Sampling device and method for hydraulic test of primary loop of nuclear power plant
By installing clamping units on the side wall of the evaporator in a nuclear power plant, and using pipelines to directly connect to the evaporator, remote filling, water effluent and sampling are realized, the problem of personnel entering and leaving high-radiation areas many times in the prior art has been solved, and manpower has been reduced Cost and radiation dose improve engineering efficiency.
Patent Information
- Application Number
- CN202411498506.X
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2024-10-24
- Publication Date
- 2025-02-25
- Estimated Expiration
- 2044-10-24
AI Technical Summary
During the first-circuit hydraulic pressure test of a nuclear power plant, the existing technology requires personnel to enter and exit the high-radiation dose area multiple times to fill, sample and drain water, resulting in high labor costs, large radiation dose and extended construction period.
A sampling device including a water supply unit, a water supply sampling unit, a clamping unit and a sample loading unit are designed. By installing a clamping unit on the side wall of the evaporator, it is directly connected to the evaporator with a pipe to realize remote filling, water effluent and sampling. .
It reduces the number of times people enter and exit the high-radiation area, reduces labor costs and radiation dose, and reduces the time for welding repair and ray detection of the evaporator hydrophobic pipe, and improves engineering efficiency.
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Figure CN119510050A_ABST
Abstract
Description
Technical Field
[0001] The invention relates to the field of liquid sampling test, and in particular to a sampling device and method for a primary circuit water pressure test of a nuclear power plant. Background Art
[0002] Domestic nuclear reactor units are generally equipped with a primary circuit and a secondary circuit. The liquid in the primary circuit is in direct contact with the reactor and generally contains high radiation. The secondary circuit is set in the evaporator and exchanges heat with the liquid in the primary circuit through external pure water. During the implementation of the primary circuit water pressure test, the secondary circuit of the evaporator must be filled with water according to the RSE-M specification requirements, and then the water in the secondary circuit must be extracted for radiation detection to detect whether there is any leakage in the primary circuit due to the water pressure test.
[0003] At present, the pipes are generally cut on the APG system drain line of the evaporator, and water intake equipment is installed for water intake testing. However, since this area is a high radiation dose area, personnel enter and exit the high radiation dose area of the control area several times during the test to fill the secondary circuit with water, take samples, drain water and deliver samples. The labor cost is high and the collective radiation dose is large. After the water pressure test is completed, the water intake and intake devices are dismantled, the pipeline welds are restored and X-ray inspections are carried out, which is extremely time-consuming and hinders the progress of other projects, resulting in an extension of the overall project schedule. Summary of the invention
[0004] The technical problem to be solved by the present invention is to provide a nuclear power plant primary circuit water pressure test sampling device and method, aiming to solve the problems in the prior art.
[0005] The technical solution adopted by the present invention to solve its technical problems includes: a water supply unit, a water supply sampling unit, a clamping unit and a sample loading unit; the water supply unit supplies liquid into the water supply sampling unit; the clamping unit is arranged on the evaporator, and the clamping unit is provided with a through hole penetrating the side wall of the evaporator; the water supply sampling unit includes an inlet valve, an outlet valve, a flow meter and a water pump, the flow meter is connected to the clamping unit through a pipeline, and the pipeline passes through the side wall of the evaporator and extends into the evaporator; the water supply unit, the water inlet valve, the flow meter and the clamping unit are connected through a pipeline to form a first water path, the first water path is used to supply water to the evaporator, the clamping unit, the flow meter, the water pump and the outlet valve are connected through a pipeline to form a second water path, and the second water path is used to extract liquid in the evaporator into the sample loading unit.
[0006] In one embodiment, the clamping unit includes a base and a blocking piece, the base is arranged at the through hole, the blocking piece is detachably connected to the base, and the blocking piece is used to block the through hole.
[0007] In one embodiment, the blocking member is connected to the base via bolts, and the sealing gasket is provided between the blocking member and the base.
[0008] In one embodiment, the sample clamping unit includes a sampling inner barrel and an outer barrel, the sampling inner barrel is connected to the water outlet valve, and the sampling inner barrel is arranged in the outer barrel.
[0009] In one embodiment, the water pump is a manual water pump.
[0010] In one embodiment, the first water channel and the second water channel share a pipeline through which the flow meter is connected to the clamping unit.
[0011] In one embodiment, the water supply unit is located higher than the water inlet valve, the flow meter and the clamping unit, and the water supply unit supplies water to the water inlet valve by relying on gravitational potential energy.
[0012] The present invention also discloses a nuclear power plant primary circuit water pressure test sampling method, comprising the following steps:
[0013] Step S1, opening the water inlet valve, and the water supplied by the water supply unit flows through the water inlet valve, the flow meter, the clamping unit, and finally flows into the evaporator;
[0014] Step S2, when the flow meter reaches the specified water inlet volume, close the water inlet valve;
[0015] Step S3, starting the water pump, opening the drain valve, and allowing the liquid in the evaporator to flow through the flow meter, the water pump and the drain valve, and finally flow into the sample loading unit;
[0016] Step S4, when it is observed that the flow meter reaches the specified water output, the water outlet valve is closed, and the sample loading unit is removed to complete the sampling.
[0017] In one embodiment, before step S1, the clamping unit needs to be opened to expose the through hole for connection with the pipeline.
[0018] In one embodiment, if the water output exceeds the capacity of the sample loading unit, the water outlet valve needs to be closed immediately.
[0019] The implementation of the present invention has the following beneficial effects: a clamping unit is installed on the side wall of the evaporator, the clamping unit has a hole in the side wall of the evaporator, and can be directly connected to the inside of the evaporator through a hose, and the water supply sampling unit can perform remote injection, water discharge and sampling, which reduces the number of times users enter and exit high radiation dose areas, and because there is no need to cut the evaporator drain pipe every time, the time for welding and repairing the evaporator drain pipe and radiographic inspection is reduced, greatly improving engineering efficiency. BRIEF DESCRIPTION OF THE DRAWINGS
[0020] In order to more clearly illustrate the technical solution of the present invention, the present invention will be further described below in conjunction with the accompanying drawings and embodiments. It should be understood that the following drawings only show certain embodiments of the present invention and should not be regarded as limiting the scope. For ordinary technicians in this field, other related drawings can be obtained based on these drawings without creative work. In the drawings:
[0021] Figure 1 It is an overall diagram of a nuclear power plant primary circuit water pressure test sampling device in one embodiment of the present invention;
[0022] Figure 2 It is a front view of a clamping unit of a nuclear power plant primary circuit water pressure test sampling device in one embodiment of the present invention;
[0023] Figure 3 It is a cross-sectional view of a clamping unit of a nuclear power plant primary circuit water pressure test sampling device in one embodiment of the present invention;
[0024] Figure 4 The present invention is a flowchart of a nuclear power plant primary circuit water pressure test sampling method in one embodiment of the present invention.
[0025] Figure Annotation
[0026] 100, water supply unit; 110, evaporator; 200, water supply sampling unit; 210, water inlet valve; 220, water outlet valve; 230, water pump; 240, flow meter; 300, clamping unit; 310, through hole; 320, bolt; 330, base; 340, plugging piece; 350, sealing gasket; 400, sampling inner barrel; 410, outer barrel. DETAILED DESCRIPTION
[0027] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, the specific embodiments of the present invention are now described in detail with reference to the accompanying drawings. In the following description, it should be understood that the directions or positional relationships indicated by "front", "back", "up", "down", "left", "right", "longitudinal", "horizontal", "vertical", "horizontal", "top", "bottom", "inside", "outside", "head", "tail", etc. are based on the directions or positional relationships shown in the accompanying drawings, are constructed and operated in a specific direction, and are only for the convenience of describing the present technical solution, rather than indicating that the device or element referred to must have a specific direction, and therefore cannot be understood as a limitation to the present invention.
[0028] It should also be noted that, unless otherwise clearly specified and limited, the terms such as "installed", "connected", "connected", "fixed", "set" and the like should be understood in a broad sense, for example, it can be a fixed connection, a detachable connection, or an integral one; it can be a mechanical connection or an electrical connection; it can be directly connected or indirectly connected through an intermediate medium, it can be the internal connection of two elements or the interaction relationship between two elements. When an element is referred to as being "on" or "under" another element, the element can be "directly" or "indirectly" located on the other element, or there may be one or more intermediate elements. The terms "first", "second", "third", etc. are only for the convenience of describing the present technical solution, and cannot be understood as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Therefore, the features defined as "first", "second", "third", etc. can explicitly or implicitly include one or more of the features. For those of ordinary skill in the art, the specific meanings of the above terms in the present invention can be understood according to the specific circumstances.
[0029] Figures 1 to 3 The present invention shows a nuclear power plant primary circuit water pressure test sampling device in an embodiment of the present invention, which can be used for water pressure test sampling investigation in the nuclear power plant evaporator 110, and may include a water supply unit 100, a water supply sampling unit 200, a clamping unit 300 and a sample loading unit; the water supply unit 100 supplies liquid to the water supply sampling unit 200; the clamping unit 300 is arranged on the evaporator 110, and the clamping unit 300 is provided with a through hole 310 penetrating the side wall of the evaporator 110; the water supply sampling unit 200 includes a water inlet valve 210, a water outlet valve 220, a flow meter 240 and a water pump 230, and the flow meter 240 is connected to the clamping unit 300 through a pipeline, and the pipeline passes through the side wall of the evaporator 110 and extends into the evaporator 110; the water supply unit 100, the water inlet valve 210, the flow meter 240 and the water pump 230 The meter 240 and the clamping unit 300 are connected by a pipeline to form a first water circuit, and the first water circuit is used to supply water to the evaporator 110. The clamping unit 300, the flow meter 240, the water pump 230 and the water outlet valve 220 are connected by a pipeline to form a second water circuit, and the second water circuit is used to extract the liquid in the evaporator 110 into the loading sample unit. The clamping unit 300 is installed on the side wall of the evaporator 110. The clamping unit 300 has a hole in the side wall of the evaporator 110 and can be directly connected to the inside of the evaporator 110 through a hose. The water supply sampling unit 200 can perform remote irrigation, water discharge and sampling. The user responds that the number of times entering and exiting the high radiation dose area is reduced, and since there is no need to destroy the drain pipe of the evaporator 110 every time, the time for welding and repairing the drain pipe of the evaporator 110 and radiographic flaw detection is reduced, greatly improving engineering efficiency.
[0030] It is understandable that the temperature, humidity and radiation of the environment where the evaporator 110 is located are relatively high, which is not suitable for engineers to stay for a long time. Therefore, the length of the pipeline between the clamping unit 300 and the flow meter 240 is relatively long and can be extended to an area with a relatively good working environment for sampling.
[0031] In a specific embodiment, the flow meter 240 is a non-contact flow meter 240 , which can detect flow without directly contacting the liquid, thereby preventing the flow meter 240 from being damaged by high-temperature and high-radiation liquid.
[0032] In a specific embodiment, the flow meter 240 is an ultrasonic flow meter 240, and detection can be performed by simply connecting the ultrasonic flow meter 240 to the pipeline, which is simple to operate and has high accuracy.
[0033] In a specific embodiment, the flow meter 240 is a mechanical flow meter 240. Since there are no corresponding electronic components inside, it can still work normally in a high radiation and high temperature working environment.
[0034] In a specific embodiment, the water inlet valve 210, the water outlet valve 220, the flow meter 240 and the water pump 230 are integrated into one device.
[0035] In a specific embodiment, a radiation detection device is provided in the sample loading unit. When the sample loading unit is loaded with a radiation liquid, the radiation detection device automatically detects the radiation content of the liquid.
[0036] Figure 1 and Figure 3 It is shown that the clamping unit 300 may include a base 330 and a sealing member 340 in one embodiment. The base 330 is arranged at the through hole 310. The sealing member 340 is detachably connected to the base 330. The sealing member 340 is used to seal the through hole 310. When sampling is required, the sealing member 340 is opened and the pipeline enters the evaporator 110 through the through hole 310. When sampling is not required, the pipeline is taken out of the through hole 310 and the sealing member 340 is installed back into the through hole 310.
[0037] In a specific embodiment, the base 330 is welded to the evaporator 110 .
[0038] Figure 1 and Figure 3 It is shown that the clamping unit 300 may include a sealing member 340 connected to a base 330 via bolts 320 in one embodiment, and a sealing gasket 350 is provided between the sealing member 340 and the base 330 to prevent leakage between the sealing member 340 and the base 330 .
[0039] In a specific embodiment, the blocking member 340 is a cover plate made of a non-transparent material, which is fixed to the base 330 by bolts 320. Transparent objects are not allowed to be brought into the nuclear power facility.
[0040] Figure 1 It is shown that the clamping sample unit may include a sampling inner barrel 400 and an outer barrel 410 in one embodiment. The sampling inner barrel 400 is connected to the water outlet valve 220, and the sampling inner barrel 400 is arranged in the outer barrel 410. The sampling inner barrel 400 is used to load the sampled liquid, and the outer barrel 410 is used to prevent the poured liquid from remaining on the ground.
[0041] It can be understood that the shape of the sampling inner barrel 400 depends on actual needs and design requirements, and can be a normal beaker shape, a bottle shape, etc.
[0042] Figure 1 It is shown that in one embodiment, the water pump 230 may include a manual water pump 230. The manual water pump 230 can be pumped manually. When the water injection is less than 10 liters, the use of the manual water pump 230 can save the demand for electricity supply and reduce the total cost. The manual water pump 230 can stop pumping water at any time. It is simpler to operate and more controllable than the electric water pump 230.
[0043] Figure 1 It is shown that the loading unit 330 may include a pipeline of the first water path and the second water path connecting the clamping unit 300 with a common flow meter 240 in one embodiment.
[0044] Figure 1 It is shown that the loading unit 330 may include a water supply unit 100 located higher than the water inlet valve 210 , the flow meter 240 and the clamping unit 300 in one embodiment, and the water supply unit 100 supplies water to the water inlet valve 210 by gravity potential energy.
[0045] Figure 4 A method for sampling a primary circuit water pressure test of a nuclear power plant in an embodiment of the present invention is shown, which may include:
[0046] Step S1, the water inlet valve 210 is opened, and the water supplied by the water supply unit 100 flows through the water inlet valve 210, the flow meter 240, the clamping unit 300, and finally flows into the evaporator 110;
[0047] Step S2, when the flow meter 240 reaches the specified water inflow, close the water inlet valve 210;
[0048] Step S3, start the water pump 230, open the drain valve, and the liquid in the evaporator 110 flows through the flow meter 240, the water pump 230 and the drain valve, and finally flows into the sample loading unit;
[0049] Step S4, when the flow meter 240 reaches the specified water output, the water outlet valve 220 is closed, the sample loading unit is removed, and the sampling is completed.
[0050] Figure 2 and Figure 3 It is shown that step S1 in one embodiment may include opening the clamping unit 300 before step S1 to expose the through hole 310 for connection with the pipeline.
[0051] Figure 4 In one embodiment, step S4 may include immediately closing the water outlet valve 220 if the water output exceeds the capacity of the sample loading unit to prevent the water from overflowing onto the ground and causing radiation contamination.
[0052] It can be understood that the above embodiments only express the preferred implementation modes of the present invention, and the description thereof is relatively specific and detailed, but it cannot be understood as limiting the patent scope of the present invention. It should be pointed out that, for ordinary technicians in this field, without departing from the concept of the present invention, the above technical features can be freely combined, and several deformations and improvements can be made, which all belong to the protection scope of the present invention. Therefore, all equivalent changes and modifications made to the scope of the claims of the present invention should belong to the scope covered by the claims of the present invention.
Claims
1. A sampling device for a hydraulic pressure test of a primary circuit of a nuclear power plant, wherein the primary circuit of the nuclear power plant comprises an evaporator (110), characterized in that: include: A water supply unit (100), a water supply sampling unit (200), a clamping unit (300) and a sample loading unit; The water supply unit (100) supplies liquid into the water supply sampling unit (200); The clamping unit (300) is arranged on the evaporator (110), and the clamping unit (300) is provided with a through hole (310) penetrating a side wall of the evaporator (110); The water supply sampling unit (200) comprises a water inlet valve (210), a water outlet valve (220), a flow meter (240) and a water pump (230); the flow meter (240) is connected to the clamping unit (300) via a pipeline, and the pipeline passes through the side wall of the evaporator (110) and extends into the evaporator (110); the water supply unit (100), the water inlet valve (210), the flow meter (240) and the clamping unit (300) are connected via a pipeline to form a first water path, and the first water path is used to supply water to the evaporator (110); the clamping unit (300), the flow meter (240), the water pump (230) and the water outlet valve (220) are connected via a pipeline to form a second water path, and the second water path is used to extract liquid in the evaporator (110) into the sample loading unit.
2. The nuclear power plant primary circuit water pressure test sampling device according to claim 1, characterized in that: The clamping unit (300) comprises a base (330) and a blocking piece (340), wherein the base (330) is arranged at the through hole (310), the blocking piece (340) is detachably connected to the base (330), and the blocking piece (340) is used to block the through hole (310).
3. The nuclear power plant primary circuit water pressure test sampling device according to claim 1, characterized in that: The blocking member (340) and the base (330) are connected via bolts (320), and the sealing gasket (350) is provided between the blocking member (340) and the base (330).
4. The nuclear power plant primary circuit water pressure test sampling device according to claim 1, characterized in that: The sample clamping unit comprises a sampling inner barrel (400) and an outer barrel (410); the sampling inner barrel (400) is in communication with the water outlet valve (220); and the sampling inner barrel (400) is disposed in the outer barrel (410).
5. The nuclear power plant primary circuit water pressure test sampling device according to claim 1, characterized in that: The water pump (230) is a manual water pump (230).
6. The nuclear power plant primary circuit water pressure test sampling device according to claim 1, characterized in that: The first water channel and the second water channel share the flow meter (240) connected to the pipeline of the clamping unit (300).
7. The nuclear power plant primary circuit water pressure test sampling device according to claim 1, characterized in that: The water supply unit (100) is located higher than the water inlet valve (210), the flow meter (240) and the clamping unit (300), and the water supply unit (100) supplies water to the water inlet valve (210) by relying on gravitational potential energy.
8. A sampling method for a primary circuit water pressure test in a nuclear power plant, applied to a sampling device for a primary circuit water pressure test in a nuclear power plant as claimed in any one of claims 1 to 7, characterized in that: The following steps are involved: Step S1, opening the water inlet valve (210), so that the water supplied by the water supply unit (100) flows through the water inlet valve (210), the flow meter (240), and the clamping unit (300), and finally flows into the evaporator (110); Step S2, when the flow meter (240) reaches a specified water inflow, closing the water inlet valve (210); Step S3, starting the water pump (230), opening the drain valve, and allowing the liquid in the evaporator (110) to flow through the flow meter (240), the water pump (230) and the drain valve, and finally flowing into the sample loading unit; Step S4, when the flow meter (240) is observed to reach the specified water output, the water outlet valve (220) is closed, and the sample loading unit is removed to complete the sampling.
9. The nuclear power plant primary circuit water pressure test sampling method according to claim 8, characterized in that: Before step S1, the clamping unit (300) needs to be opened to expose the through hole (310) for connection with the pipeline.
10. The nuclear power plant primary circuit water pressure test sampling method according to claim 8, characterized in that: In step S4, if the water output exceeds the capacity of the sample loading unit, the water outlet valve (220) needs to be closed immediately.
Citation Information
Patent Citations
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