Gamma scanning device and measuring equipment for radioactive waste barrel of nuclear power plant

Abstract

The utility model discloses a nuclear power plant radioactive waste barrel gamma scanning device and measuring equipment, and the nuclear power plant radioactive waste barrel gamma scanning device comprises a supporting seat, a sealing cover, a rotating disc, a control mechanism and a fixing assembly. The sealing cover is detachably mounted on the supporting seat, and a sealing cavity is formed between the sealing cover and the supporting seat; the turntable is detachably mounted on the supporting seat and rotates in the sealing cavity; the fixing assembly is installed on the rotating disc, the radioactive waste barrel is detachably fixed to the rotating disc, and the axis of the radioactive waste barrel is parallel to the plane of the rotating disc. Therefore, the total activity of the radioactive raw material in the radioactive waste barrel can be quickly obtained only through twice measurement, the measurement efficiency and the accuracy of activity reconstruction are improved, the layering frequency is reduced, and the measurement time is saved.

Description

Technical Field

[0001] This utility model relates to the field of nuclear power measurement technology, and in particular to a gamma scanning device and measuring equipment for radioactive waste bins in nuclear power plants. Background Technology

[0002] Nuclear power plants generate a large amount of low-level radioactive waste during operation. Before final disposal, it is necessary to measure its radioactivity, mainly through the inherent radioactivity of the nuclear material itself or the radioactivity induced by external nuclear reactions.

[0003] Nuclear power plants typically perform layered scanning of waste bins, dividing the waste bins into several layers, reconstructing the activity of each layer, and then summing them to obtain the total activity. This method is prone to interlayer crosstalk due to the distribution of collimator openings and the distance between the detector and the bin, leading to measurement errors. Utility Model Content

[0004] The technical problem to be solved by this utility model is to provide a gamma scanning device and measuring equipment for radioactive waste bins in nuclear power plants.

[0005] The technical solution adopted by this utility model to solve its technical problem is as follows: A gamma scanning device for a radioactive waste bin in a nuclear power plant is constructed, comprising: a support base, a sealing cover, a turntable, a control mechanism, and a fixing component; the sealing cover is detachably installed on the support base, forming a sealed cavity between the cover and the support base; the turntable is detachably installed on the support base and rotates within the sealed cavity; the fixing component is installed on the turntable, detachably fixing the radioactive waste bin to the turntable, such that the axis of the radioactive waste bin is parallel to the plane of the turntable; the control mechanism includes: a measurement module and a drive module; the measurement module is installed on the support base perpendicular to the axis of the radioactive waste bin, and the measurement module passes through the sealing cover to perform radioactive measurements on the radioactive waste bin in the sealed cavity; the drive module is detachably installed on the support base, driving the turntable to rotate in a direction perpendicular to the axis of the radioactive waste bin.

[0006] Furthermore, the support base includes: a support frame, an operating platform, and a conveying assembly. The operating platform is detachably mounted on the support frame, forming the sealing cavity between itself and the sealing cover. The conveying assembly is mounted on the operating platform, and the turntable is rotatably connected to the conveying assembly, driving the turntable to reciprocate between the outside and the sealing cavity.

[0007] Furthermore, the conveying assembly includes: a guide rail, a slide block, and a limiting member. The guide rail is mounted on the operating platform, the slide block is slidably connected to the guide rail, the turntable is rotatably connected to the slide block, and the limiting member is slidably connected to the operating platform, thereby restricting the movement of the slide block after the turntable moves into the sealed cavity.

[0008] Furthermore, the fixing component includes: clamping blocks and locking elements. The turntable has a sliding groove, and at least two clamping blocks are slidably connected to the sliding grooves on both sides of the radioactive waste bin. The locking elements are installed on the turntable to restrict the sliding of the clamping blocks.

[0009] Furthermore, the locking component includes a mounting base and a screw. The mounting base is fixedly mounted on the turntable. The screw is connected to the mounting base via a threaded joint, and one end of the screw is rotatably connected to the corresponding clamping block, driving and restricting the movement of the clamping block.

[0010] Furthermore, the sealing cover includes an isolation cover and an isolation door. The isolation cover is detachably mounted on the operating platform. The isolation cover is provided with a notch that allows the turntable to reciprocate between the outside and the sealing cavity. The isolation door is rotatably connected to the isolation cover to open or close the notch.

[0011] Furthermore, the sealing cover also includes a transparent panel and a handle mounted on the isolation door.

[0012] Furthermore, the drive module includes a motor and a friction wheel. The motor is detachably mounted on the support base. The friction wheel is installed in the sealed cavity and connected to the motor. After the turntable moves into the sealed cavity, the friction wheel contacts the turntable, and the friction wheel drives the turntable to rotate in a direction perpendicular to the axis of the radioactive waste container through friction.

[0013] In addition, this utility model also provides a gamma measurement device for radioactive waste bins in nuclear power plants, including the aforementioned gamma scanning device for radioactive waste bins in nuclear power plants, and a radioactive waste bin, wherein the radioactive waste bin is placed horizontally in the gamma scanning device for radioactive waste bins in nuclear power plants.

[0014] Furthermore, the gamma measurement equipment for the radioactive waste bins in nuclear power plants also includes: a human-machine interaction module, a data acquisition and management module, a gamma energy spectrum analysis module, a passive efficiency calibration module, and a communication interface.

[0015] The following are the beneficial effects of implementing this utility model:

[0016] This application detachably fixes the radioactive waste container to a turntable, ensuring that the axis of the radioactive waste container is parallel to the plane of the turntable. The control mechanism includes a measurement module and a drive module. The measurement module is mounted on a support base perpendicular to the axis of the radioactive waste container. The measurement module passes through a sealed cover to perform radioactivity measurements on the radioactive waste container within the sealed cavity. Thus, only two measurements are needed to quickly obtain the total activity of the radioactive material in the radioactive waste container, improving measurement efficiency and the accuracy of activity reconstruction, reducing the number of stratification steps, and saving measurement time. Attached Figure Description

[0017] To more clearly illustrate the technical solution of this utility model, the present 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 some embodiments of this utility model and should not be regarded as a limitation on the scope. For those skilled in the art, other related drawings can be obtained from these drawings without creative effort.

[0018] In the attached image:

[0019] Figure 1 This is a three-dimensional structural schematic diagram of the gamma measurement device for radioactive waste bins in nuclear power plants in some embodiments of this utility model;

[0020] Figure 2 This is a cross-sectional view of the sealing cover in this utility model;

[0021] Figure 3 This is a three-dimensional structural schematic diagram of the gamma scanning device for the radioactive waste bins in nuclear power plants in this utility model;

[0022] Figure 4 This is a cross-sectional schematic diagram of the gamma scanning device for the radioactive waste bins in nuclear power plants in this utility model;

[0023] Figure 5 This is a structural schematic diagram of the turntable and locking component in this utility model.

[0024] Explanation of markings in the diagram

[0025] Support base 1, support frame 11, operating platform 12, conveying assembly 13, guide rail 131, slide 132, limiting component 133, sealing cover 2, isolation cover 21, isolation door 22, transparent plate 23, handle 24, turntable 3, control mechanism 4, measuring module 41, drive module 42, motor 421, friction wheel 422, fixing assembly 5, clamping block 51, locking component 52, mounting base 521, screw 522, slide groove 53, sealing cavity 6, radioactive waste bin 7. Detailed Implementation

[0026] To provide a clearer understanding of the technical features, objectives, and effects of this utility model, the specific embodiments of this utility model are now described in detail with reference to the accompanying drawings. In the following description, it should be understood that the orientations or positional relationships indicated by terms such as "front," "rear," "upper," "lower," "left," "right," "longitudinal," "horizontal," "vertical," "horizontal," "top," "bottom," "inner," "outer," "head," and "tail" are based on the orientations or positional relationships shown in the accompanying drawings, and are constructed and operated in a specific orientation. They are only for the convenience of describing this technical solution and do not indicate that the device or component referred to must have a specific orientation; therefore, they should not be construed as limitations on this utility model.

[0027] It should also be noted that, unless otherwise explicitly specified and limited, terms such as "installation," "connection," "joining," "fixing," and "setting" should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral part; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; they can refer to the internal communication of two components or the interaction between two components. When an component is referred to as being "on" or "below" another component, the component can be located "directly" or "indirectly" on the other component, or there may be one or more intermediary components. The terms "first," "second," "third," etc., are only for the convenience of describing this technical solution and should not be construed as indicating or implying relative importance or implicitly specifying the number of indicated technical features. Therefore, features defined with "first," "second," "third," etc., may explicitly or implicitly include one or more of that feature. For those skilled in the art, the specific meaning of the above terms in this utility model can be understood according to the specific circumstances.

[0028] In the following description, specific details such as particular system structures and techniques are set forth for illustrative purposes and not for limitation, in order to provide a thorough understanding of the embodiments of the present invention. However, those skilled in the art will understand that the present invention can be implemented in other embodiments without these specific details. In other instances, detailed descriptions of well-known systems, apparatuses, circuits, and methods are omitted so as not to obscure the description of the present invention with unnecessary detail.

[0029] Please see Figures 1 to 3The first embodiment of this utility model discloses a gamma scanning device for a radioactive waste bin in a nuclear power plant. This device includes: a support base 1, a sealing cover 2, a turntable 3, a control mechanism 4, and a fixing assembly 5. The sealing cover 2 is detachably mounted on the support base 1, forming a sealed cavity 6 between the cover and the support base 1. The turntable 3 is detachably mounted on the support base 1 and rotates within the sealed cavity 6. The fixing assembly 5 is mounted on the turntable 3, detachably fixing the radioactive waste bin 7 to the turntable 3, such that the axis of the radioactive waste bin 7 is parallel to the plane of the turntable 3. The control mechanism 4 includes: a measurement module 41 and a drive module 42. The measurement module 41 is mounted on the support base 1 perpendicular to the axis of the radioactive waste bin 7. The measurement module 41 passes through the sealing cover 2 to perform radioactive measurements on the radioactive waste bin 7 within the sealed cavity 6. The drive module 42 is detachably mounted on the support base 1, driving the turntable 3 to rotate in a direction perpendicular to the axis of the radioactive waste bin 7.

[0030] This application detachably fixes the radioactive waste container 7 to the turntable 3, making the axis of the radioactive waste container 7 parallel to the plane of the turntable 3. The control mechanism 4 includes a measurement module 41 and a drive module 42. The measurement module 41 is mounted on the support base 1 perpendicular to the axis of the radioactive waste container 7. The measurement module 41 passes through the sealing cover 2 to perform radioactive measurements on the radioactive waste container 7 in the sealed cavity 6. The drive module 42 is detachably mounted on the support base 1 and drives the turntable 3 to rotate in a direction perpendicular to the axis of the radioactive waste container 7. In this process, radioactive waste container 7 collects radioactive materials, is weighed, and then placed horizontally on a turntable 3 in a sealed cavity 6, with the axis of the radioactive waste container 7 parallel to the plane of the turntable 3. The radioactive waste container 7 is fixed to the turntable 3 by a fixing component 5. Then, the drive module 42 is activated to rotate the turntable 3 in a direction perpendicular to the axis of the radioactive waste container 7. The measurement module 41 measures the count rate C1 while the radioactive waste container 7 is rotating. The source is considered as upper and lower parts, and under the assumption of uniform radioactive distribution, the efficiency of the upper and lower parts of the source is calibrated separately. After the first measurement, the radioactive waste container 7 is rotated around its circumference so that the side originally closer to the turntable 3 faces the measurement module 41. The measurement module 41 then measures the count rate C2 again on the axis perpendicular to the radioactive waste container 7. The measurement module 41 records the values ​​of C1 and C2. The measurement module 41 automatically substitutes the values ​​of C1 and C2 into the formula:

[0031] C1=A1*E1+A2*E2, C2=A2*E1+A1*E2.

[0032] In this context, we assume that the total activity of the upper half is A1 and the activity of the lower half is A2, where A1 and A2 are unknowns.

[0033] E1 and E2 are known values ​​obtained from tables in the prior art based on the activities A of C1 and C2 fixed under ideal conditions. The tables for looking up E1 and E2 can be pre-entered into the measurement module 41, and the corresponding values ​​are automatically looked up and recorded based on C1 and C2 during measurement, and substituted into the formula.

[0034] E1, E2, C1, and C2 are all known values. By substituting them into the above formulas, the measurement module 41 automatically solves the two formulas into a linear equation with two variables, obtaining A1 and A2. These are then substituted into A1 + A2 = A to obtain the total activity A of the radioactive material in the entire radioactive waste container 7. This is displayed in the measurement module 41. Therefore, only two measurements are needed to quickly obtain the total activity A of the radioactive material in the radioactive waste container 7, reducing cross-contamination interference and improving measurement efficiency and the accuracy of activity reconstruction.

[0035] Specifically, the axis of the radioactive waste bin 7 is fixed parallel to the plane of the turntable 3. When the turntable 3 rotates in a direction perpendicular to the axis of the radioactive waste bin 7, the distance from the top to the bottom of the radioactive waste bin 7 in the direction perpendicular to the axis is reduced, thereby reducing the number of layers and saving measurement time. Each horizontal layering makes the distance between the layer and the measurement module 41 more uniform, and it is less likely to produce dead angles after rotation, thereby improving the accuracy of the measurement values.

[0036] Please see Figures 1 to 3 In some embodiments, the support base 1 includes: a support frame 11, an operating platform 12 and a conveying assembly 13. The operating platform 12 is detachably mounted on the support frame 11, forming a sealed cavity 6 between itself and the sealing cover 2. The conveying assembly 13 is mounted on the operating platform 12, and the turntable 3 is rotatably connected to the conveying assembly 13, driving the turntable 3 to reciprocate between the outside and the sealed cavity 6.

[0037] This application utilizes an operating platform 12 detachably mounted on a support frame 11, forming a sealed cavity 6 between the platform and the sealing cover 2. A conveying assembly 13 is mounted on the operating platform 12, and a turntable 3 is rotatably connected to the conveying assembly 13, causing the turntable 3 to reciprocate between the external environment and the sealed cavity 6. The conveying assembly 13 reduces the contact time between the operator and the radioactive waste container 7, thereby reducing the risk of radioactive contamination and providing some protection. The sealed cavity 6 formed between the operating platform 12 and the sealing cover 2 further prevents the spread of radioactive materials, thus protecting the surrounding environment and reducing its influence on measurement values, further improving the accuracy of the measurements. The operating platform 12 facilitates the placement of the radioactive waste container 7 onto the turntable 3, preventing it from falling and improving safety.

[0038] Please see Figures 1 to 4 In some embodiments, the conveying assembly 13 includes a guide rail 131, a slide 132, and a limiting member 133. The guide rail 131 is mounted on the operating platform 12, the slide 132 is slidably connected to the guide rail 131, the turntable 3 is rotatably connected to the slide 132, and the limiting member 133 is slidably connected to the operating platform 12 to restrict the movement of the slide 132 after the turntable 3 moves into the sealed cavity 6.

[0039] This application utilizes a guide rail 131 to mount the device on the operating platform 12. A slide block 132 is slidably connected to the guide rail 131, and a turntable 3 is rotatably connected to the slide block 132. A limiting member 133 is slidably connected to the operating platform 12, restricting the movement of the slide block 132 after the turntable 3 moves into the sealed cavity 6. The operator clamps the radioactive waste container 7 onto the turntable 3 using the fixing component 5, and then pushes the slide block 132, causing it to move along the guide rail 131 and drive the turntable 3 into the sealed cavity 6 under inertia. After the sealed cavity 6 is sealed, measurements are taken. The cooperation between the slide block 132 and the guide rail 131 allows the operator to place the radioactive waste container 7 into the sealed cavity 6 more easily, reducing the contact time with the radioactive waste container 7 and thus protecting the operator during movement. The sliding block 132 and the guide rail 131 do not require electrical components to cooperate, which can avoid interference from radioactive materials and affect the smoothness of operation, further improving safety and making the cost more affordable and reliable.

[0040] The sliding limiter 133 blocks the slide block 132, which can stably restrict the slide block 132 in the sealed cavity 6, thereby improving the stability during measurement and facilitating operation.

[0041] Please see Figures 1 to 5 In some embodiments, the fixing component 5 includes: a clamping block 51 and a locking member 52. The turntable 3 has a sliding groove 53. At least two clamping blocks 51 are slidably connected in the sliding grooves 53 on both sides of the radioactive waste bin 7. The locking member 52 is installed on the turntable 3 to restrict the sliding of the clamping blocks 51.

[0042] This application utilizes a rotary table 3 with grooves 53. At least two clamping blocks 51 are slidably connected to the grooves 53 on both sides of the radioactive waste container 7. Locking elements 52 are installed on the rotary table 3 to restrict the sliding of the clamping blocks 51. After the clamping blocks 51 on both sides come into contact with the radioactive waste container 7, the locking elements 52 restrict the sliding of the clamping blocks 51, thus fixing the radioactive waste container 7 on the rotary table 3. This reduces the shaking of the radioactive waste container 7 when the rotary table 3 is rotated, improves stability, and thus improves the accuracy of measurement. It also improves safety, facilitates operation, and is more cost-effective and reliable.

[0043] Among them, the locking component 52 can be a bolt or screw, which saves manufacturing costs, has a simple and reliable structure, and is convenient for clamping and fixing the radioactive waste container 7, thereby improving the efficiency of measurement.

[0044] Please see Figures 1 to 5 In some embodiments, the locking element 52 includes a mounting base 521 and a screw 522. The mounting base 521 is fixedly mounted on the turntable 3, and the screw 522 is connected to the mounting base 521 by a threaded pair. One end of the screw 522 is rotatably connected to the corresponding clamping block 51, driving and restricting the movement of the clamping block 51.

[0045] This application utilizes a mounting base 521 to fix the device onto the turntable 3. A screw 522 is connected to the mounting base 521 via a threaded connection. One end of the screw 522 is rotatably connected to a corresponding clamping block 51, driving and restricting the movement of the clamping block 51. After placing the radioactive waste container 7 onto the turntable 3, the operator can rotate the screw 522 to move it back and forth on the mounting base 521. This causes the screw 522 to move the clamping block 51 closer to or further away from the radioactive waste container 7, detachably clamping the radioactive waste container 7 onto the turntable 3. This facilitates clamping by the operator, improves measurement efficiency, and allows for clamping of radioactive waste containers 7 of different sizes, expanding the applicable range and making operation more convenient.

[0046] Please see Figures 1 to 4 In some embodiments, the sealing cover 2 includes an isolation cover 21 and an isolation door 22. The isolation cover 21 is detachably mounted on the operating platform 12. The isolation cover 21 is provided with a notch that allows the turntable 3 to reciprocate between the outside and the sealing cavity 6. The isolation door 22 is rotatably connected to the isolation cover 21 to open or close the notch.

[0047] This application utilizes an isolation cover 21 that is detachably mounted on the operating platform 12. The isolation cover 21 has a notch that allows the turntable 3 to reciprocate between the outside and the sealed cavity 6. An isolation door 22 is rotatably connected to the isolation cover 21, opening or closing the notch. The notch in the isolation cover 21 facilitates the placement of the radioactive waste container 7 into the sealed cavity 6 by the conveying assembly 13, thereby improving measurement efficiency. The isolation door 22 keeps the sealed cavity 6 sealed, facilitating operation. The isolation door 22 can rotate on the upper part of the isolation cover 21 and is kept open or closed by a spring or cylinder, reducing its footprint and making the structure more compact. It also prevents accidental contact by unauthorized personnel, thus improving safety. After closing, the isolation door 22 can be locked with a pin or bolt, further enhancing sealing and safety.

[0048] Please see Figures 1 to 4In some embodiments, the sealing cover 2 also includes a transparent panel 23 and a handle 24 mounted on the isolation door 22.

[0049] This application improves the accuracy and safety of measurement values ​​by installing a transparent plate 23 and a handle 24 on the isolation door 22. The transparent plate 23 allows the operator to observe the measurement status of the radioactive waste container 7 inside the sealed cavity 6. If the radioactive waste container 7 is observed to be separated from the turntable 3 or to malfunction, the operation of the device can be stopped in time.

[0050] This application uses a handle 24 installed on the isolation door 22 to facilitate the operator to open and close the isolation door 22, thereby improving the efficiency of measurement, making operation more labor-saving, and reducing labor intensity.

[0051] Please see Figures 1 to 4 In some embodiments, the drive module 42 includes a motor 421 and a friction wheel 422. The motor 421 is detachably mounted on the support base 1. The friction wheel 422 is installed in the sealed cavity 6 and connected to the motor 421. After the turntable 3 moves into the sealed cavity 6, the friction wheel 422 contacts the turntable 3. The friction wheel 422 drives the turntable 3 to rotate in a direction perpendicular to the axis of the radioactive waste container 7 through friction.

[0052] This application uses a friction wheel 422 installed in the sealed cavity 6 and connected to a motor 421. After the turntable 3 moves into the sealed cavity 6, the friction wheel 422 contacts the turntable 3, and the friction wheel 422 drives the turntable 3 to rotate in a direction perpendicular to the axis of the radioactive waste container 7 through friction. After the slide 132 drives the radioactive waste container 7 into the sealed cavity 6 via the turntable 3, the side of the turntable 3 contacts the side of the friction wheel 422. Then, the movement of the turntable 3 is restricted by the limiting member 133, so that the turntable 3, the slide 132 and the friction wheel 422 remain relatively stationary. Then, the operator closes the isolation door 22 by holding the handle 24 and starts the drive module 42, so that the motor 421 drives the friction wheel 422 to rotate. The rotating friction wheel 422 drives the turntable 3 to rotate, so that the radioactive waste container 7 on the turntable 3 rotates while being measured, which facilitates operation and improves measurement efficiency. In particular, the friction between the friction wheel 422 and the turntable 3 allows the turntable 3 to easily drive the radioactive waste container 7 to reciprocate into the sealed cavity 6, avoiding obstruction between the radioactive waste container 7 and the measurement module 41, and further improving the accuracy of the measurement.

[0053] Please see Figures 1 to 4In some embodiments, a gamma measurement device for radioactive waste bins of nuclear power plants is also provided. The gamma measurement device for radioactive waste bins of nuclear power plants includes the gamma scanning device for radioactive waste bins of nuclear power plants described in the above embodiments, and a radioactive waste bin 7, which is placed horizontally in the gamma scanning device for radioactive waste bins of nuclear power plants.

[0054] This application allows for the rapid acquisition of the total activity A of radioactive materials in the radioactive waste container 7 by placing the radioactive waste container 7 horizontally within the gamma scanning device of the radioactive waste container in a nuclear power plant. The horizontal placement of the radioactive waste container 7 increases the measurement area of ​​the measurement module 41, thereby avoiding interference from cross-layers through the large-area measurement module 41, and improving the measurement efficiency and numerical accuracy.

[0055] Please see Figures 1 to 5 In some embodiments, the gamma measurement device for radioactive waste bins in nuclear power plants further includes: a human-machine interaction module, a data acquisition and management module, a gamma spectrum analysis module, a passive efficiency calibration module, and a communication interface.

[0056] This application utilizes a human-computer interaction module, a data acquisition and management module, a gamma spectrum analysis module, a passive efficiency calibration module, and a communication interface. The gamma spectrum analysis module performs detector spectrum analysis, while the passive efficiency calibration module obtains the efficiency calibration factor without the need for relative measurements using a standard source, enabling rapid acquisition of efficiency calibration curves for complex radioactive waste. The data acquisition and management module records data in the background, facilitating later management and analysis. The human-computer interaction module facilitates measurements for operators, improving measurement efficiency and reducing workload. The communication interface transmits measurement data, enabling unified management.

[0057] It is understood that the above embodiments only illustrate preferred embodiments of the present utility model, and their descriptions are relatively specific and detailed, but they should not be construed as limiting the scope of the present utility model patent. It should be noted that for those skilled in the art, the above technical features can be freely combined, and several modifications and improvements can be made without departing from the concept of the present utility model, all of which fall within the protection scope of the present utility model. Therefore, all equivalent transformations and modifications made within the scope of the claims of the present utility model should fall within the coverage of the claims of the present utility model.

Claims

1. A gamma scanning device for radioactive waste bins in nuclear power plants, characterized in that, include: Support base (1), sealing cover (2), turntable (3), control mechanism (4) and fixing assembly (5); The sealing cover (2) is detachably installed on the support base (1) and forms a sealing cavity (6) between it and the support base (1); The turntable (3) is detachably mounted on the support base (1) and rotates in the sealed cavity (6); The fixing component (5) is installed on the turntable (3) to detachably fix the radioactive waste bin (7) on the turntable (3) so that the axis of the radioactive waste bin (7) is parallel to the plane of the turntable (3); The control mechanism (4) includes a measurement module (41) and a drive module (42). The measurement module (41) is mounted on the support base (1) perpendicular to the axis of the radioactive waste bin (7). The measurement module (41) passes through the sealing cover (2) to perform radioactive measurements on the radioactive waste bin (7) in the sealing cavity (6). The drive module (42) is detachably mounted on the support base (1) and drives the turntable (3) to rotate in a direction perpendicular to the axis of the radioactive waste bin (7).

2. The gamma scanning device for radioactive waste bins in nuclear power plants according to claim 1, characterized in that, The support base (1) includes: a support frame (11), an operating platform (12) and a conveying assembly (13). The operating platform (12) is detachably mounted on the support frame (11) and forms the sealing cavity (6) between itself and the sealing cover (2). The conveying assembly (13) is mounted on the operating platform (12), and the turntable (3) is rotatably connected to the conveying assembly (13), driving the turntable (3) to reciprocate between the outside and the sealing cavity (6).

3. The gamma scanning device for radioactive waste bins in nuclear power plants according to claim 2, characterized in that, The conveying assembly (13) includes a guide rail (131), a slide (132), and a limiting member (133). The guide rail (131) is mounted on the operating platform (12). The slide (132) is slidably connected to the guide rail (131). The turntable (3) is rotatably connected to the slide (132). The limiting member (133) is slidably connected to the operating platform (12). After the turntable (3) moves into the sealed cavity (6), it restricts the movement of the slide (132).

4. The gamma scanning device for radioactive waste bins in nuclear power plants according to claim 1, characterized in that, The fixing component (5) includes a clamping block (51) and a locking member (52). The turntable (3) has a sliding groove (53). At least two clamping blocks (51) are slidably connected in the sliding groove (53) on both sides of the radioactive waste bin (7). The locking member (52) is installed on the turntable (3) to restrict the sliding of the clamping block (51).

5. The gamma scanning device for radioactive waste bins in nuclear power plants according to claim 4, characterized in that, The locking element (52) includes a mounting base (521) and a screw (522). The mounting base (521) is fixedly mounted on the turntable (3). The screw (522) is connected to the mounting base (521) by a threaded pair. One end of the screw (522) is rotatably connected to the corresponding clamping block (51) to drive and restrict the movement of the clamping block (51).

6. The gamma scanning device for radioactive waste bins in nuclear power plants according to claim 2, characterized in that, The sealing cover (2) includes an isolation cover (21) and an isolation door (22). The isolation cover (21) is detachably installed on the operating platform (12). The isolation cover (21) is provided with a notch that allows the turntable (3) to reciprocate between the outside and the sealing cavity (6). The isolation door (22) is rotatably connected to the isolation cover (21) to open or close the notch.

7. The gamma scanning device for radioactive waste bins in nuclear power plants according to claim 6, characterized in that, The sealing cover (2) also includes a transparent panel (23) and a handle (24) mounted on the isolation door (22).

8. The gamma scanning device for radioactive waste bins in nuclear power plants according to claim 1, characterized in that, The drive module (42) includes a motor (421) and a friction wheel (422). The motor (421) is detachably mounted on the support base (1). The friction wheel (422) is installed in the sealed cavity (6) and connected to the motor (421). After the turntable (3) moves into the sealed cavity (6), the friction wheel (422) contacts the turntable (3). The friction wheel (422) drives the turntable (3) to rotate in a direction perpendicular to the axis of the radioactive waste container (7) through friction.

9. A gamma measurement device for radioactive waste containers in nuclear power plants, characterized in that, The device includes a nuclear power plant radioactive waste bin gamma scanning device according to any one of claims 1-8, and a radioactive waste bin (7) placed horizontally in the nuclear power plant radioactive waste bin gamma scanning device.

10. The gamma measurement device for radioactive waste bins in nuclear power plants according to claim 9, characterized in that, The gamma measurement equipment for the radioactive waste bins in the nuclear power plant also includes: a human-machine interaction module, a data acquisition and management module, a gamma spectrum analysis module, a passive efficiency calibration module, and a communication interface.

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