Solid material sampling device for nuclear power plants
By designing a nuclear power plant solid material sampling device including a cylinder, a diversion assembly and a piston pusher, the high industrial safety risks and unrepresentative sampling brought about by manual sampling of nuclear power plants are solved, and the safety, accurate sampling and analysis accuracy of solid materials are achieved.
Patent Information
- Application Number
- CN202421110035.6
- Authority / Receiving Office
- CN · China
- Patent Type
- Utility models(China)
- Current Assignee / Owner
- Filing Date
- 2024-05-20
- Publication Date
- 2025-04-01
- Estimated Expiration
- 2034-05-20
AI Technical Summary
Nuclear power plants lack special chemical solid material sampling tools, resulting in high industrial safety risks such as leakage, pollution, and personnel contamination in manual sampling. Moreover, sampling is not representative, affecting the dosing control indicators and the evaluation of resin effectiveness life.
A solid material sampling device for nuclear power plants is designed, including a cylinder, a flow guide assembly and a piston pusher. The flow guide and pulling member are used to control the opening and closing of the material port. The piston pusher defines the size of the accommodation space to achieve safe and accurate sampling of solid materials.
The device uses the tension of the solid material particles to squeeze each other after being pressed into the pipe, fixing the material in the pipe to avoid leakage and pollution, reducing industrial safety risks, ensuring representative sampling and analysis accuracy, and providing guarantees for the precise control of desalination of nuclear power plants and the water quality of the second circuit.
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Figure CN222704388U_ABST
Abstract
Description
Technical Field
[0001] The utility model relates to the field of solid chemical sampling for nuclear power plants, in particular to a solid material sampling device for nuclear power plants. Background Art
[0002] The water system of a nuclear power plant requires the use of chemical materials. For example, phosphates are needed to adjust the water quality of the circulating cooling water loop, and activated carbon and resin are added to the activated carbon filters in the desalted water production system, anion / cation / mixed ion exchangers, condensate polishing pre-cation bed / high-speed mixed bed, and resin regeneration towers.
[0003] These chemical materials need to be sampled and analyzed during the purchase, storage, and life inspection process to ensure that the purchased chemical materials meet the requirements of technical specifications, and the concentration and indicators of the stored chemical materials meet the dosing standards of the power plant-related systems and the technical parameters of the service life. At present, nuclear power plants do not have dedicated chemical solid material sampling tools. Generally, newly purchased samples are manually poured or simply sampled. The sampling process is prone to leakage, pollution, and personnel contamination. The industrial safety risk is extremely high. There is a problem that the sampling is not representative, and there is a human factor analysis bias, which is easy to mislead the dosing control indicators and affect the effectiveness and life evaluation of the resin. Utility Model Content
[0004] The technical problem to be solved by the utility model is to provide a solid material sampling device for a nuclear power plant.
[0005] The technical solution adopted by the utility model to solve the technical problem is: construct a nuclear power plant solid material sampling device, which includes a cylinder, a flow guide component and a piston push head;
[0006] The flow guide assembly includes a flow guide body connected to the cylinder, a flow guide cover movably connected to the flow guide body, and a pulling member connected to the flow guide cover. The flow guide body is provided with a material passing port. The interior of the cylinder and the interior of the flow guide body together form a containing space for containing solid materials. The material passing port is connected to the containing space.
[0007] The pulling member controls the movement of the deflector cover so that the deflector cover covers the material passage; or the deflector cover is displaced from the material passage to open the material passage so that the solid material can enter the accommodating space from the material passage;
[0008] The piston push head is installed inside the cylinder and limits the size of the accommodating space.
[0009] In some embodiments, the nuclear power plant solid material sampling device also includes a connecting rod connected to the piston push head and a push rod handle, and one end of the connecting rod away from the piston push head is located outside the cylinder and connected to the push rod handle.
[0010] In some embodiments, the connecting rod is provided with a scale.
[0011] In some embodiments, the pulling member includes a pulling body connected to the air deflector and a pulling handle connected to the pulling body.
[0012] In some embodiments, a first retaining member and a second retaining member are respectively provided on both sides of the circumferential end surface of the cylinder;
[0013] The pulling body is inserted through the first fixing member and the second fixing member and is fixedly connected to the air deflector. One end of the pulling body away from the air deflector is fixedly connected to the pulling handle.
[0014] In some embodiments, an exhaust hole is provided on one end of the cylinder away from the flow guide body, and the exhaust hole is connected to the interior of the cylinder.
[0015] In some embodiments, the nuclear power plant solid material sampling device further includes a positioning member connected to the connecting rod and used to position the relative position of the connecting rod and the cylinder.
[0016] In some embodiments, the positioning member is a positioning nut.
[0017] In some embodiments, there are two flow guide covers, and the two flow guide covers are symmetrically arranged about the central axis of the cylinder.
[0018] In some embodiments, the guide body has a conical structure.
[0019] The implementation of the utility model has the following beneficial effects: the solid material sampling device of the nuclear power plant utilizes the principle that the particles of the solid material are fixed in the tube and cannot move after being pressed into the tube and the tension is generated, so that the particles of the solid material are fixed in the tube and cannot move, and the sampling of the solid material can be realized. It can solve the risk of leakage, pollution, and personnel contamination caused by manual pouring sampling, and reduce industrial safety risks. It can also solve the technical problems of unrepresentative sampling and difficulty in sampling solid materials, ensure accurate analysis, and provide guarantees for the precise control of desalted water and secondary circuit water quality in nuclear power plants. At the same time, the opening and closing of the discharge port are controlled by the guide cover and the pulling member, which facilitates the sampling of the solid material sampling device of the nuclear power plant. A piston push head is also provided to limit the size of the accommodating space, so that the device can adjust the size of the accommodating space according to the sampling requirements. The solid material sampling device of the nuclear power plant is light, simple, practical, and easy to carry. BRIEF DESCRIPTION OF THE DRAWINGS
[0020] In order to more clearly illustrate the technical solution of the utility model, the utility model 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 utility model, and therefore should not be regarded as limiting the scope. For ordinary technicians in this field, other relevant drawings can be obtained based on these drawings without creative work. In the drawings:
[0021] Figure 1 It is a schematic diagram of the overall structure of a nuclear power plant solid material sampling device in some embodiments of the utility model. DETAILED DESCRIPTION
[0022] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, the specific implementation methods 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.
[0023] 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 utility model can be understood according to the specific circumstances.
[0024] See also Figure 1, is a nuclear power plant solid material sampling device in some embodiments of the utility model. The nuclear power plant solid material sampling device can be used for sampling materials related to chemical systems, such as activated carbon, resin, trisodium phosphate and other materials newly purchased in the warehouse, activated carbon filters in desalted water production systems, anion / cation / mixed ion exchangers, condensate polishing pre-cation bed / high-speed mixed bed and resin regeneration tower, activated carbon packaging bags, resin packaging barrels, phosphate barrels and other containers. Activated carbon, resin, phosphate can effectively improve the sampling work efficiency and reduce the industrial safety risks of personnel sampling.
[0025] Specifically, the solid material sampling device of the nuclear power plant may include a cylinder 1, a flow guide assembly 2 and a piston push head 3. The flow guide assembly 2 includes a flow guide body 21 connected to the cylinder 1, a flow guide cover 22 movably connected to the flow guide body 21 and a pull member 23 connected to the flow guide cover 22. A material passing port 211 is provided on the flow guide body 21. The interior of the cylinder 1 and the interior of the flow guide body 21 together form a receiving space 4 for receiving solid materials. The material passing port 211 is connected to the receiving space 4. The pull member 23 controls the movement of the flow guide cover 22 so that the flow guide cover 22 covers the material passing port 211; or the flow guide cover 22 is misaligned with the material passing port 211 to open the material passing port 211 so that solid materials can enter the receiving space 4 from the material passing port 211. The piston push head 3 is installed inside the cylinder 1 and limits the size of the receiving space 4. The size of the receiving space 4 affects the total amount of solid material sampled.
[0026] It can be understood that the interior of the cylinder 1 is a hollow structure, which can accommodate the relevant solid materials of the above-mentioned chemical system. The guide body 21 can be detachably connected to the cylinder 1, and the guide body 21 is roughly conical. The conical structure allows the guide body 21 to drill through the material layer to facilitate better sampling. The guide cover 22 is shielded from the material port 211 in the initial state. When the solid material sampling device of the nuclear power plant needs to sample the material, the movement of the guide cover 22 can be controlled by the pulling member 23. When the guide cover 22 is shielded from the material port 211, the solid material cannot enter the accommodating space 4 from the material port 211. When the guide cover 22 is misaligned with the material port 211, the solid material can enter the accommodating space 4 from the material port 211.
[0027] Among them, the cylinder 1 and the flow guide 21 can be set with sampling devices of different sizes and materials according to the characteristics of containers of different sizes and solid materials to avoid new pollution caused by the reaction between solid materials and sampling equipment. For example, the cylinder 1 and the flow guide 21 can be made of stainless steel.
[0028] In this embodiment, there are two flow guide covers 22, which are symmetrically arranged about the central axis of the cylinder 1, and there are two pullers 23 and two feed ports 211. In other embodiments, the number and arrangement of the flow guide covers 22 can be set according to actual conditions, and are not specifically limited here.
[0029] In addition, the outer wall size of the piston push head 3 is consistent with the inner wall size of the cylinder 1 to seal one end of the accommodating space 4. The piston push head 3 can be moved along the axial direction of the cylinder 1 to adjust the size of the accommodating space 4. The position of the piston push head 3 can be adjusted according to different sampling requirements.
[0030] In some embodiments, the pulling member 23 includes a pulling body 231 connected to the air deflector 22 and a pulling handle 232 connected to the pulling body 231, and the first retaining member 11 and the second retaining member 12 are respectively provided on both sides of the circumferential end surface of the cylinder 1, the pulling body 231 is penetrated by the first retaining member 11 and the second retaining member 12, and is fixedly connected to the air deflector 22, and the end of the pulling body 231 away from the air deflector 22 is fixedly connected to the pulling handle 232. It can be understood that the first retaining member 11 and the second retaining member 12 can provide a guiding effect for the movement of the pulling body 231, and the first retaining member 11 can also provide a limiting effect on the pulling handle 232. The operator can pull the pulling handle 232 to move the pulling body 231 and thus move the air deflector 22.
[0031] Furthermore, the nuclear power plant solid material sampling device further comprises a connecting rod 5 connected to the piston push head 3 and a push rod handle 6, wherein one end of the connecting rod 5 away from the piston push head 3 is located outside the cylinder 1 and connected to the push rod handle 6. The connecting rod 5 can move along the axial direction of the cylinder 1, and before sampling is required, the push rod handle 6 can drive the piston push head 3 to move through the connecting rod 5, so that the accommodating space 4 is reduced or increased, and when testing is required after the sampling is completed, the piston push head 3 can also be driven by the push rod handle 6 to make the solid material flow out of the accommodating space 4.
[0032] In some embodiments, an exhaust hole 13 is provided on one end of the cylinder 1 away from the flow guide 21 . The exhaust hole 13 is connected to the interior of the cylinder 1 , and the gas in the cylinder 1 can be discharged through the exhaust hole 13 .
[0033] In some embodiments, the nuclear power plant solid material sampling device further includes a positioning member 7 connected to the connecting rod 5 and used to position the relative position of the connecting rod 5 and the cylinder 1. The connecting rod 5 may be a screw, and the positioning member 7 may be a positioning nut, which may lock the relative position between the connecting rod 5 and the cylinder 1, so that the size of the accommodating space 4 remains unchanged during the sampling process. When solid material detection is required after sampling, the positioning nut may be loosened to allow the connecting rod 5 to move.
[0034] In addition, the connecting rod 5 is provided with a scale so that the operator can conveniently adjust the size of the accommodating space 4 according to the scale.
[0035] The specific working process of the solid material sampling device of the nuclear power plant is:
[0036] 1. Use the push rod handle 6 to adjust the position of the piston push head 3. After the piston push head 3 reaches a suitable position, lock the positioning member 7;
[0037] 2. Insert the cylinder 1 and the guide body 21 vertically into the solid material, drill the solid material through the guide body 21, and after reaching the target depth, pull the pull handle 232 to displace the guide cover 22 and the material passing port 211, and the solid material enters the accommodating space 4 from the material passing port 211;
[0038] 3. Continue to insert the guide body 21 downward until the solid material entering the accommodating space 4 meets the total amount of sampling;
[0039] 4. After the solid materials entering the accommodating space 4 meet the total amount of sampling, the pull handle 232 is pushed so that the guide cover 22 covers the material passing port 211. At this time, the solid materials cannot enter the accommodating space 4, and then the entire nuclear power plant solid material sampling device is taken out;
[0040] 5. Release the positioning member 7, use the push rod handle 6 to push the piston push head 3, and push the solid material originally accommodated in the accommodating space 4 into the sample holding container to complete the overall sampling work.
[0041] It can be understood that the solid material sampling device of the nuclear power plant utilizes the principle that the particles of the solid material are fixed in the tube and cannot move after being pressed into the tube by the tension of squeezing each other, so that the particles of the solid material can be sampled. It can solve the risk of leakage, pollution, and personnel contamination caused by manual pouring sampling, and reduce industrial safety risks. It can also solve the technical problems of unrepresentative sampling and difficult sampling of solid materials, ensure accurate analysis, and provide guarantees for the precise control of desalted water and secondary circuit water quality in nuclear power plants. At the same time, the guide cover 22 and the pull member 23 are used to control the opening and closing of the discharge port, which facilitates the sampling of the solid material sampling device of the nuclear power plant. A piston push head 3 is also provided to limit the size of the accommodating space 4, so that the device can adjust the size of the accommodating space 4 according to the sampling requirements. The solid material sampling device of the nuclear power plant is light, simple, practical, and easy to carry.
[0042] It can be understood that the above embodiments only express the preferred implementation methods of the utility model, and the descriptions thereof are relatively specific and detailed, but they cannot be understood as limiting the patent scope of the utility model. It should be pointed out that, for ordinary technicians in this field, without departing from the concept of the utility model, the above-mentioned technical features can be freely combined, and several deformations and improvements can be made, which all belong to the protection scope of the utility model. Therefore, all equivalent changes and modifications made to the scope of the claims of the utility model should fall within the scope of the claims of the utility model.
Claims
1. A solid material sampling device for a nuclear power plant, characterized in that: It comprises a cylinder (1), a flow guide assembly (2) and a piston push head (3); The flow guide assembly (2) comprises a flow guide body (21) connected to the cylinder (1), a flow guide cover (22) movably connected to the flow guide body (21), and a pulling member (23) connected to the flow guide cover (22); a material passing port (211) is provided on the flow guide body (21); the interior of the cylinder (1) and the interior of the flow guide body (21) together form a containing space (4) for containing solid materials; the material passing port (211) is connected to the containing space (4); The pulling member (23) controls the movement of the guide cover (22) so that the guide cover (22) covers the material passage opening (211); or the guide cover (22) and the material passage opening (211) are displaced to open the material passage opening (211) so that solid materials can enter the accommodating space (4) from the material passage opening (211); The piston push head (3) is installed inside the cylinder (1) and limits the size of the accommodating space (4).
2. The solid material sampling device for nuclear power plants according to claim 1, characterized in that: The nuclear power plant solid material sampling device also includes a connecting rod (5) connected to the piston push head (3) and a push rod handle (6); one end of the connecting rod (5) away from the piston push head (3) is located outside the cylinder (1) and connected to the push rod handle (6).
3. The solid material sampling device for nuclear power plants according to claim 2, characterized in that: The connecting rod (5) is provided with a scale.
4. The solid material sampling device for nuclear power plants according to claim 1, characterized in that: The pulling member (23) comprises a pulling body (231) connected to the air deflector (22) and a pulling handle (232) connected to the pulling body (231).
5. The solid material sampling device for nuclear power plants according to claim 4, characterized in that: A first retaining member (11) and a second retaining member (12) are respectively provided on both sides of the circumferential end surface of the cylinder (1); The pulling body (231) is inserted through the first fixing member (11) and the second fixing member (12) and is fixedly connected to the air deflector (22); one end of the pulling body (231) away from the air deflector (22) is fixedly connected to the pulling handle (232).
6. The solid material sampling device for nuclear power plants according to claim 1, characterized in that: An exhaust hole (13) is provided on one end of the cylinder (1) away from the flow guide (21), and the exhaust hole (13) is communicated with the interior of the cylinder (1).
7. The solid material sampling device for nuclear power plants according to claim 2, characterized in that: The nuclear power plant solid material sampling device further comprises a positioning member (7) connected to the connecting rod (5) and used for positioning the relative position of the connecting rod (5) and the cylinder (1).
8. The solid material sampling device for nuclear power plants according to claim 7, characterized in that: The positioning member (7) is a positioning nut.
9. The solid material sampling device for a nuclear power plant according to claim 1, characterized in that: The number of the air guide covers (22) is two, and the two air guide covers (22) are symmetrically arranged about the central axis of the cylinder (1).
10. The solid material sampling device for a nuclear power plant according to claim 1, characterized in that: The flow guide (21) has a conical structure.