Nuclear power plant sampling control method and device

By designing automated sample transport vehicles and sample distribution tables in nuclear power plants, the safety and efficiency problems existing in manual participation in radioactive sample sampling and transportation are solved, and an efficient and safe sample processing process without participation is achieved.

CN119470943APending Publication Date: 2025-02-18SANMEN NUCLEAR POWER CO LTD
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Patent Information

Application Number
CN202411460412.3
Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Filing Date
2024-10-18
Publication Date
2025-02-18

AI Technical Summary

Technical Problem

In the prior art, artificial participation in the sampling and transportation of radioactive samples has the risk of nuclear radiation leakage and personnel exposure, and is inefficient and prone to errors.

Method used

A nuclear power plant sampling control method and device is designed, and the robotic arms of the sample transport vehicle and the sample decoupling table are used for automated sampling and sampling, and the work flow of the sample transport vehicle, sample decoupling table and detection instrument are coordinated through the control module.

Benefits of technology

Without manual participation, robotic arms and trolleys replace manual operation, avoiding the harm of nuclear leakage and personnel exposure, improving work efficiency, and preventing manual operation errors. The sampling door and delivery door of the sample separation table are only open when transporting samples and remain closed at other moments, further preventing nuclear leakage.

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Abstract

The invention relates to the technical field of computers, and discloses a sampling control method and device for a nuclear power plant. The method comprises the steps that in response to a to-be-detected sample obtained by a sample transport vehicle, the sample transport vehicle is controlled to transport the to-be-detected sample into a first preset area near a sample separation table, and the sample separation table comprises a mechanical arm, a sampling door and a sample sending door; when it is detected that the sample transport vehicle is located in the first preset area, a sample separation table is controlled to open a sampling door, and a mechanical arm is controlled to grab a to-be-detected sample on the sample transport vehicle to the sample separation table; controlling the sample separation table to separate the to-be-detected sample so as to obtain a plurality of to-be-detected sub-samples corresponding to different detection instruments; when it is detected that the sample transport vehicle is located in a second preset area near the sample separation table, the multiple to-be-detected sub-samples are placed on the sample transport vehicle, and the sample transport vehicle is controlled to transport the multiple to-be-detected sub-samples to the corresponding detection instruments respectively. Automatic operation is achieved, the working efficiency is improved, human errors are reduced, and harm to workers is reduced.
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Description

Technical Field

[0001] The present invention relates to the field of computer technology, and in particular to a nuclear power plant sampling control method and device. Background Art

[0002] Radioactive samples refer to wastewater containing radioactive substances, which mainly come from nuclear power generation, nuclear fuel processing, nuclear research and other activities related to nuclear technology. These wastewaters may contain radioactive isotopes of different types and concentrations, and therefore pose a potential threat to the environment and human health. The detection of radioactive samples is an important step in the management of radioactive samples. The detection of radioactive samples mainly includes the determination of their radioactive concentration and physical and chemical properties. Radioactive sample detection is often carried out in the laboratory. Before the radioactive samples are detected, it is necessary to collect the radioactive samples and separate them to prepare for different detection instruments in the laboratory.

[0003] In the related technology, samples to be tested need to be manually divided and transported. However, in the process of sampling and dividing samples to be tested by laboratory staff, there is a risk of nuclear radiation leakage and personnel exposure. The manual participation in radioactive sample testing cannot ensure the safety of laboratory staff, and is inefficient and prone to errors. Summary of the invention

[0004] The embodiments of this specification provide a nuclear power plant sampling control method, device, electronic equipment, and storage medium, and the technical solutions are as follows:

[0005] In a first aspect, an embodiment of the present specification provides a nuclear power plant sampling control method, which is applied to a control module in a sampling system, wherein the sampling system includes the control module, a sample transport vehicle, a sample separation platform, and multiple detection instruments. The nuclear power plant sampling control method includes the following steps:

[0006] In response to the sample transport vehicle acquiring the sample to be tested, controlling the sample transport vehicle to transport the sample to be tested to a first preset area near the sample separation platform, wherein the sample separation platform includes a mechanical arm, a sampling door, and a sample delivery door;

[0007] When it is detected that the sample transport vehicle is located in the first preset area, the sample separation platform is controlled to open the sampling door, and the mechanical arm is controlled to grab the sample to be tested on the sample transport vehicle and place it on the sample separation platform;

[0008] Controlling the sample splitting station to split the sample to be tested, so as to obtain a plurality of sub-samples to be tested corresponding to different testing instruments;

[0009] When it is detected that the sample transport vehicle is located in a second preset area near the sample separation station, the multiple sub-samples to be tested are placed on the sample transport vehicle, and the sample transport vehicle is controlled to transport the multiple sub-samples to be tested to corresponding detection instruments respectively.

[0010] In a second aspect, the embodiments of this specification provide a nuclear power plant sampling control device, which is applied to a control module of a sampling system, wherein the sampling system includes the control module, a sample transport vehicle, a sample separation platform, and a plurality of detection instruments;

[0011] The nuclear power plant sampling control device comprises:

[0012] A first transport unit, configured to control the sample transport vehicle to transport the sample to be tested to a first preset area near the sample separation platform in response to the sample transport vehicle acquiring the sample to be tested, wherein the sample separation platform includes a mechanical arm, a sampling door, and a sample delivery door;

[0013] an opening unit, for controlling the sample separation table to open the sampling door when detecting that the sample transport vehicle is located in the first preset area, and controlling the mechanical arm to grab the sample to be tested on the sample transport vehicle to the sample separation table;

[0014] A sample splitting unit, used to control the sample splitting station to split the sample to be tested, so as to obtain a plurality of sub-samples to be tested corresponding to different testing instruments;

[0015] The second transport unit is used to place the multiple sub-samples to be tested on the sample transport vehicle when it is detected that the sample transport vehicle is located in a second preset area near the sample separation table, and control the sample transport vehicle to transport the multiple sub-samples to be tested to corresponding detection instruments respectively.

[0016] In a third aspect, an embodiment of the present specification provides an electronic device, comprising a processor and a memory; the processor is connected to the memory; the memory is used to store executable program code; the processor runs a program corresponding to the executable program code by reading the executable program code stored in the memory, so as to execute the steps of the nuclear power plant sampling control method described in the first aspect of the above embodiment.

[0017] In a fourth aspect, an embodiment of the present specification provides a computer storage medium, wherein the computer storage medium stores a plurality of instructions, wherein the instructions are suitable for being loaded by a processor and executing the steps of the nuclear power plant sampling control method described in the first aspect of the above embodiment.

[0018] The beneficial effects brought by the technical solutions provided by some embodiments of this specification include at least:

[0019] On the one hand, in the process of testing the samples to be tested, no human intervention is required. The robot arm replaces the human role, and the trolley replaces the transportation role. This can not only avoid the harm to the workers caused by nuclear leakage and contact with radioactive samples, but also improve work efficiency and prevent operational errors caused by human participation. On the other hand, the sample separation table is equipped with a sampling door and a sample delivery door. During the sampling and sample separation process, these two doors are only controlled when transporting samples, and are kept closed at other times, so that the sample separation table is kept closed as much as possible, further preventing the harm to the workers and the surrounding environment caused by the leakage of radioactive samples. BRIEF DESCRIPTION OF THE DRAWINGS

[0020] In order to more clearly illustrate the technical solutions in the embodiments of this specification, the drawings required for use in the embodiments will be briefly introduced below. Obviously, the drawings described below are only some embodiments of this specification. For ordinary technicians in this field, other drawings can be obtained based on these drawings without paying creative work.

[0021] Figure 1 It is an architectural diagram of a sampling system provided in an embodiment of this specification.

[0022] Figure 2 It is a flow chart of a nuclear power plant sampling control method provided in an embodiment of this specification.

[0023] Figure 3a It is a schematic diagram of the exterior of a sample separation platform provided in an embodiment of this specification.

[0024] Figure 3b It is a schematic diagram of the interior of a sample separation platform provided in an embodiment of this specification.

[0025] Figure 4 It is a schematic diagram of a sample temporary storage area and a sample separation operation table provided in an embodiment of this specification.

[0026] Figure 5 It is a schematic diagram of a sample transport vehicle provided in an embodiment of this specification.

[0027] Figure 6 It is a schematic diagram of a sample separation platform in a planar perspective provided in an embodiment of this specification.

[0028] Figure 7 It is a block diagram of a nuclear power plant sampling control device provided in an embodiment of this specification.

[0029] Figure 8 A schematic diagram of the structure of an electronic device provided in an embodiment of this specification.

[0030] In the figure, 11-sample transport vehicle; 12-sample separation platform; 13-first detection instrument; 14-second detection instrument; 31-sampling door; 32-sample delivery door; 311-first support rail; 312-second support rail; 313-first blocking door; 321-third support rail; 322-fourth support rail; 323-second blocking door; 33-mechanical arm; 34-opening device; 35-suction device; 36-guide rail device;

[0031] 401-temporary sample storage area; 402-sample separation operation area; 403-sample separation operation table; 404-temporary storage area for barrel covers;

[0032] 51-sample storage space; 52-trolley mechanical arm;

[0033] 601-container storage device; 602-mobile suction device; 603-cleaning station; 604-temporary storage of barrel lids; 702-first transport unit; 704-opening unit; 706-sample separation unit; 708-second transport unit; 710-generation unit;

[0034] 800 - electronic device; 801 - processor; 802 - communication bus; 803 - user interface; 804 - network interface; 805 - memory. DETAILED DESCRIPTION

[0035] The technical solutions in the embodiments of this specification will be described clearly and completely below in conjunction with the drawings in the embodiments of this specification.

[0036] The terms "first", "second", etc. in the description and claims of this specification and the above-mentioned drawings are used to distinguish different objects, rather than to describe a specific order. In addition, the term "comprising" and any variation thereof are intended to cover non-exclusive inclusions. For example, a process, method, system, product or device comprising a series of steps or units is not limited to the listed steps or units, but optionally also includes steps or units that are not listed, or optionally also includes other steps or units inherent to these processes, methods, products or devices.

[0037] The sampling control method for a nuclear power plant is described in detail below in conjunction with one or more embodiments.

[0038] Radioactive samples refer to wastewater containing radioactive substances, which mainly come from nuclear power generation, nuclear fuel processing, nuclear research and other activities related to nuclear technology. These wastewaters may contain radioactive isotopes of different types and concentrations, and therefore pose a potential threat to the environment and human health. The detection of radioactive samples is an important step in the management of radioactive samples. The detection of radioactive samples mainly includes the determination of their radioactive concentration and physical and chemical properties. Radioactive sample detection is often carried out in the laboratory. Before the radioactive samples are detected, it is necessary to collect the radioactive samples and separate them to prepare for different detection instruments in the laboratory.

[0039] In the related technology, samples to be tested need to be manually sorted and transported. However, when nuclear laboratory staff sample and sort samples to be tested, there is a risk of nuclear radiation leakage and personnel exposure. The manual participation in radioactive sample testing cannot ensure the safety of laboratory staff, is inefficient, and is prone to errors.

[0040] In order to solve the problems existing in the related art, this specification proposes a nuclear power plant sampling control method, device, electronic equipment, and storage medium.

[0041] Combine the following Figure 1 The architecture involved in the sampling control method of the nuclear power plant is described in detail. Figure 1 , Figure 1 Schematic diagram of a sampling system provided by an embodiment of this specification is shown. Figure 1 As shown, the system may include: a sample transport vehicle 11 , a sample separation platform 12 , a first detection instrument 13 , and a second detection instrument 14 .

[0042] The sample transport vehicle 11 is an intelligent electronic vehicle for sample transportation and sample placement. The vehicle is equipped with a communication device for receiving instructions sent by the sampling system and for feeding back the results of instruction execution to the sampling system. The sample transport vehicle 11 also includes a sample storage space for placing samples and a mechanical arm for grabbing samples for placement. The mechanical arm of the sample transport vehicle will be described in detail later and will not be described here.

[0043] The sample separation table 12 is an operating table for sample separation. Sample separation refers to dividing a sample into multiple samples for detection by different detection instruments. The sample separation table 12 is wrapped by an outer shell, and the outer shell includes multiple openable baffles. When the baffles are closed, the sample separation table 12 is in a closed state to avoid the risk of radioactive leakage. The baffles on the outer shell can also be triggered to open due to the sample transportation task of the sample transport vehicle 11. A robotic arm is also installed on the sample separation table 12, which is used to grab the samples placed on the sample transport vehicle and put them on the sample separation table 12 for sample separation.

[0044] The detection instrument is an electronic analysis instrument for detecting samples, and may include, for example: a first detection instrument 13 - a lead can container, and a second detection instrument 14 - a nuclide measuring device. Of course, the detection instrument is not limited thereto, and may also include a pH detection device, etc., which is not limited in this specification.

[0045] On the one hand, the sampling system does not require manual intervention during the testing of samples to be tested. The mechanical arm replaces the manual function, and the trolley replaces the transportation function. This can not only avoid the harm caused by nuclear leakage to the staff, but also improve work efficiency and prevent operational errors caused by manual participation. On the other hand, the sample separation table is equipped with a sampling door and a sample delivery door. During the sampling and sample separation process, these two doors are only controlled when transporting samples, and are kept closed at other times, so that the sample separation table is kept closed as much as possible, further preventing the harm caused by nuclear leakage to the staff.

[0046] See also Figure 2 , Figure 2 A schematic diagram of a nuclear power plant sampling control method provided in an embodiment of this specification is shown. Figure 2 As shown, the nuclear power plant sampling control method is applied to the control module of the sampling system, and the sampling system includes the control module, a sample transport vehicle, a sample separation platform, and multiple detection instruments;

[0047] The nuclear power plant sampling control method may at least include the following steps:

[0048] Step 202: In response to the sample transport vehicle acquiring the sample to be tested, the sample transport vehicle is controlled to transport the sample to be tested to a first preset area near the sample separation platform, wherein the sample separation platform includes a robotic arm, a sampling door, and a sample delivery door.

[0049] The specific method for the control module to confirm that the sample transport vehicle has obtained the sample to be tested can be: a camera is installed in the sample storage space of the sample transport vehicle, and when the camera captures the sample to be tested placed in the sample storage space, the sample transport vehicle is confirmed to have obtained the sample to be tested. Similarly, the specific method for the control module to confirm that the sample transport vehicle is in the first preset area can also be image recognition based on the camera.

[0050] The first preset area and the subsequent second preset area may be an area near the sample separation table preset by the developer of the sampling system.

[0051] like Figure 3a As shown, the sample separation station includes a sampling door 31 and a sample delivery door 32. Figure 3bAs shown, the sample separation station also includes a mechanical arm 33. The sampling door 31 is used to open the sample separation station when the sample transport vehicle transports the sample to be tested to the sample separation station, the sample delivery door 32 is used to open the sample separation station after the sample separation is completed, and the mechanical arm 33 is used to operate during the sample separation process of the sample separation station.

[0052] In one embodiment, the sample separation table is surrounded by a shell, and the shell includes the sampling door and the sample delivery door. The sampling door and / or the sample delivery door include two supporting rails and a baffle door, and the baffle door is slidably connected to the supporting rails.

[0053] like Figure 3a As shown, the housing includes a sampling door 31 and a sample delivery door 32, wherein the sampling door 31 includes a first support rail 311, a second support rail 312 and a first stopper 313, and the sample delivery door 32 includes a third support rail 321, a fourth support rail 322 and a second stopper 323. The first support rail 311 and the second support rail 312 can be arranged vertically so that the first stopper 313 can slide along the rails in the vertical direction; the third support rail 321 and the fourth support rail 322 can be arranged horizontally so that the second stopper 323 can slide along the rails in the horizontal direction. Of course, the installation positions and sliding directions of the sampling door and the sample delivery door can also be interchanged, and this specification does not limit this.

[0054] Step 204: When it is detected that the sample transport vehicle is located in the first preset area, the sample separation platform is controlled to open the sampling door, and the robotic arm is controlled to grab the sample to be tested on the sample transport vehicle and place it on the sample separation platform.

[0055] Step 206: Control the sample splitting station to split the sample to be tested to obtain multiple sub-samples to be tested corresponding to different testing instruments.

[0056] Step 208: When it is detected that the sample transport vehicle is located in a second preset area near the sample separation station, the multiple sub-samples to be tested are placed on the sample transport vehicle, and the sample transport vehicle is controlled to transport the multiple sub-samples to be tested to corresponding testing instruments respectively.

[0057] In this embodiment, on the one hand, in the process of testing the samples to be tested, no human intervention is required, the robot arm replaces the human role, and the trolley replaces the transportation role, which can not only avoid the harm caused by nuclear leakage to the staff, but also improve the work efficiency and prevent the operation errors caused by human participation. On the other hand, the sample separation table is provided with a sampling door and a sample delivery door. In the process of sampling and sample separation, these two doors are controlled only when transporting samples, and are kept closed at other times, so that the sample separation table is kept in a closed state as much as possible, further preventing the harm caused by nuclear leakage to the staff.

[0058] In one embodiment, the sample splitting table includes a sample temporary storage area and a sample splitting operation area. The sample temporary storage area and the first preset area are close to the sampling door, and the sample splitting operation area and the second preset area are close to the sample delivery door.

[0059] like Figure 4 As shown, the sample splitting table may include a sample temporary storage area 401 and a sample splitting operation area 402. The sample temporary storage area 401 and the first preset area are close to the sampling door, and the sample splitting operation area 402 and the second preset area are close to the sample delivery door.

[0060] In this embodiment, by setting the sample temporary storage area and the first preset area close to the sampling door, and setting the sample separation operation area and the second preset area close to the sample delivery door, it helps the sample separation platform to grab the samples to be tested from the sample transport vehicle, and also helps to place the sub-samples to be tested after separation on the sample transport vehicle, thereby improving the efficiency of sample transportation.

[0061] In one embodiment, the control of the sample separation station to separate the samples to be tested includes: in response to a received sample separation request, determining a target detection instrument and a capacity to be tested corresponding to the sample separation request; determining a target container corresponding to the target detection instrument, and controlling the sample separation station to add the sample to be tested of the capacity to be tested into the target container to obtain a sub-sample to be tested corresponding to the sample separation request.

[0062] The condition for triggering the sampling request may be that the nuclear power plant sampling control module receives a request sent by the user; or, when the container carrying the sample to be tested is placed on the sample transport vehicle, the sampling request is automatically triggered, and this specification does not limit this.

[0063] There are many testing instruments, such as pH tester, high-purity germanium spectrometer for nuclide measurement, liquid scintillation spectrometer for tritium measurement, etc. Different testing instruments may be adapted to different containers. Similarly, different testing instruments require different sample capacities.

[0064] Furthermore, the sample separation platform also includes a cover opening device and a suction device, and the samples to be tested are contained in a sample delivery barrel; controlling the sample separation platform to add the samples to be tested of the to-be-tested capacity to the target container includes: controlling the cover opening device to open the barrel lid of the sample delivery barrel, and controlling the suction device to suck the samples to be tested corresponding to the to-be-tested capacity from the sample delivery barrel; controlling the robotic arm to obtain the target container, and controlling the suction device to release the sucked samples to be tested into the target container.

[0065] As shown in FIG3 , the sample separation station further includes a cover opening device 34 and a suction device 35 . The cover opening device 34 is used to open the lid of the sample delivery barrel. The suction device 35 includes a peristaltic pump and a suction head. The peristaltic pump provides power for the suction head to suck the sample to be tested from the sample delivery barrel and release the sample to be tested into the target container.

[0066] Specifically, the mechanical arm 33, the cover opening device 34 and the suction device 35 are all installed on the guide rail device 36 on the top of the sample separation table. The guide rail device 36 includes guide rails and motors that are slidably connected to the mechanical arm 33, the cover opening device 34 and the suction device 35 respectively. The control module of the sampling system can control the motor to drive the mechanical arm 33, the cover opening device 34 and the suction device 35 to slide along the guide rails. Similarly, the cover opening device 34 and the suction device 35 are also provided with chains or guide rail mechanisms, so that the cover opening device 34 and the suction device 35 can extend downward to the vicinity of the sample delivery barrel or the target container.

[0067] Of course, the lid opening device can also be a lid opening mechanical claw installed on a robotic arm. In this case, the specific lid opening process can be: the robotic arm moves to the top of the sample barrel, and the lid opening mechanical claw contacts the barrel lid of the sample barrel and rotates it to open.

[0068] In one embodiment, placing the multiple sub-samples to be tested on the sample transport vehicle includes: controlling the robotic arm to grab the containers containing the multiple sub-samples to be tested and place them on the sample transport vehicle respectively; or controlling the grabbing device on the sample transport vehicle to grab the containers containing the multiple sub-samples to be tested and place them on the sample transport vehicle respectively.

[0069] like Figure 5 As shown, the sample transport vehicle includes a sample storage space 51 and a trolley mechanical arm 52 . In response to the sample transport vehicle receiving a grabbing instruction, the trolley mechanical arm 52 is controlled to grab the sample to be tested from the sample separation table into the sample storage space 51 .

[0070] In one embodiment, each sub-sample to be tested corresponds to a sample number, including: obtaining the test results of each sub-sample to be tested from the multiple testing instruments according to the sample number, and generating a test report for the sub-sample to be tested according to the obtained test results.

[0071] Combine the following Figure 6The process of sample sorting on the sample sorting table is described in detail: the control module controls the robot arm 33 to move to the sample temporary storage area 401, grab the sample barrel and send it to the sample sorting operation table 403. Adjust the cover opening mechanical claw on the robot arm, align the claw with the screw cap of the black sample barrel, and rotate to open the barrel lid. Move the robot arm 33 to put the barrel lid into the barrel lid temporary storage area 404. Move the robot arm 33 to grab a target container in the container storage device 601 and put it into the sample sorting operation table 403. Move the suction device 602 and insert the two suction heads into the black sample barrel and the target container respectively. Turn on the peristaltic pump to extract 1 liter of sample and inject it into the target container. Remove the suction device 602 and generate the sub-sample number to be tested.

[0072] Control the sample transport vehicle to move to the second pre-area, open the sample delivery door, and control the robot arm of the vehicle to grab the sub-sample to be tested and put it into the sample transport vehicle.

[0073] The mobile suction device 602 is used to insert the two suction heads into the cleaning table 603. The cleaning table 603 contains three cleaning nozzles spaced 120 degrees apart. The nozzles are turned on to clean the outside of the suction heads. The solenoid valve installed on the cleaning table 607 is used to close the water pipe under the cleaning table, and the cleaning table is filled with water to clean the internal pipes of the suction heads. The solenoid valve is used to open the water pipe under the cleaning table and drain the cleaning table. The mobile suction device 602 is reset and waits for the next task.

[0074] The mobile robot 33 grabs the barrel cover from the barrel cover temporary storage 404, aligns the gripper with the screw cap of the black sample barrel, and rotates and tightens the barrel cover. The sample barrel is placed in the sample barrel recycling area 604. The mobile robot 33 is reset and waits for the next task.

[0075] In this embodiment, on the one hand, after the suction task of the cover opening device is completed, the suction head is placed in the cleaning station for cleaning, so that the residual sample on the suction head will not affect the next test, thereby ensuring the accuracy of the test; on the other hand, in the process of testing the sample to be tested, no human participation is required, the mechanical arm replaces the human role, and the trolley replaces the transportation role, which can not only avoid the harm caused by nuclear leakage to the staff, but also improve work efficiency and prevent operational errors caused by human participation. In addition, the sample separation table is provided with a sampling door and a sample delivery door. In the process of sampling and sample separation, these two doors are controlled only when transporting samples, and are kept closed at other times, so that the sample separation table is kept in a closed state as much as possible, further preventing the harm caused by nuclear leakage to the staff.

[0076] See also Figure 7 , Figure 7 A block diagram of a nuclear power plant sampling control device provided in an embodiment of this specification. A control module applied to a sampling system, the sampling system includes the control module, a sample transport vehicle, a sample separation platform, and multiple detection instruments;

[0077] The nuclear power plant sampling control device comprises:

[0078] The first transport unit 702 is used for controlling the sample transport vehicle to transport the sample to be tested to a first preset area near the sample separation platform in response to the sample transport vehicle acquiring the sample to be tested, wherein the sample separation platform includes a mechanical arm, a sampling door and a sample delivery door;

[0079] The opening unit 704 is used to control the sample separation table to open the sampling door when it is detected that the sample transport vehicle is located in the first preset area, and control the mechanical arm to grab the sample to be tested on the sample transport vehicle to the sample separation table;

[0080] The sample splitting unit 706 is used to control the sample splitting station to split the sample to be tested, so as to obtain multiple sub-samples to be tested corresponding to different testing instruments;

[0081] The second transport unit 708 is used to place the multiple sub-samples to be tested on the sample transport vehicle when it is detected that the sample transport vehicle is located in a second preset area near the sample separation table, and control the sample transport vehicle to transport the multiple sub-samples to be tested to corresponding detection instruments respectively.

[0082] Optionally, the sample separation table includes a sample temporary storage area and a sample separation operation area, the sample temporary storage area and the first preset area are close to the sampling door, and the sample separation operation area and the second preset area are close to the sample delivery door.

[0083] Optionally, the sampling unit 706 is specifically used for:

[0084] In response to the received sample splitting request, determining the target detection instrument and the capacity to be detected corresponding to the sample splitting request;

[0085] The target container corresponding to the target detection instrument is determined, and the sample separation station is controlled to add the sample to be tested of the test capacity into the target container to obtain the sub-sample to be tested corresponding to the sample separation request.

[0086] Optionally, the sample separation station further includes a cover opening device and a suction device, and the sample to be tested is contained in a sample delivery barrel; the sample separation unit 706 is specifically used for:

[0087] Controlling the cover opening device to open the cover of the sample delivery barrel, and controlling the suction device to suck the sample to be tested corresponding to the volume to be tested from the sample delivery barrel;

[0088] The robot arm is controlled to acquire the target container, and the suction device is controlled to release the sucked sample to be tested into the target container.

[0089] Optionally, the sample separation table is surrounded by an outer shell, the outer shell includes the sampling door and the sample delivery door, the sampling door and / or the sample delivery door includes two supporting rails and a baffle door, and the baffle door is slidably connected to the supporting rails.

[0090] Optionally, the second transport unit 708 is specifically used for:

[0091] Control the robot arm to grab the containers containing the multiple sub-samples to be tested and place them on the sample transport vehicle; or,

[0092] The grabbing device on the sample transport vehicle is controlled to grab the containers containing the multiple sub-samples to be tested and place them on the sample transport vehicle respectively.

[0093] Optionally, each sub-sample to be tested corresponds to a sample number, and also includes:

[0094] The generating unit 710 is used to obtain the test results of each sub-sample to be tested from the multiple testing instruments according to the sample number, and generate a test report of the sub-sample to be tested according to the obtained test results.

[0095] In this embodiment, on the one hand, in the process of testing the samples to be tested, no manual intervention is required, the mechanical arm replaces the manual function, and the trolley replaces the transportation function, which can not only avoid the harm caused by the leakage of radioactive samples to the staff, but also improve the work efficiency and prevent the operation errors caused by manual participation. On the other hand, the sample separation table is provided with a sampling door and a sample delivery door. In the process of sampling and sample separation, these two doors are controlled only when the samples are transported, and are kept closed at other times, so that the sample separation table is kept in a closed state as much as possible, further preventing the harm caused by nuclear leakage to the staff.

[0096] Each embodiment in this specification is described in a progressive manner, and the same or similar parts between the embodiments can be referred to each other, and each embodiment focuses on the differences from other embodiments. In particular, for the embodiment of the nuclear power plant sampling control device, since it is basically similar to the embodiment of the nuclear power plant sampling control method, the description is relatively simple, and the relevant parts can be referred to the partial description of the method embodiment.

[0097] See also Figure 8 A schematic diagram of the structure of an electronic device provided in an embodiment of this specification is shown.

[0098] like Figure 8 As shown, the electronic device 800 may include: at least one processor 801 , at least one network interface 804 , a user interface 803 , a memory 805 , and at least one communication bus 802 .

[0099] The communication bus 802 may be used to realize the connection and communication among the above-mentioned components.

[0100] The user interface 803 may include buttons, and the optional user interface may also include a standard wired interface or a wireless interface.

[0101] The network interface 804 may include, but is not limited to, a Bluetooth module, an NFC module, a Wi-Fi module, etc.

[0102] Among them, the processor 801 may include one or more processing cores. The processor 801 uses various interfaces and lines to connect various parts within the entire electronic device 800, and executes various functions and processes data of the electronic device 800 by running or executing instructions, programs, code sets or instruction sets stored in the memory 805, and calling data stored in the memory 805. Optionally, the processor 801 can be implemented in at least one hardware form of DSP, FPGA, and PLA. The processor 801 can integrate one or a combination of CPU, GPU, modem, etc. Among them, the CPU mainly processes the operating system, user interface, and application programs; the GPU is responsible for rendering and drawing the content to be displayed on the display screen; the modem is used to handle wireless communications. It can be understood that the above-mentioned modem may not be integrated into the processor 801, and it can be implemented separately through a chip.

[0103] Among them, the memory 805 may include RAM or ROM. Optionally, the memory 805 includes a non-transitory computer-readable medium. The memory 805 can be used to store instructions, programs, codes, code sets or instruction sets. The memory 805 may include a program storage area and a data storage area, wherein the program storage area may store instructions for implementing an operating system, instructions for at least one function (such as a touch function, a sound playback function, an image playback function, etc.), instructions for implementing the above-mentioned various method embodiments, etc.; the data storage area may store data involved in the above-mentioned various method embodiments, etc. The memory 805 may also be at least one storage device located away from the aforementioned processor 801. The memory 805 as a computer storage medium may include an operating system, a network communication module, a user interface module, and a nuclear power plant sampling control application. The processor 801 may be used to call the nuclear power plant sampling control application stored in the memory 805 and execute the steps of nuclear power plant sampling control mentioned in the above-mentioned embodiments.

[0104] The embodiment of the present specification also provides a computer-readable storage medium, in which instructions are stored. When the instructions are executed on a computer or a processor, the computer or the processor executes the above Figure 2One or more steps in the illustrated embodiment. If the components of the electronic device described above are implemented in the form of software functional units and sold or used as independent products, they can be stored in the computer-readable storage medium.

[0105] In the above embodiments, it can be implemented in whole or in part by software, hardware, firmware or any combination thereof. When implemented using software, it can be implemented in whole or in part in the form of a computer program product. The computer program product includes one or more computer instructions. When the computer program instructions are loaded and executed on a computer, the process or function described in the embodiment of this specification is generated in whole or in part. The computer can be a general-purpose computer, a special-purpose computer, a computer network, or other programmable device. The computer instructions can be stored in a computer-readable storage medium or transmitted through the computer-readable storage medium. The computer instructions can be transmitted from a website site, computer, server or data center to another website site, computer, server or data center by wired (e.g., coaxial cable, optical fiber, digital subscriber line (Digital Subscriber Line, DSL)) or wireless (e.g., infrared, wireless, microwave, etc.) mode. The computer-readable storage medium can be any available medium that a computer can access or a data storage device such as a server, data center, etc. that contains one or more available media integrated. The available medium may be a magnetic medium (eg, a floppy disk, a hard disk, a magnetic tape), an optical medium (eg, a digital versatile disc (DVD)), or a semiconductor medium (eg, a solid state disk (SSD)).

[0106] Those skilled in the art can understand that all or part of the processes in the above-mentioned embodiments can be implemented by instructing the relevant hardware through a computer program, and the program can be stored in a computer-readable storage medium. When the program is executed, it can include the processes of the embodiments of the above-mentioned methods. The aforementioned storage medium includes: ROM, RAM, magnetic disk or optical disk and other media that can store program codes. In the absence of conflict, the technical features in this embodiment and the implementation scheme can be combined arbitrarily.

[0107] The embodiments described above are merely preferred embodiments of this specification and are not intended to limit the scope of this specification. Without departing from the design spirit of this specification, various modifications and improvements made to the technical solutions of this specification by ordinary technicians in this field should fall within the scope of protection determined by the claims of this specification.

Claims

1. A nuclear power plant sampling control method, characterized in that: A control module applied to a sampling system, wherein the sampling system comprises the control module, a sample transport vehicle, a sample separation platform, and a plurality of detection instruments. The nuclear power plant sampling control method comprises the following steps: In response to the sample transport vehicle acquiring the sample to be tested, controlling the sample transport vehicle to transport the sample to be tested to a first preset area near the sample separation platform, wherein the sample separation platform includes a mechanical arm, a sampling door, and a sample delivery door; When it is detected that the sample transport vehicle is located in the first preset area, the sample separation platform is controlled to open the sampling door, and the mechanical arm is controlled to grab the sample to be tested on the sample transport vehicle and place it on the sample separation platform; Controlling the sample splitting station to split the sample to be tested, so as to obtain a plurality of sub-samples to be tested corresponding to different testing instruments; When it is detected that the sample transport vehicle is located in a second preset area near the sample separation station, the multiple sub-samples to be tested are placed on the sample transport vehicle, and the sample transport vehicle is controlled to transport the multiple sub-samples to be tested to corresponding detection instruments respectively.

2. A nuclear power plant sampling control method according to claim 1, characterized in that: The sample splitting table includes a sample temporary storage area and a sample splitting operation area. The sample temporary storage area and the first preset area are close to the sampling door, and the sample splitting operation area and the second preset area are close to the sample delivery door.

3. A nuclear power plant sampling control method according to claim 1, characterized in that: The controlling the sample separation platform to separate the samples to be tested comprises: In response to the received sample splitting request, determining the target detection instrument and the capacity to be detected corresponding to the sample splitting request; The target container corresponding to the target detection instrument is determined, and the sample separation station is controlled to add the sample to be tested of the test capacity into the target container to obtain the sub-sample to be tested corresponding to the sample separation request.

4. A nuclear power plant sampling control method according to claim 3, characterized in that: The sample separation station also includes a cover opening device and a suction device. The sample to be tested is contained in a sample delivery barrel. The control of the sample separation station to add the sample to be tested in the test volume to the target container includes: Controlling the cover opening device to open the cover of the sample delivery barrel, and controlling the suction device to suck the sample to be tested corresponding to the volume to be tested from the sample delivery barrel; The robot arm is controlled to acquire the target container, and the suction device is controlled to release the sucked sample to be tested into the target container.

5. A nuclear power plant sampling control method according to claim 1, characterized in that: The sample dividing platform is surrounded by an outer shell, and the outer shell includes the sampling door and the sample delivery door. The sampling door and / or the sample delivery door include two supporting rails and a blocking door, and the blocking door is slidably connected to the supporting rails.

6. A nuclear power plant sampling control method according to claim 1, characterized in that: Placing the plurality of sub-samples to be tested on the sample transport vehicle comprises: Control the robot arm to grab the containers containing the multiple sub-samples to be tested and place them on the sample transport vehicle; or, The grabbing device on the sample transport vehicle is controlled to grab the containers containing the multiple sub-samples to be tested and place them on the sample transport vehicle respectively.

7. A nuclear power plant sampling control method according to claim 1, characterized in that: Each sub-sample to be tested has a corresponding sample number, which also includes: The test results of each sub-sample to be tested are obtained from the multiple testing instruments according to the sample numbers, and a test report of the sample to be tested is generated according to the obtained test results.

8. A nuclear power plant sampling control device, characterized in that: A control module applied to a sampling system, wherein the sampling system comprises the control module, a sample transport vehicle, a sample separation platform, and a plurality of detection instruments. The nuclear power plant sampling control device comprises: A first transport unit, configured to control the sample transport vehicle to transport the sample to be tested to a first preset area near the sample separation platform in response to the sample transport vehicle acquiring the sample to be tested, wherein the sample separation platform includes a mechanical arm, a sampling door, and a sample delivery door; an opening unit, for controlling the sample separation table to open the sampling door when detecting that the sample transport vehicle is located in the first preset area, and controlling the mechanical arm to grab the sample to be tested on the sample transport vehicle to the sample separation table; A sample splitting unit, used to control the sample splitting station to split the sample to be tested, so as to obtain a plurality of sub-samples to be tested corresponding to different testing instruments; The second transport unit is used to place the multiple sub-samples to be tested on the sample transport vehicle when it is detected that the sample transport vehicle is located in a second preset area near the sample separation table, and control the sample transport vehicle to transport the multiple sub-samples to be tested to corresponding detection instruments respectively.

9. An electronic device, characterized in that: including a processor and a memory; The processor is connected to the memory; The memory is used to store executable program code; The processor runs a program corresponding to the executable program code by reading the executable program code stored in the memory, so as to execute the method according to any one of claims 1 to 7.

10. A computer-readable storage medium having a computer program stored thereon, characterized in that: When the computer program is executed by a processor, the method according to any one of claims 1 to 7 is implemented.