CN216848156U

CN216848156U - Radioactivity detection device for nuclear waste resin barrel

Info

Publication number: CN216848156U
Application number: CN202123121914.8U
Authority: CN
Inventors: 王俊苏
Original assignee: Ekron Intelligent Technology Suzhou Co ltd
Current assignee: Ekron Intelligent Technology Suzhou Co ltd
Priority date: 2021-12-13
Filing date: 2021-12-13
Publication date: 2022-06-28
Anticipated expiration: 2031-12-13

Abstract

The utility model relates to a radioactive detection technical field discloses a useless resin drum radioactive detection device of nuclear, including base and the useless resin drum of nuclear, the mounting groove has been seted up to one side of base, the internally mounted of mounting groove has the rotatory roll table of three hundred sixty degrees, the useless resin drum of nuclear is located the top of the rotatory roll table of three hundred sixty degrees, second sample arm is installed at the top of base, one side of second sample arm is provided with the mounting bracket, one side of second sample arm is passed through mounting bracket movable mounting has first sample arm, one side of first sample arm is provided with four support arms, the top fixed mounting of base has surperficial dose rate detector and distant place dose rate detector, just the top fixed mounting of base has host computer and controller, the one end fixed mounting of second sample arm has micro motor. The utility model discloses a set up a series of structures and make this device have the characteristics that detection efficiency is high and the accuracy nature that detects is strong.

Description

Radioactivity detection device for nuclear waste resin barrel

Technical Field

The utility model relates to a radioactivity detection technology field, in particular to nuclear waste resin bucket radioactivity detection device.

Background

Radioactivity detection refers to the safety detection of a machine or site that is capable of generating radioactivity, such as ionizing radiation or electromagnetic radiation. Because of the great radiation hazard and the perception of the radioactive hazard generally by means of special instruments, the radioactive detection is widely applied to production and life.

When the radioactivity of the nuclear waste resin barrel is detected, most of the radioactivity is manually detected by a handheld instrument at each position of the barrel body, so that the detection is not comprehensive enough, the detection efficiency is low, and the manpower is consumed. Therefore, a radioactivity detecting device for the nuclear waste resin barrel is provided.

SUMMERY OF THE UTILITY MODEL

The utility model aims at providing a nuclear waste resin bucket radioactivity detection device has the effect that the accuracy nature of detection efficiency height and detection is strong.

The above technical purpose of the present invention can be achieved by the following technical solutions: the utility model provides a nuclear waste resin bucket radioactivity detection device, includes the useless resin bucket of base and nuclear, the mounting groove has been seted up to one side of base, the internally mounted of mounting groove has the rotatory roll table of three hundred sixty degrees, the useless resin bucket of nuclear is located the top of the rotatory roll table of three hundred sixty degrees, second sample arm is installed at the top of base, one side of second sample arm is provided with the mounting bracket, one side of second sample arm is passed through mounting bracket movable mounting has first sample arm, one side of first sample arm is provided with four support arms, the top fixed mounting of base has surperficial dose rate detector and distant dose rate detector, just the top fixed mounting of base has host computer and controller.

The utility model discloses a further set up to: the one end fixed mounting of second sample arm has micro motor, the second sampling head is installed to micro motor's output shaft, micro motor's power input end pass through the wire with the power output end electric connection of host computer.

Through adopting above-mentioned technical scheme, accessible host computer controls micro motor, and micro motor can drive the activity of second sampling head.

The utility model discloses a further set up to: four the one end of support arm all is provided with the installation piece, four the equal movable mounting of one end of installation piece has first sample head, just one side of first sample head is provided with the spring.

Through adopting above-mentioned technical scheme, through the elasticity of spring, can be convenient for first sample head and the inseparable laminating of nuclear waste resin bucket.

The utility model discloses a further set up to: the inside fixed mounting of base has driving motor, driving motor's output is provided with the turn round, the top of turning round with the bottom fixed connection of first sample arm, driving motor's electric power input pass through the wire with the electric power output electric connection of host computer.

Through adopting above-mentioned technical scheme, accessible host computer control driving motor, driving motor then drives first sample arm and rotates, makes four first sampling heads of its one side closely laminate with nuclear waste resin bucket.

The utility model discloses a further set up to: the surface dosage rate detector is positioned on one side of the nuclear waste resin barrel, and the distance between the far dosage rate detector and the nuclear waste resin barrel is one meter.

By adopting the technical scheme, the dosage rates on the surface of the nuclear waste resin barrel and one meter can be detected.

The utility model discloses a further set up to: the host is electrically connected with the controller through a lead, and the signal output ends of the surface dose rate detector and the far dose rate detector are connected with the signal input end of the host.

By adopting the technical scheme, the controller can control the host, and the host can output and display the dosage rates detected by the surface dosage rate detector and the far dosage rate detector through the controller.

The beneficial effects of the utility model are that: after a nuclear waste resin barrel loaded with waste resin and activated carbon is positioned on a three-hundred-sixty-degree rotary roller way, a first sampling arm is driven by a driving motor to rotate to the position where a first sampling head is tightly attached to the surface of the nuclear waste resin barrel, a micro motor drives a second sampling head to be attached to the surface of the top of the nuclear waste resin barrel, the three-hundred-sixty-degree rotary roller way resets after rotating to a circle, the driving motor drives the first sampling arm to reset, the micro motor drives the second sampling head to reset, four samples on the first sampling head and samples on the second sampling head are taken down and sent to an analysis room for analysis and data recording, a surface dose rate detector is positioned on one side of the nuclear waste resin barrel, the distance between a far dose rate detector and the nuclear waste resin barrel is one meter, and the dose rates on the surface of the nuclear waste resin barrel and one meter can be detected.

Drawings

In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings needed to be used in the description of the embodiments will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings without creative efforts.

Fig. 1 is a perspective view of the present invention.

Fig. 2 is a schematic structural diagram of the first sampling arm of the present invention.

Fig. 3 is an enlarged view of a portion a in fig. 2 according to the present invention.

In the figure, 1, a base; 2. a host; 3. a support arm; 4. a first sampling arm; 5. a mounting frame; 6. a console; 7. a remote dose rate detector; 8. a second sampling arm; 9. a micro-motor; 10. a second sampling head; 11. a nuclear waste resin barrel; 12. a surface dose rate detector; 13. mounting grooves; 14. a three hundred sixty degree rotary roller way; 15. a drive motor; 16. turning the head; 17. mounting a block; 18. a spring; 19. a first sampling head.

Detailed Description

The technical solution of the present invention will be clearly and completely described below with reference to the specific embodiments. It is obvious that the described embodiments are only some of the embodiments of the present invention, and not all of them. Based on the embodiments of the present invention, all other embodiments obtained by a person of ordinary skill in the art without creative efforts belong to the protection scope of the present invention.

Referring to fig. 1-3, the present invention provides a technical solution: the utility model provides a nuclear waste resin bucket radioactivity detection device technical scheme, including base 1 and nuclear waste resin bucket 11, mounting groove 13 has been seted up to one side of base 1, the internally mounted of mounting groove 13 has three hundred sixty degrees rotatory roll table 14, nuclear waste resin bucket 11 is located the top of three hundred sixty degrees rotatory roll table 14, second sample arm 8 is installed at base 1's top, one side of second sample arm 8 is provided with mounting bracket 5, there is first sample arm 4 one side of second sample arm 8 through 5 movable mounting of mounting bracket, one side of first sample arm 4 is provided with four support arms 3, base 1's top fixed mounting has surperficial dose rate detector 12 and distant dose rate detector 7, and base 1's top fixed mounting has host computer 2 and controller 6.

Preferably, a micro motor 9 is fixedly mounted at one end of the second sampling arm 8, a second sampling head 10 is mounted on an output shaft of the micro motor 9, an electric power input end of the micro motor 9 is electrically connected with an electric power output end of the host 2 through a wire, the micro motor 9 can be controlled through the host 2, and the micro motor 9 can drive the second sampling head 10 to move.

Preferably, the installation blocks 17 are arranged at one ends of the four support arms 3, the first sampling heads 19 are movably arranged at one ends of the four installation blocks 17, the springs 18 are arranged on one sides of the first sampling heads 19, and the first sampling heads 19 can be conveniently and tightly attached to the nuclear waste resin barrel 11 through the elasticity of the springs 18.

Preferably, the inside fixed mounting of base 1 has driving motor 15, driving motor 15's output is provided with the turn round 16, the top of turn round 16 and the bottom fixed connection of first sample arm 4, driving motor 15's power input end passes through the wire and the power output end electric connection of host computer 2, accessible host computer 2 control driving motor 15, driving motor 15 then drives first sample arm 4 and rotates, makes four first sampling heads 19 of its one side closely laminate with nuclear waste resin bucket 11.

Preferably, the surface dose rate detector 12 is located at one side of the nuclear waste resin barrel 11, and the distance between the far dose rate detector 7 and the nuclear waste resin barrel 11 is one meter, so that the dose rates on the surface of the nuclear waste resin barrel 11 and one meter can be detected.

Preferably, pass through wire electric connection between host computer 2 and the controller 6, the signal output part of surperficial dose rate detector 12 and distant dose rate detector 7 all is connected with the signal input part of host computer 2, and controller 6 can control host computer 2, and host computer 2 can pass through controller 6 output with the dose rate that surperficial dose rate detector 12 and distant dose rate detector 7 detected and show.

The working principle is as follows: before use, the safety of each structure of the device is checked, after the nuclear waste resin barrel 11 loaded with waste resin and active carbon is positioned on a three hundred sixty-degree rotary roller table 14, the driving motor 15 drives the first sampling arm 4 to rotate until the first sampling head 19 is tightly attached to the surface of the nuclear waste resin barrel 11, the micro motor 9 drives the second sampling head 10 to be attached to the surface of the top of the nuclear waste resin barrel 11, the three-hundred and sixty-degree rotary roller table 14 rotates to a circle and then resets, the driving motor 15 drives the first sampling arm 4 to reset, the micro motor 9 drives the second sampling head 10 to reset, four samples on the first sampling head 19 and samples on the second sampling head 10 are taken down and sent to an analysis room for analysis and data recording, and the surface dosage rate detector 12 is positioned at one side of the nuclear waste resin barrel 11, and the distance between the remote dosage rate detector 7 and the nuclear waste resin barrel 11 is one meter, so that the dosage rates on the surface of the nuclear waste resin barrel 11 and one meter can be detected.

It should be noted that, in this document, relational terms such as first and second, and the like are used solely to distinguish one entity or action from another entity or action without necessarily requiring or implying any actual such relationship or order between such entities or actions. Furthermore, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus, and standard components used in the description herein may be commercially available and may be custom-built from descriptions of both the detailed description and the drawings, with the specific connections for each component being made by conventional means well known in the art, with the machines, components, and apparatuses being made by conventional means well known in the art, and with the circuits being made by conventional means well known in the art, and without further elaboration herein.

Although embodiments of the present invention have been shown and described, it will be appreciated by those skilled in the art that changes, modifications, substitutions and alterations can be made in these embodiments without departing from the principles and spirit of the invention, the scope of which is defined in the appended claims and their equivalents.

Claims

1. The utility model provides a nuclear waste resin bucket radioactivity detection device, includes base (1) and nuclear waste resin bucket (11), its characterized in that: mounting groove (13) have been seted up to one side of base (1), the internally mounted of mounting groove (13) has three hundred sixty degrees rotatory roll table (14), nuclear waste resin bucket (11) are located the top of three hundred sixty degrees rotatory roll table (14), second sample arm (8) are installed at the top of base (1), one side of second sample arm (8) is provided with mounting bracket (5), one side of second sample arm (8) is passed through mounting bracket (5) movable mounting has first sample arm (4), one side of first sample arm (4) is provided with four support arms (3), the top fixed mounting of base (1) has surface detector dose rate (12) and distant dose rate detector (7), just the top fixed mounting of base (1) has host computer (2) and controller (6).

2. The apparatus for detecting radioactivity in a nuclear waste resin cask according to claim 1, wherein: one end fixed mounting of second sample arm (8) has micro motor (9), second sampling head (10) are installed to the output shaft of micro motor (9), the electric power input of micro motor (9) pass through the wire with the electric power output electric connection of host computer (2).

3. The radioactivity detecting device for the nuclear waste resin cask according to claim 1, wherein: four the one end of support arm (3) all is provided with installation piece (17), four the equal movable mounting of one end of installation piece (17) has first sample head (19), just one side of first sample head (19) is provided with spring (18).

4. The apparatus for detecting radioactivity in a nuclear waste resin cask according to claim 1, wherein: the inside fixed mounting of base (1) has driving motor (15), the output of driving motor (15) is provided with turns round (16), the top of turning round (16) with the bottom fixed connection of first sample arm (4), the electric power input of driving motor (15) pass through the wire with the electric power output electric connection of host computer (2).

5. The radioactivity detecting device for the nuclear waste resin cask according to claim 1, wherein: the surface dosage rate detector (12) is located on one side of the nuclear waste resin barrel (11), and the distance between the far dosage rate detector (7) and the nuclear waste resin barrel (11) is one meter.

6. The radioactivity detecting device for the nuclear waste resin cask according to claim 1, wherein: the host (2) is electrically connected with the controller (6) through a lead, and the signal output ends of the surface dose rate detector (12) and the far dose rate detector (7) are connected with the signal input end of the host (2).