reduces the working time of maintenance, and simultaneously can improve the function recovery capability of an equipment cooling water system and improve the reliability of a cold source of a spent fuel pool in an emergency.
Description
Technical Field
The invention belongs to the technical field of nuclear auxiliary cooling water systems of nuclear power plants, and particularly relates to a method for maintaining a valve diaphragm of a nuclear power plant.
Background
In order to ensure safe and efficient operation of the nuclear power plant, the valve diaphragms of the nuclear power plant need to be overhauled at intervals. The valve diaphragms are mainly arranged in branch pipelines of a cooling water system of unit equipment of the nuclear power station. These branch pipes are connected to the main pipe.
In the prior art, when the instrument equipment of the nuclear power station is overhauled, a valve on a main pipeline needs to be closed, fluid in the pipeline is emptied, and then a valve diaphragm is maintained. However, since the branch pipes of the nuclear power plant connected to the main pipe are complicated in arrangement and the pipes are long, the evacuation takes a long time. After maintenance, a lot of time is consumed for filling water and exhausting air to the branch pipelines.
In actual operationIn the process, the equipment cooling water head tank is used for replenishing water to the branch pipelines. The water replenishing capacity of the equipment cooling water head tank is only 20m3And because the butterfly valve is difficult to control when water is filled, the liquid level of the equipment cooling water head tank is low due to the fact that the butterfly valve is difficult to control, and the operation of an equipment cooling water system is influenced.
In addition, during the maintenance period, the cooling of the spent fuel pool is provided by the cooling water system of the adjacent unit, and once the cooling of the cooling water system of the adjacent unit is lost, the time consumed for recovering the cooling water system of the unit equipment to provide cooling for cooling the spent fuel pool is longer, so that the water temperature of the spent fuel pool is easily over 50 ℃, and the normal operation of the spent fuel pool is influenced.
Disclosure of Invention
The invention aims to provide a method for maintaining a valve diaphragm of a nuclear power station, which aims to solve the technical problem that the valve diaphragm in the prior art is too long in maintenance time.
In order to achieve the purpose, the invention adopts the technical scheme that: the maintenance method of the valve diaphragm of the nuclear power station comprises the following steps:
isolating a pipeline area to be maintained of a nuclear power station, wherein the pipeline area to be maintained comprises a main pipeline, a plurality of branch pipelines and working point pipelines, the branch pipelines are communicated with the main pipeline, the working point pipelines are communicated with the main pipeline, and working point valves are arranged on the working point pipelines;
opening the working point valve, and judging whether the water yield of the working point valve is less than a preset water yield threshold value or not;
and if the water yield of the valve at the working point is less than a preset water yield threshold value, maintaining the valve diaphragm of the specified valve in the pipeline area to be maintained according to a preset maintenance program.
Optionally, after opening the operating point valve and determining whether the water yield of the operating point valve is less than a preset water yield threshold, the method further includes:
if the water yield of the working point valve is greater than or equal to a preset water yield threshold value, connecting a compressed air output device with the working point pipeline, and closing the working point valve;
and opening a designated branch valve on the branch pipeline, and delivering compressed air to the working point pipeline through the compressed air output device so as to discharge and reduce the water quantity in the pipeline area to be maintained through the designated branch valve.
Optionally, after the opening of the specified branch valve on the branch pipeline and the delivery of the compressed air to the working point pipeline through the compressed air output device to discharge and reduce the amount of water in the pipeline region to be maintained through the specified branch valve, the method further includes:
when the specified branch valve does not discharge water, the working point valve is opened, and whether the water yield of the working point valve is smaller than a preset water yield threshold value or not is judged;
and if the water yield of the working point valve is less than a preset water yield threshold value, reducing the pressure of the working point pipeline to normal pressure, and then maintaining the valve diaphragm of the specified valve in the pipeline area to be maintained according to the preset maintenance program.
Optionally, when the specified branch valve does not discharge water, the operating point valve is opened, and whether the water yield of the operating point valve is less than a preset water yield threshold value is determined, the method further includes:
if the water yield of operating point valve is greater than or equal to and predetermines the water yield threshold value, then open appointed branch road valve makes through the action of gravity water in waiting to maintain the pipeline region passes through the operating point valve is discharged, the elevation of operating point valve is less than the elevation of appointed branch road valve.
Optionally, before isolating the pipe area to be maintained, the method further includes:
closing connecting valves of the pipeline area to be maintained and an external pipeline, and closing connecting valves of branch pipelines except the branch pipeline provided with the emptying valve and the main pipeline;
opening the emptying valve, and judging whether water is discharged from the emptying valve;
and when the drain valve does not drain water, judging that the pipeline area to be maintained is isolated.
Optionally, after the opening the evacuation valve and determining whether the evacuation valve has water to be discharged, the method further includes:
if the emptying valve has water to discharge, the emptying valve is closed firstly, and then a connecting valve of the branch pipeline provided with the emptying valve and the main pipeline is closed;
opening the evacuation valve to determine the position of the connecting valve which does not produce the isolation effect;
after the position of the connection valve without isolation is determined, the connection valve without isolation is adjusted to enable the connection valve without isolation to generate isolation.
Optionally, after the valve diaphragm of the specified valve in the pipeline region to be maintained is maintained according to a preset maintenance program, the method further includes:
after the valve diaphragm is maintained, filling water into the branch pipeline from the pipeline where the specified branch valve is located;
and gradually restoring the connection between the pipeline area to be maintained and the pipeline outside the pipeline area to be maintained according to a preset commissioning procedure.
Optionally, if the water yield of the working point valve is less than a preset water yield threshold, reducing the pressure of the working point pipeline to normal pressure, and then maintaining the valve diaphragm of the specified valve in the pipeline region to be maintained according to the preset maintenance program, further including:
after the valve diaphragm is maintained, filling water into the working point pipeline through the working point valve and the specified branch valve;
and gradually restoring the connection between the pipeline area to be maintained and the pipeline outside the pipeline area to be maintained according to a preset commissioning procedure.
Optionally, if the fuel water pool connected to the pipeline area to be maintained loses cooling of the unit system, filling water into the pipeline of the working point through the valve of the working point and the valve of the specified branch;
and gradually restoring the connection between the pipeline area to be maintained and the pipeline outside the pipeline area to be maintained according to a preset commissioning procedure.
Optionally, the lateral includes a first lateral, the first lateral is connected with a first reactor coolant pool, the first lateral is further provided with a first reactor coolant main pump, the first reactor coolant main pump set up in the first reactor coolant pool with between the trunk line.
Optionally, the lateral conduit still includes the second lateral conduit, the second lateral conduit is connected with second reactor cooling pond, the second lateral conduit still is provided with reactor coolant second main pump, reactor coolant second main pump set up in the second reactor cooling pond with between the trunk line.
Optionally, the branch pipeline further comprises a third branch pipeline, the third branch pipeline is connected with a third reactor cooling pool, the third branch pipeline is further provided with a third reactor coolant main pump, and the third reactor coolant main pump is arranged between the third reactor cooling pool and the main pipeline.
Optionally, the branch pipeline further comprises a fourth branch pipeline, a first sub-branch and a second sub-branch are arranged on the fourth branch pipeline, the first sub-branch is provided with a reactor coolant pressure relief tank and a pressure relief pump, and the second sub-branch is provided with an excess downward-relief heat exchanger and a heat relief pump.
Optionally, the branch pipeline still includes the fifth branch pipeline, the fifth branch pipeline is connected with air-cooled system heat exchanger, the fifth branch pipeline still is provided with the heat transfer heat exchange pump, the heat transfer heat exchange pump set up in air-cooled system heat exchanger with between the trunk line.
Optionally, the branch pipeline further includes a sixth branch pipeline, the sixth branch pipeline is connected with the refrigerating unit and the heat exchanger of the blowdown system, the sixth branch pipeline is further provided with a blowdown heat exchange pump, and the blowdown heat exchange pump is arranged between the heat exchanger of the blowdown system and the main pipeline.
The method for maintaining the valve diaphragm of the nuclear power station has the advantages that: compared with the prior art, the method for maintaining the valve diaphragm of the nuclear power station realizes the drainage-free maintenance of the valve in the pipeline area to be maintained by isolating the pipeline area to be maintained, namely, the replacement of the valve diaphragm is completed, so that the working efficiency of the maintenance is greatly improved, the working time of the maintenance is reduced, and meanwhile, the function recovery capability of an equipment cooling water system can be improved and the reliability of a cold source of a spent fuel pool can be improved in an emergency.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings needed to be used in the embodiments or the prior art descriptions will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without inventive exercise.
Fig. 1 is a schematic structural diagram of a pipe region to be maintained according to an embodiment of the present invention.
Detailed Description
In order to make the technical problems, technical solutions and advantageous effects to be solved by the present invention more clearly apparent, the present invention is further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
It will be understood that when an element is referred to as being "secured to" or "disposed on" another element, it can be directly on the other element or be indirectly on the other element. When an element is referred to as being "connected to" another element, it can be directly connected to the other element or be indirectly connected to the other element.
It will be understood that the terms "length," "width," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," and the like, as used herein, refer to an orientation or positional relationship indicated in the drawings that is solely for the purpose of facilitating the description and simplifying the description, and do not indicate or imply that the device or element being referred to must have a particular orientation, be constructed and operated in a particular orientation, and is therefore not to be construed as limiting the invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of that feature. In the description of the present invention, "a plurality" means two or more unless specifically defined otherwise.
Referring to fig. 1, a method for maintaining a valve diaphragm of a nuclear power plant according to the present invention will now be described. The maintenance method of the nuclear power station valve diaphragm comprises the following steps:
isolating a pipeline area to be maintained of a nuclear power station, wherein the pipeline area to be maintained comprises a main pipeline, a plurality of branch pipelines and working point pipelines, the branch pipelines are communicated with the main pipeline, the working point pipelines are communicated with the main pipeline, and working point valves 005 are arranged on the working point pipelines;
opening the working point valve 005 and judging whether the water yield of the working point valve 005 is less than a preset water yield threshold value or not;
and if the water yield of the valve 005 at the working point is less than the preset water yield threshold value, maintaining the valve diaphragm of the specified valve in the pipeline area to be maintained according to a preset maintenance program.
In this embodiment, the pipeline region to be maintained includes a main pipeline, a plurality of branch pipelines, and a working point pipeline. The main pipeline is provided with a valve 001, a valve 002, a valve 003 and a valve 004, and when the four valves are closed, the pipeline area to be maintained of the nuclear power station is isolated from an external pipeline. A working point valve 005 is provided on the working point pipeline connected to the main pipeline. Here, the pipe diameter of the main pipeline is more than 10 times larger than that of the pipeline at the working point. For example, the diameter of the main pipe is large, which can be 355.6 mm; the pipe diameter of the working point pipeline is far smaller than that of the main pipeline and can be 21.3 mm. In one example, the level of the working point valve 005 (relative to the building) is-6.7 m, the level of the major part of the main pipe is 0m, and the highest level of the main pipe is 11.5m (but the length of the main pipe at the highest end is smaller).
When the pipe area to be maintained of the nuclear power plant is isolated from the external pipe, some of the valves in the branch pipes may also be in a closed state, such as the valves 101 and 102 in the first branch pipe, the valves 201 and 202 in the second branch pipe, the valves 301 and 302 in the third branch pipe, the valves 401 and 402 in the fourth branch pipe, and the valves 501 and 502 in the fifth branch pipe.
Because the pipe diameter of the main pipe is far greater than the pipe diameter of the working point pipeline, when a valve (such as the working point valve 005) of the working point pipeline in the pipeline area to be maintained or a valve (not shown) on a small pipe diameter on the branch pipeline is maintained under the action of atmospheric pressure, only a small part of water in the main pipe flows out from the opened valve, and the majority of water still remains in the main pipe. Therefore, scheduled maintenance work can be completed without draining water in the main pipeline, the maintenance time of the nuclear power station valve diaphragm is greatly shortened, and meanwhile, when the function of the pipeline area to be maintained is recovered (namely, the pipeline of the pipeline area to be maintained is communicated with an external pipeline), the recovery time is also greatly shortened. During the overhaul period, if the spent fuel pool loses the cooling of the adjacent unit equipment, the cooling water supply of the unit equipment can be quickly recovered, so that the spent fuel pool can be quickly cooled, and the reliability of a cold source of the spent fuel pool is greatly improved.
It should be noted that when the isolation of the pipe area to be maintained is good, the water output of the operating point valve 005 is small. The preset water outlet threshold value can be set according to actual needs. In some cases, the preset water out threshold may be a time threshold. For example, after the operating point valve 005 is opened, if no water flows out from the operating point valve 005 after one minute, it can be determined that the water output of the operating point valve 005 is less than the preset water output threshold. When the water yield of the working point valve 005 is less than the preset water yield threshold, the valve diaphragm of the designated valve in the pipeline area to be maintained can be maintained according to the preset maintenance program. Here, the designated valve may be a valve of a working point line (e.g., working point valve 005), or a valve on a small pipe diameter of a branch line (not shown). The preset maintenance program may include: and (3) disassembling the appointed valve, replacing the valve diaphragm and installing the appointed valve.
The method for maintaining the valve diaphragm of the nuclear power station provided by the embodiment has good practical effects when trial operation is performed in a plurality of nuclear power bases.
Optionally, after the operating point valve 005 is opened and whether the water yield of the operating point valve 005 is smaller than the preset water yield threshold is judged, the method further includes:
if the water yield of the working point valve 005 is greater than or equal to a preset water yield threshold value, connecting a compressed air output device with the working point pipeline, and simultaneously closing the working point valve 005;
and opening a designated branch valve on the branch pipeline, and delivering compressed air to the working point pipeline through the compressed air output device so as to discharge and reduce the water quantity in the pipeline area to be maintained through the designated branch valve.
In this embodiment, if the water yield of the operating point valve 005 is greater than or equal to the preset water yield threshold, it indicates that water flows out of the operating point valve 005 in a short time, and at this time, the designated valve to be maintained cannot be directly maintained. At this time, the compressed air output device may be connected to the working point pipeline, while the working point valve 005 is closed, and then the designated branch valve on the branch pipeline is opened, and compressed air is delivered to the working point pipeline through the compressed air output device, so as to be discharged through the designated branch valve and reduce the amount of water in the pipeline region to be maintained. It is noted that the operating point line may include a plurality of operating point valves 005. One of which may be used with the compressed air output device. When the compressed air output device delivers compressed air to the working point line, the working point valve 005 connected to the compressed air output device is in an open state, and the other working point valves 005 are in a closed state. The discharge speed of the water in the pipe in the area of the pipe to be serviced can be accelerated by the pressurizing effect of the compressed air.
In one embodiment, the designated branch valves may be valve 305, valve 406, valve 505.
Optionally, after the opening of the specified branch valve on the branch pipeline and the delivery of the compressed air to the working point pipeline through the compressed air output device to discharge and reduce the amount of water in the pipeline region to be maintained through the specified branch valve, the method further includes:
when the specified branch valve does not discharge water, the working point valve 005 is opened, and whether the water yield of the working point valve 005 is smaller than a preset water yield threshold value is judged;
and if the water yield of the working point valve 005 is less than a preset water yield threshold value, reducing the pressure of the working point pipeline to normal pressure, and then maintaining the valve diaphragm of the specified valve in the pipeline area to be maintained according to the preset maintenance program.
In this embodiment, after part of the water in the pipeline region to be maintained is discharged by the compressed air, the designated branch valve may be closed, the compressed air output device may be moved out, the operating point valve 005 may be opened, and it may be determined whether the water in the operating point valve 005 may be completely flowed in a short time (i.e., whether the water yield of the operating point valve 005 is less than the preset water yield threshold). When the water in the working point valve 005 can be completely poured in a short time, the pressure of the working point pipeline can be reduced to normal pressure, and then the valve diaphragm of the designated valve in the pipeline area to be maintained is maintained according to the preset maintenance program.
Optionally, when the specified branch valve does not discharge water, the operating point valve 005 is opened, and after determining whether the water yield of the operating point valve 005 is less than a preset water yield threshold, the method further includes:
if the water yield of operating point valve 005 is greater than or equal to the preset water yield threshold value, then open appointed branch road valve makes through the action of gravity water in waiting to maintain the pipeline region passes through operating point valve 005 discharges, the elevation of operating point valve 005 is less than the elevation of appointed branch road valve.
In this embodiment, when the drainage measures of the above embodiments are not effective (i.e. a large amount of water still flows out from the valve 005 at the working point), the water in the pipe area to be maintained needs to be drained. At this time, the water in the pipe area to be maintained can be drained in a gravity drainage manner. Specifically, the elevation of the working point valve 005 is-6.7 m, and the elevation of the designated branch valve is 0 m. Under the influence of gravity, the water in the area of the pipeline to be maintained is drained through the service point valve 005.
Optionally, before isolating the pipe area to be maintained, the method further includes:
closing the connecting valves of the pipeline area to be maintained and the external pipeline, and closing the connecting valves of the branch pipelines except the branch pipeline provided with the emptying valve 006 and the main pipeline;
opening the evacuation valve 006, and determining whether the evacuation valve 006 discharges water;
when the drain valve 006 does not drain water, it is determined that the pipe region to be maintained has been isolated.
In this embodiment, the isolation of the pipe area to be maintained requires the release of the internal pressure of the pipe area to be maintained. The specific operation may be: closing connecting valves of the pipeline area to be maintained and the external pipeline, namely a valve 001, a valve 002, a valve 003 and a valve 004; the connection valves of the branch pipes other than the branch pipe provided with the purge valve 006 to the main pipe, that is, the valve 101, the valve 201, the valve 301, the valve 401, the valve 501, the valve 102, the valve 202, the valve 302, the valve 402, and the valve 502 are closed. And then opens the purge valve 006. If there is an internal pressure in the pipe in the area of the pipe to be serviced, the internal pressure may force some of the water in the pipe out of the evacuation valve 006. When the drain valve 006 does not drain water, it is determined that the pipe area to be serviced is isolated.
Optionally, after the emptying valve 006 is opened and whether water is discharged from the emptying valve 006 is determined, the method further includes:
if the evacuation valve 006 discharges water, the evacuation valve 006 is closed first, and then a connecting valve between the branch pipeline provided with the evacuation valve 006 and the main pipeline is closed;
opening the purge valve 006 to determine the position of the connecting valve that does not perform the isolation function;
after the position of the connection valve without isolation is determined, the connection valve without isolation is adjusted to enable the connection valve without isolation to generate isolation.
In this embodiment, when the evacuation valve 006 continuously discharges water, which indicates that the pipe area to be maintained is not completely isolated from the external pipe, the evacuation valve 006 may be closed first, and then the connection valves of the branch pipe provided with the evacuation valve 006 and the main pipe, i.e., the valve 601 and the valve 602, may be closed. The evacuation valve 006 is then opened to determine where the connecting valves that are not providing isolation (either valves on the main or branch lines) are located. A connection valve that does not produce an isolation effect means that the connection valve is not completely closed. After determining the position of the connecting valve which does not produce the isolation effect, the torque of the connecting valve can be checked by using a static machine to judge whether the valve is completely closed. When the static machine detects that the torque of the connecting valve is at a normal value, the connecting valve can be judged to be completely closed. Only when the connecting valve is fully closed can it be ensured that the pipe area to be serviced is completely isolated from the external pipe.
Optionally, after the valve diaphragm of the specified valve in the pipeline region to be maintained is maintained according to a preset maintenance program, the method further includes:
after the valve diaphragm is maintained, filling water into the branch pipeline from the pipeline where the specified branch valve is located;
and gradually restoring the connection between the pipeline area to be maintained and the pipeline outside the pipeline area to be maintained according to a preset commissioning procedure.
The embodiment is suitable for the later water filling and air exhausting operation when the gravity drainage is not carried out. And after the valve diaphragms of all the designated valves are replaced, filling water into the branch pipelines from the designated branch valves, and gradually recovering the connection between the pipeline area to be maintained and the pipeline outside the pipeline area to be maintained according to a preset commissioning procedure. The designated branch valves include valve 305, valve 406, and valve 505. The water source for the fill may be from an SED system (nuclear island desalinated water distribution system).
The preset commissioning procedure may include:
1. on the RRI (facility cooling water system) side of the APG system (steam generator blowdown system), the exhaust is performed by opening an evacuation valve (not shown) of a branch pipe in which the APG system is located.
2. The RRI side of the DEG system (nuclear island chilled water subsystem) is put into operation, and exhaust is performed by opening an evacuation valve (not shown) of a branch pipe where the DEG system is located.
3. The first branch line, the second branch line, and the third branch line are opened, and exhaust is performed by an evacuation valve (not shown) provided in each branch line.
4. The evacuation valve 006 is opened to relieve pressure to the system.
5. And gradually opening a valve on the main pipeline. For example, a series of double valves may be provided at valve 003, where the first valve (the side connected to the external pipe) is opened with the test box for five seconds, the second valve is opened by 5%, the second valve is opened slowly after the liquid level in the RRI a column header tank does not drop, and the first valve is opened after the second valve is fully opened. The RRI a head tank is located at an elevation of 20m for receiving water volume changes due to temperature changes and providing a net positive suction head to the RRI pump.
6. The double valve set at valve 001 was opened in the manner of step 5 and the RRI a train was vented as a whole.
7. After the liquid level of the RRIA row connected to the public load head box is stable, the valve 002 and the valve 004 are opened in the same method, and the whole RRI B row is exhausted. The RRI B head box is located at an elevation of 20m and has the same function as the RRI a head box.
Optionally, if the water yield of the working point valve 005 is less than a preset water yield threshold, reducing the pressure of the working point pipeline to normal pressure, and then maintaining the valve diaphragm of the specified valve in the pipeline region to be maintained according to the preset maintenance program, further including:
after the valve diaphragm is maintained, filling water into the working point pipeline through the working point valve 005 and the designated branch valve;
and gradually restoring the connection between the pipeline area to be maintained and the pipeline outside the pipeline area to be maintained according to a preset commissioning procedure.
The embodiment is suitable for the water filling and air exhausting operation after the water is drained to 0m or minus 6.7m and the isolation is released. Specifically, the preset commissioning procedure is the same as the previous embodiment. But the fill position adds to the line in which the operating point valve 005 is located.
Optionally, if the fuel water pool connected to the pipeline area to be maintained loses cooling of the unit system, filling water into the pipeline of the working point through the valve 005 of the working point and the valve of the designated branch;
and gradually restoring the connection between the pipeline area to be maintained and the pipeline outside the pipeline area to be maintained according to a preset commissioning procedure.
The embodiment is suitable for water filling and air exhausting operation in emergency. Specifically, when an emergency occurs, the isolation of the pipe area to be maintained is immediately released, and water is filled into the working point pipeline through the working point valve 005 and the designated branch valve. The default commissioning procedure is the same as in the previous embodiment.
Optionally, the branch pipeline includes a first branch pipeline, the first branch pipeline is connected with the first reactor cooling pool 104, the first branch pipeline is further provided with a first reactor coolant main pump 103, and the first reactor coolant main pump 103 is arranged between the first reactor cooling pool 104 and the main pipeline.
In the present embodiment, the first reactor cooling pool 104 is provided on the first branch pipe. A first main reactor coolant pump 103 is also provided between the first reactor cooling pool 104 and the main conduit.
Optionally, the branch pipeline further includes a second branch pipeline, the second branch pipeline is connected with the second reactor cooling pool 204, the second branch pipeline is further provided with a second reactor coolant main pump 203, and the second reactor coolant main pump 203 is arranged between the second reactor cooling pool 204 and the main pipeline.
In this embodiment, the second reactor cooling pool 204 is provided on the second branch pipe. A second main reactor coolant pump 203 is also provided between the second reactor cooling pool 204 and the main pipe.
Optionally, the branch pipe further includes a third branch pipe, the third branch pipe is connected to a third reactor cooling pool 304, the third branch pipe is further provided with a third reactor coolant main pump 303, and the third reactor coolant main pump 303 is disposed between the third reactor cooling pool 304 and the main pipe.
In this embodiment, a third reactor cooling pool 304 is provided on the third branch pipe. A third main reactor coolant pump 303 is also provided between the third reactor coolant pool 304 and the main conduit.
Optionally, the branch pipe further includes a fourth branch pipe, the fourth branch pipe is provided with a first sub-branch and a second sub-branch, the first sub-branch is provided with a reactor coolant pressure relief tank 405 and a pressure relief pump 407, and the second sub-branch is provided with an excess downward-venting heat exchanger 404 and a heat-venting pump 403.
In this embodiment, the fourth branch pipe is provided with a first sub-branch and a second sub-branch. Specifically, the first sub-branch is provided with a reactor coolant pressure relief tank 405 and a pressure relief pump 407. The second sub-branch is provided with an excess letdown heat exchanger 404 and a heat let down pump 403. The reactor coolant pressure relief tank 405 is adapted to receive liquid discharged from a valve connected thereto, which is cooled by and discharged from the facility cooling water system. The valves connected to the reactor coolant pressure relief tank 405 include a potentiostat safety valve, a waste heat removal system safety valve, and a chemical volume control system. The excess bleed heat exchanger 404 cools the primary side fluid through the facility cooling water system to remove excess bleed heat.
Optionally, the branch pipeline further includes a fifth branch pipeline, the fifth branch pipeline is connected to the air-cooled system heat exchanger 504, the fifth branch pipeline is further provided with a heat exchange heat exchanger pump 503, and the heat exchange heat exchanger pump 503 is arranged between the air-cooled system heat exchanger 504 and the main pipeline.
In this embodiment, the air-cooling system heat exchanger 504 is provided on the fifth branch duct. A heat exchange and heat exchange pump 503 is arranged between the air cooling system heat exchanger 504 and the main pipeline. The air-cooled system heat exchanger 504 is used to maintain the temperature of the CRDM power coil unit and the position indicator within acceptable ranges to ensure their proper operation, the heat of which is removed by the facility cooling water system.
Optionally, the branch pipe further includes a sixth branch pipe, the sixth branch pipe is connected to the refrigerating unit and the heat exchanger 604 of the blowdown system, the sixth branch pipe is further provided with a blowdown heat exchanger pump 603, and the blowdown heat exchanger pump 603 is disposed between the heat exchanger 604 of the blowdown system and the main pipe.
In this embodiment, a chiller (not shown) and a blowdown heat exchanger 604 are provided on the fifth branch conduit. A blowdown system heat exchanger 603 is provided between the blowdown system heat exchanger 604 and the main pipe.
To facilitate understanding of the above-described embodiments of the present invention, the default commissioning procedure of an exemplary embodiment includes the following:
1. on the RRI (equipment cooling water system) side of the APG system (steam generator blowdown system) in the sixth branch line, exhaust is performed by opening an evacuation valve (not shown) of the branch line in which the APG system is located.
2. And (3) putting the DEG system (nuclear island chilled water subsystem) on the sixth branch pipeline into operation, and exhausting by opening an exhaust valve (not shown) of the branch pipeline where the DEG system is positioned.
3. The first branch line, the second branch line, and the third branch line are opened, and exhaust is performed by an evacuation valve (not shown) provided in each branch line.
4. The evacuation valve 006 is opened to relieve pressure to the system.
5. And gradually opening a valve on the main pipeline. For example, a series of double valves may be provided at valve 003, where the first valve (the side connected to the external pipe) is opened with the test box for five seconds, the second valve is opened by 5%, the second valve is opened slowly after the liquid level in the RRI a column header tank does not drop, and the first valve is opened after the second valve is fully opened.
6. The double valve set at valve 001 was opened in the manner of step 5 and the RRI a train was vented as a whole.
7. After the liquid level of the RRIA row connected to the public load head box is stable, the valve 002 and the valve 004 are opened in the same method, and the whole RRI B row is exhausted.
The above description is only for the purpose of illustrating the preferred embodiments of the present invention and is not to be construed as limiting the invention, and any modifications, equivalents and improvements made within the spirit and principle of the present invention are intended to be included within the scope of the present invention.
Claims (15)
1. A nuclear power plant valve diaphragm maintenance method is characterized by comprising the following steps:
isolating a pipeline area to be maintained of a nuclear power station, wherein the pipeline area to be maintained comprises a main pipeline, a plurality of branch pipelines and working point pipelines, the branch pipelines are communicated with the main pipeline, the working point pipelines are communicated with the main pipeline, and working point valves are arranged on the working point pipelines;
opening the working point valve, and judging whether the water yield of the working point valve is less than a preset water yield threshold value or not;
and if the water yield of the valve at the working point is less than a preset water yield threshold value, maintaining the valve diaphragm of the specified valve in the pipeline area to be maintained according to a preset maintenance program.
2. The method for maintaining the nuclear power plant valve diaphragm as recited in claim 1, wherein after the step of opening the operating point valve and determining whether the water yield of the operating point valve is less than a preset water yield threshold value, the method further comprises the steps of:
if the water yield of the working point valve is greater than or equal to a preset water yield threshold value, connecting a compressed air output device with the working point pipeline, and closing the working point valve;
and opening a designated branch valve on the branch pipeline, and delivering compressed air to the working point pipeline through the compressed air output device so as to discharge and reduce the water quantity in the pipeline area to be maintained through the designated branch valve.
3. The method of claim 2, wherein the step of opening a branch valve of the branch conduit to deliver compressed air to the worksite line via the compressed air output device to vent and reduce the amount of water in the conduit in the area of the conduit to be serviced via the branch valve further comprises:
when the specified branch valve does not discharge water, the working point valve is opened, and whether the water yield of the working point valve is smaller than a preset water yield threshold value or not is judged;
and if the water yield of the working point valve is less than a preset water yield threshold value, reducing the pressure of the working point pipeline to normal pressure, and then maintaining the valve diaphragm of the specified valve in the pipeline area to be maintained according to the preset maintenance program.
4. The method for maintaining the nuclear power plant valve diaphragm as recited in claim 3, wherein after the step of opening the operating point valve and determining whether the water output of the operating point valve is less than a preset water output threshold when the designated branch valve does not discharge water, the method further comprises:
if the water yield of operating point valve is greater than or equal to and predetermines the water yield threshold value, then open appointed branch road valve makes through the action of gravity water in waiting to maintain the pipeline region passes through the operating point valve is discharged, the elevation of operating point valve is less than the elevation of appointed branch road valve.
5. The method of nuclear power plant valve diaphragm maintenance of claim 1, further comprising, prior to isolating the area of pipe to be maintained:
closing connecting valves of the pipeline area to be maintained and an external pipeline, and closing connecting valves of branch pipelines except the branch pipeline provided with the emptying valve and the main pipeline;
opening the emptying valve, and judging whether water is discharged from the emptying valve;
and when the drain valve does not drain water, judging that the pipeline area to be maintained is isolated.
6. The method for maintaining a nuclear power plant valve diaphragm as in claim 5, wherein after the opening of the evacuation valve and the determination of whether the evacuation valve has water discharged, the method further comprises:
if the emptying valve has water to discharge, the emptying valve is closed firstly, and then a connecting valve of the branch pipeline provided with the emptying valve and the main pipeline is closed;
opening the evacuation valve to determine the position of the connecting valve which does not produce the isolation effect;
after the position of the connection valve without isolation is determined, the connection valve without isolation is adjusted to enable the connection valve without isolation to generate isolation.
7. The method for maintaining the valve diaphragm of the nuclear power plant according to claim 1, wherein after the valve diaphragm of the specified valve in the pipeline region to be maintained is maintained according to a preset maintenance program, the method further comprises the following steps:
after the valve diaphragm is maintained, filling water into the branch pipeline from the pipeline where the specified branch valve is located;
and gradually restoring the connection between the pipeline area to be maintained and the pipeline outside the pipeline area to be maintained according to a preset commissioning procedure.
8. The method for maintaining the nuclear power plant valve diaphragm as recited in claim 3, wherein after the pressure of the working point pipeline is reduced to normal pressure if the water yield of the working point valve is less than a preset water yield threshold value, and then the valve diaphragm of the specified valve in the pipeline region to be maintained is maintained according to the preset maintenance program, the method further comprises:
after the valve diaphragm is maintained, filling water into the working point pipeline through the working point valve and the specified branch valve;
and gradually restoring the connection between the pipeline area to be maintained and the pipeline outside the pipeline area to be maintained according to a preset commissioning procedure.
9. The method for maintaining the nuclear power plant valve diaphragm according to claim 3, wherein if a fuel pool connected with the pipeline area to be maintained loses unit system cooling, water is filled into the working point pipeline through the working point valve and the designated branch valve;
and gradually restoring the connection between the pipeline area to be maintained and the pipeline outside the pipeline area to be maintained according to a preset commissioning procedure.
10. The method of nuclear power plant valve diaphragm maintenance of claim 1, wherein the branch conduit comprises a first branch conduit connected to a first reactor coolant pool, the first branch conduit further provided with a first reactor coolant main pump disposed between the first reactor coolant pool and the main conduit.
11. The method of nuclear power plant valve diaphragm maintenance of claim 1, wherein the branch conduit further comprises a second branch conduit connected to a second reactor cooling pool, the second branch conduit further provided with a second reactor coolant main pump, the second reactor coolant main pump provided between the second reactor cooling pool and the main conduit.
12. The method of nuclear power plant valve diaphragm maintenance of claim 1, wherein the branch conduit further comprises a third branch conduit connected to a third reactor cooling pool, the third branch conduit further provided with a third reactor coolant main pump disposed between the third reactor cooling pool and the main conduit.
13. The method of nuclear power plant valve diaphragm maintenance of claim 1, wherein the branch conduit further comprises a fourth branch conduit, wherein the fourth branch conduit is provided with a first sub-branch and a second sub-branch, wherein the first sub-branch is provided with a reactor coolant pressure relief tank and a pressure relief pump, and wherein the second sub-branch is provided with an excess letdown heat exchanger and a heat relief pump.
14. The method for maintaining the nuclear power plant valve diaphragm as recited in claim 1, wherein the branch pipe further comprises a fifth branch pipe, the fifth branch pipe is connected with an air-cooled system heat exchanger, the fifth branch pipe is further provided with a heat exchange pump, and the heat exchange pump is arranged between the air-cooled system heat exchanger and the main pipe.
15. The nuclear power plant valve diaphragm maintenance method of claim 1, wherein the branch pipe further comprises a sixth branch pipe, the sixth branch pipe being connected to a chiller and a blowdown system heat exchanger, the sixth branch pipe further being provided with a blowdown heat exchange pump, the blowdown heat exchange pump being disposed between the blowdown system heat exchanger and the main pipe.
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Cited By (1)
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| CN114110433A (en) * | 2021-11-30 | 2022-03-01 | 内蒙古蒙牛乳业（集团）股份有限公司 | Safety maintenance device and method |
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