Nuclear power plant dry ice decontamination device and nuclear power plant dry ice decontamination system

Abstract

The utility model discloses a nuclear power plant dry ice decontamination device and a nuclear power plant dry ice decontamination system. The dry ice decontamination device comprises a machine shell, dry ice spraying equipment for spraying dry ice into an operation space and an air exhaust mechanism for forming negative pressure in the operation space. An operation window and an exhaust port are formed in the machine shell, and an operation space and an air isolation space are defined in the machine shell; the operation space is communicated with the outside through the operation window, and the exhaust port corresponds to the air isolation space; at least one first extraction opening is formed between the working space and the air isolation space; the air exhaust mechanism is arranged in the air isolation space, the first end of the air exhaust mechanism is communicated with the at least one first air exhaust opening, and the second end of the air exhaust mechanism is communicated with the air exhaust opening. The radioactive contamination diffusion can be prevented.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of nuclear power, in particular to a nuclear power plant dry ice decontamination device and a nuclear power plant dry ice decontamination system. BACKGROUND

[0002] During the operation of a nuclear power plant, some equipment and tools may be contaminated by radioactive substances. At present, there is a method for decontaminating the radioactive substances on the surface of the equipment and tools by using dry ice.

[0003] During the dry ice decontamination process, when the surface of the equipment and tools is cleaned by the dry ice, small radioactive aerosol particles may be generated. The radioactive aerosol particles may be mixed in the gasified carbon dioxide. If the mixed gas is not completely collected, the radioactive aerosol may escape, causing a pollution risk. CONTENT OF THE INVENTION

[0004] The technical problem to be solved by the present application is to provide a nuclear power plant dry ice decontamination device and a nuclear power plant dry ice decontamination system.

[0005] The technical solution adopted by the present application to solve the technical problem is:

[0006] A nuclear power plant dry ice decontamination device is constructed, comprising:

[0007] A housing is formed with an operation window and an exhaust port, and defines a working space and an air isolation space; the operation window connects the working space with the outside, and the exhaust port corresponds to the air isolation space; at least one first air suction port is formed between the working space and the air isolation space;

[0008] A dry ice injection device is arranged to inject dry ice into the working space; and

[0009] An air suction mechanism is arranged to form a negative pressure in the working space, and is arranged in the air isolation space, with a first end connected to the at least one first air suction port and a second end connected to the exhaust port.

[0010] In some embodiments, the housing further defines a waste collection space at the bottom end of the working space, and is connected to the working space through at least one through hole and connected to the air isolation space through at least one second air suction port;

[0011] The first end of the air suction mechanism is further connected to the at least one second air suction port.

[0012] In some embodiments, the nuclear power plant dry ice decontamination device further comprises a work platform, a first partition plate and a second partition plate; the work platform separates the work space from the waste collection space, and the at least one through hole is formed on the work platform; the first partition plate separates the work space from the air isolation space, and the at least one first air outlet is formed on the first partition plate; the second partition plate separates the waste collection space from the air isolation space, and the at least one second air outlet is formed on the second partition plate.

[0013] In some embodiments, the nuclear power plant dry ice decontamination device further comprises a filter plate arranged corresponding to the second air outlet.

[0014] In some embodiments, the casing further comprises a first communication port for connecting the air isolation space with the outside; and the nuclear power plant dry ice decontamination device further comprises a first removable plate for sealing the first communication port.

[0015] In some embodiments, the casing further comprises a second communication port for connecting the waste collection space with the outside; and the nuclear power plant dry ice decontamination device further comprises a second removable plate for sealing the second communication port.

[0016] In some embodiments, the work space is provided with at least one fixing mechanism for suspending and fixing a nuclear contamination equipment.

[0017] In some embodiments, the air extraction mechanism comprises at least one air extraction pipeline and a filter arranged on the air extraction pipeline.

[0018] In some embodiments, the nuclear power plant dry ice decontamination device further comprises a cover plate for sealing the operation window.

[0019] In some embodiments, the cover plate is provided with an equipment placing assembly for detachably connecting the dry ice spraying equipment.

[0020] The nuclear power plant dry ice decontamination system comprises a nuclear air purifier and the nuclear power plant dry ice decontamination device according to any one of the above embodiments, and the nuclear air purifier is connected with the air outlet.

[0021] The implementation of the present application at least has the following beneficial effects:

[0022] The air extraction mechanism can timely extract the gas in the work space, so as to construct a negative pressure environment for the work space, avoid the radioactive aerosol generated in the work space from escaping from the operation window and the like, and prevent the spread of radioactive pollution. BRIEF DESCRIPTION OF DRAWINGS

[0023] The present application will be further described in conjunction with the accompanying drawings and embodiments. In the drawings:

[0024] Figure 1 is a structural schematic diagram of a dry ice decontamination device of a nuclear power plant according to an embodiment of the present application;

[0025] Figure 2 is a structural schematic diagram of a dry ice decontamination device of a nuclear power plant according to an embodiment of the present application; Figure 1 is a structural schematic diagram of a dry ice decontamination device of a nuclear power plant according to an embodiment of the present application;

[0026] Figure 3 is a structural schematic diagram of a dry ice decontamination device of a nuclear power plant according to an embodiment of the present application; Figure 1 is a structural schematic diagram of a dry ice decontamination device of a nuclear power plant according to an embodiment of the present application;

[0027] Figure 4 is a structural schematic diagram of a dry ice decontamination device of a nuclear power plant according to an embodiment of the present application; Figure 1 is a structural schematic diagram of a dry ice decontamination device of a nuclear power plant according to an embodiment of the present application. DETAILED DESCRIPTION

[0028] In order to have a clearer understanding of the technical features, objectives and effects of the present application, the specific embodiments of the present application will be described in detail with reference to the accompanying drawings. In the following description, it should be understood that the directions or positional relationships indicated by "front", "back", "upper", "lower", "left", "right", "vertical", "horizontal", "bottom", "inner", "outer", etc. are based on the directions or positional relationships shown in some of the drawings, the specific directions of construction and operation, and are only for the convenience of describing the technical solutions, and should not be construed as indicating that the devices or elements must have the specific directions. Therefore, it should not be understood as a limitation on the present application.

[0029] It should also be noted that, unless otherwise explicitly specified and limited, the terms "mounting", "connection", "connecting", "fixing", "setting", etc. should be interpreted in a broad sense, for example, can be fixed connection, or detachable connection, or integrated; can be mechanical connection, or electrical connection; can be directly connected, or indirectly connected through an intermediate medium, or the internal connection of two elements or the interaction relationship between two elements. When an element is referred to as "on" or "under" another element, the element can be "directly" or "indirectly" located on the other element, or there can be one or more intervening elements. The terms "first", "second", etc. are only for the convenience of describing the technical solutions, and should not be construed as indicating or implying relative importance or implicitly indicating the number of the indicated technical features. Therefore, the features with "first", "second", etc. can explicitly or implicitly include one or more of the features. For those skilled in the art, the specific meanings of the above terms in the present application can be understood according to the specific circumstances.

[0030] In the following description, for purposes of explanation and not limitation, specific details are set forth such as particular architectures, technologies, techniques, etc. in order to provide a thorough understanding of the embodiments of the present application. However, it will be apparent to those skilled in the art that the present application can be practiced in other embodiments that depart from these specific details. In other instances, detailed descriptions of well-known systems, devices, circuits, and methods are omitted so as not to obscure the description of the present application with unnecessary detail.

[0031] As shown in Figures 1 to 4 The present application provides a dry ice decontamination device for nuclear power plant, which can use dry ice to decontaminate (remove nuclear contamination) the nuclear contaminated equipment.

[0032] The dry ice decontamination device for nuclear power plant can include a casing 1, a dry ice spraying device 6 and an air extraction mechanism 9. The nuclear contaminated equipment can be placed in the casing 1, and the dry ice spraying device 6 can spray dry ice to the nuclear contaminated equipment in the casing 1 to perform decontamination. The air extraction mechanism 9 is arranged in the casing 1 to extract the air in the casing 1.

[0033] The casing 1 is provided with an operation window 104 and an exhaust port 105, and defines an operation space 101 and an air isolation space 103 inside. The operation space 101 is used to place the nuclear contaminated equipment, and the dry ice spraying device 6 sprays dry ice into the operation space 101 to perform dry ice decontamination on the nuclear contaminated equipment in the operation space 101. The operation window 104 can be connected to the outside to take and place the nuclear contaminated equipment through the operation window 104. The air isolation space 103 and the operation space 101 are two relatively independent chambers, but at least one first air extraction port 41 is formed between them. The first air extraction port 41 can connect the air isolation space 103 and the operation space 101. The exhaust port 105 is arranged corresponding to the air isolation space 103.

[0034] The first end of the air extraction mechanism 9 is connected to the first air extraction port 41, and the second end is connected to the exhaust port 105 to form an air extraction path. During the dry ice decontamination operation of the dry ice decontamination device for nuclear power plant, the mixed gas with radioactive aerosol generated in the operation space 101 can be extracted from the operation space 101 under the air extraction of the air extraction mechanism 9, so that a negative pressure is formed in the operation space 101, thereby avoiding the diffusion of radioactive aerosol from the operation space 101. The extracted mixed gas can pass through the air extraction mechanism 9 in the air isolation space 103 and be discharged from the exhaust port 105 of the dry ice decontamination device for nuclear power plant. In specific use, the exhaust port 105 can be connected to a corresponding radioactive material collection device or a nuclear air purifier to collect radioactive aerosol and avoid pollution diffusion.

[0035] It needs to be understood that in the process of dry ice decontamination, the surface of the nuclear contaminated equipment is cleaned by dry ice, which produces tiny radioactive aerosol particles. The application sets the air extraction mechanism 9, which can timely extract the gas in the working space 101, and constructs a negative pressure environment for the working space 101, so as to avoid the radioactive aerosol generated in the working space 101 from escaping from the opening such as the operation window 104, and prevent the spread of radioactive contamination.

[0036] The application sets the working space 101 and the air isolation space 103 in the casing 1, and sets the air extraction mechanism 9 in the air isolation space 103, so that the mechanism components can be integrated in the casing 1, and the integration of the dry ice decontamination device for the nuclear power plant is improved.

[0037] As shown in Figure 1 and Figure 2 , in some embodiments, the casing 1 is generally box-shaped, and is generally polygonal columnar structure in the horizontal direction, including two parallel and spaced polygonal side walls. The two polygonal side walls are connected by a plurality of rectangular side walls, which are sequentially arranged along the circumference of the polygonal side wall, and together form a box structure.

[0038] It needs to be understood that the top side is defined as the upper side in the direction of gravity, and the bottom side is defined as the lower side.

[0039] In the embodiments shown in Figure 1 and Figure 2 , the polygonal side wall of the casing 1 is generally arranged in a right trapezoidal shape, including a top wall, a bottom wall, a front wall, a rear wall and an inclined wall, each of which is rectangular. The top wall and the bottom wall are parallel and spaced apart, and the area of the top wall is smaller than that of the bottom wall. The front wall and the rear wall are parallel and spaced apart, and the area of the front wall is smaller than that of the rear wall. The inclined wall is connected with the top wall and the front wall respectively. The operation window 104 is formed in the inclined wall.

[0040] Further, referring to Figure 3 , the working space 101 and the air isolation space 103 are arranged adjacent to each other in the horizontal direction, and the working space 101 is generally located on the front side of the casing 1, and the air isolation space 103 is located on the rear side of the casing 1.

[0041] In some alternative embodiments, the casing 1 can also be in the shape of a rectangular body, other polygonal column, cylindrical shape, irregular shape, or other shapes. The operation window 104 can also be arranged at the rear wall, or polygonal side wall, or top wall, or other positions. The connection relationship between the operation space 101 and the air isolation space 103 can also be arranged adjacent along the gravity direction, or arranged adjacent along the direction perpendicular to the polygonal side wall.

[0042] In some embodiments, the casing 1 also defines a waste collection space 102. The waste collection space 102 is located at the bottom end of the operation space 101, and is used to collect small metal debris and other waste generated during the operation of the operation space 101. The waste collection space 102 and the operation space 101 can be arranged relatively independently, and are connected by at least one through hole 31, so that small waste can automatically fall into the waste collection space 102 under the action of gravity through the through hole 31.

[0043] It should be understood that the outer surface of the nuclear contamination equipment can be left with small metal and other substances. During the dry ice decontamination operation, the small waste material can fall under the spray of the dry ice spray equipment 6, and the surface can be left with radioactive particles.

[0044] The present application can collect and accommodate small substances falling during operation by providing a waste collection space 102, thereby avoiding leakage of radioactive substances carried by the small substances. By arranging the waste collection space 102 at the bottom end of the operation space 101, the small substances can automatically fall into the waste collection space 102 under the action of gravity, without the need for manual operation, thereby avoiding the spread of nuclear contamination during manual operation.

[0045] Further, the air isolation space 103 can be connected to the waste collection space 102 through at least one second air outlet (not shown in the figure). The first end of the air suction mechanism 9 can also be connected to the second air outlet. The air suction mechanism 9 can construct a negative pressure environment in the operation space 101 and the waste collection space 102 during air suction, while avoiding the escape of radioactive aerosols in the operation space 101 and the waste collection space 102, thereby further avoiding the spread of nuclear contamination.

[0046] In Figure 3 In the embodiment shown, the waste collection space 102 is located at the bottom end of the operation space 101, and the two are arranged adjacent in the gravity direction. The waste collection space 102 and the operation space 101 are located at the front side of the air isolation space 103, the waste collection space 102 and the bottom end of the air isolation space 103 are arranged adjacent in the horizontal direction, and the operation space 101 and the top end of the air isolation space 103 are arranged adjacent in the horizontal direction.

[0047] This arrangement allows the air extraction mechanism 9, located in the air isolation space 103, to simultaneously extract gas from both the working space 101 and the waste collection space 102. It also allows small particles to fall into the waste collection space 102 using the principle of gravity, thus improving the overall rationality of the layout.

[0048] In some other alternative embodiments, the air isolation space 103 may also be located at the bottom of the waste collection space 102 and the work space 101, and the waste collection space 102 is located between a portion of the work space 101 and a portion of the air isolation space 103 in the direction of gravity.

[0049] like Figure 1 and Figure 3 As shown, in some embodiments, the dry ice decontamination device for nuclear power plants includes a working platform 3, a first partition plate 4, and a second partition plate 5, which are respectively disposed inside the casing 1 and are used to cooperate with each other to define three spaces.

[0050] Specifically, the work platform 3 separates the work space 101 from the waste collection space 102, and the through hole 31 is formed on the work platform 3. The first partition plate 4 separates the work space 101 from the air isolation space 103, and the first air extraction port 41 is formed on the first partition plate 4. The second partition plate 5 separates the waste collection space 102 from the air isolation space 103, and the second air extraction port is formed on the second partition plate 5.

[0051] exist Figure 3 In the illustrated embodiment, the first partition plate 4 and the second partition plate 5 are arranged parallel to the direction of gravity and are connected along the direction of gravity, with the first partition plate 4 located at the top of the second partition plate 5. The working platform 3 extends horizontally and is arranged perpendicular to both the first partition plate 4 and the second partition plate 5, with one end connected to the junction of the first partition plate 4 and the second partition plate 5.

[0052] Furthermore, there are multiple through holes 31, evenly distributed on the work platform 3, to facilitate the falling of small materials into the waste collection space 102. There are also multiple first air extraction ports 41, spaced apart on portions of the first partition plate 4, penetrating along the thickness direction. The first end of the air extraction mechanism 9 can be connected to each of the multiple first air extraction ports 41. Similarly, there are multiple second air extraction ports, spaced apart on portions of the second partition plate 5, penetrating along the thickness direction. The first end of the air extraction mechanism 9 can also be connected to each of the multiple second air extraction ports.

[0053] The through holes 31, and / or the first suction port 41, and / or the second suction port can be circular holes, or polygonal holes, long holes, irregular holes, etc., which are not limited herein. The sizes of the through holes 31, and / or the first suction port 41, and / or the second suction port can be the same, or at least partially different, which are not limited herein. The number of the first suction port 41 and / or the second suction port can be one.

[0054] In some other optional embodiments, the first partition plate 4 and the second partition plate 5 can be integrated into one plate, which is vertically connected with the work platform 3 in a T shape, and separates the three spaces together.

[0055] In some other optional embodiments, the relative position relationship between the work platform 3, the first partition plate 4 and the second partition plate 5, and the respective setting angles, can be flexibly adjusted according to the position adjustment among the work space 101, the waste collection space 102 and the air isolation space 103, which are not expanded one by one herein.

[0056] It should be understood that the work platform 3, and / or the first partition plate 4, and / or the second partition plate 5 can be arranged in the casing 1 by welding, bolt sealing connection, integral molding, etc., which are not limited herein.

[0057] In some embodiments, the side of the first partition plate 4 facing the work space 101 can be provided with a lighting lamp (not shown in the figure) to provide lighting during the work process.

[0058] In some embodiments, the dry ice decontamination device for nuclear power plants can further include a filter plate (not shown in the figure), which is arranged at least corresponding to the second suction port.

[0059] By arranging the filter plate, the gas entering the suction mechanism 9 from the waste collection space 102 can be filtered, so as to avoid that small objects in the waste collection space 102 enter the suction mechanism 9 under the influence of air flow.

[0060] The shape and size of the filter plate can be the same as those of the second partition plate 5, which is arranged in the waste collection space 102 and corresponding (adhering) to the second partition plate 5.

[0061] It should be understood that the type of the filter plate selected can be flexibly selected according to the size of the small objects on the nuclear contaminated equipment to be worked, which is not limited herein.

[0062] In some other alternative embodiments, the size of the filter plate may correspond only to the area defined by each of the second air extraction ports. The shape of the filter plate may also conform to the shape of the area defined by the second air extraction ports, and can be flexibly configured into various shapes. The filter plate may also be disposed within the air extraction mechanism 9 and within a pipe connected to the second air extraction ports.

[0063] In some other optional embodiments, a filter plate may also be provided at the position corresponding to the first air extraction port 41. It may be a rectangular plate adapted to the first partition plate 4, or a plate adapted to the area defined by the first air extraction port 41, or it may be provided in the pipe in the air extraction mechanism 9 that is connected to the first air extraction port 41.

[0064] like Figure 1 As shown, in some embodiments, at least one fixing mechanism 2 is also provided in the work space 101. The fixing mechanism 2 can fix the nuclear contaminated equipment relatively suspended in the work space 101 so that the dry ice spraying equipment 6 can spray dry ice onto the nuclear contaminated equipment from all directions.

[0065] It is important to understand that currently, during dry ice decontamination operations, the nuclear contaminated equipment is typically placed directly on the work platform 3. During dry ice spraying, the end face of the nuclear contaminated equipment in contact with the work platform 3 will be difficult to spray dry ice onto, resulting in insufficient coverage of the entire outer surface of the equipment. Furthermore, the dry ice spraying process may involve significant spray pressure, which, when applied to the nuclear contaminated equipment, could cause disorderly movement of the equipment within the work space 101, thus affecting the decontamination effect.

[0066] This application, by setting up a fixing mechanism 2, can stably fix the nuclear-contaminated equipment within the work space 101. During the high-pressure spraying process of the dry ice spraying equipment 6, the nuclear-contaminated equipment can be stably fixed and supported, preventing its movement within the work space 101. At the same time, the fixing mechanism 2 can suspend the nuclear-contaminated equipment within the work space 101, ensuring that the outer surface of the nuclear-contaminated equipment does not contact the work platform 3, thereby ensuring comprehensive decontamination operations and improving the decontamination effect.

[0067] exist Figure 1 In the embodiment shown, the fixing mechanism 2 is a three-jaw chuck, which is installed on the working platform 3 and uses the jaws to suspend and fix the nuclear contaminated equipment.

[0068] In some other alternative embodiments, the fixing mechanism 2 can also be configured as two. For a longitudinally elongated nuclear contamination device, the two fixing mechanisms 2 can support and fix it at both ends to further improve the stability of the fixation.

[0069] In some other alternative embodiments, the fixing mechanism 2 may also be disposed on the inner surface of the housing 1 or on the side of the first partition plate 4 facing the work space 101.

[0070] In some other alternative embodiments, the fixing mechanism 2 may also employ other existing mechanisms such as a robotic arm, a gear / rack clamp, or a powered vise.

[0071] like Figure 4 As shown, in some embodiments, the air extraction mechanism 9 may include a filter and at least one air extraction pipe.

[0072] Specifically, for a dry ice decontamination device in a nuclear power plant that does not have a waste collection space 102, the extraction mechanism 9 may include a first exhaust pipe 91, an output pipe 92, and a filter (not shown in the figure). The first end of the first exhaust pipe 91 may be connected to the first extraction port 41, and the second end may be connected to the first end of the output pipe 92. The second end of the output pipe 92 may be connected to the exhaust port 105. The filter may be installed on the first exhaust pipe 91, on the second exhaust pipe (not shown in the figure), or at the connection between the first exhaust pipe 91 and the second exhaust pipe; no specific limitation is made here.

[0073] During the specific operation, the radioactive material collection equipment or nuclear air purifier can be connected to the exhaust port 105. Through the suction function of the radioactive gas collection equipment, the radioactive aerosol in the working space 101 can be sucked into the radioactive material collection equipment or nuclear air purifier in sequence through the first exhaust port 41, the first exhaust pipe 91, the output pipe 92 and the exhaust port 105.

[0074] In some other alternative embodiments, the air extraction mechanism 9 may also be provided with only one pipe, with its two ends connected to the first air extraction port 41 and the exhaust port 105, respectively.

[0075] For a dry ice decontamination device in a nuclear power plant equipped with a waste collection space 102, the extraction mechanism 9 may further include a second exhaust pipe. The first end of the second exhaust pipe may be connected to a second extraction port, and the second end may be connected to the first end of the output pipe 92.

[0076] In this embodiment, the number of filters can be set to two, respectively installed on the first exhaust pipe 91 and the second exhaust pipe. When the number of filters is set to one, it can also be installed on the output pipe 92.

[0077] It should be understood that the first end of the first exhaust pipe 91 and the first end of the second exhaust pipe can together constitute the first end of the suction mechanism 9. The second end of the output pipe 92 can be regarded as the second end of the suction mechanism 9.

[0078] In Figure 4 the first end of the first exhaust pipe 91 can be connected to the first plurality of suction ports 41 through a flared structure in the illustrated embodiment. The first end of the second exhaust pipe can also be connected to the second plurality of suction ports through a flared structure.

[0079] In some embodiments, the suction mechanism 9 can further include a suction pump 93, which can be disposed on the output pipe 92, or at the connection between the output pipe 92 and the first exhaust pipe 91 and / or the second exhaust pipe, to extract the gas in the working space 101 and / or the waste collection space 102.

[0080] As Figure 1 illustrated, in some embodiments, the nuclear power plant dry ice decontamination device can further include a cover plate 7 disposed on the cabinet 1 and openably covering the operation window 104.

[0081] By providing the cover plate 7, the operation window 104 can be opened when it is necessary to take out or put in the nuclear contaminated equipment. The operation window 104 can be closed during the process of not using the nuclear power plant dry ice decontamination device or performing the dry ice decontamination operation, thereby providing a relatively closed working environment to facilitate the construction of a negative pressure environment and further reduce the escape of radioactive aerosols. The provision of the cover plate 7 can also prevent the splashing of dry ice particles ejected during the dry ice decontamination process, ensuring the safety of the workers.

[0082] In Figure 1 the illustrated embodiment, the cover plate 7 is rotatably connected to the inclined wall through a plurality of hinge structures. When it is necessary to open the operation window 104, it can be flipped upwards to be attached to the inclined wall to expose the operation window 104. When it is necessary to close the operation window 104, it can be flipped downwards to cover the operation window 104.

[0083] Further, the cover plate 7 can be provided with an observation window 71 to facilitate observation of the working conditions in the working space 101 through the observation window 71 during the dry ice decontamination operation.

[0084] It should be understood that the observation window on the cover plate 7 can be made of transparent materials such as glass or plastic, which are not limited herein.

[0085] In some embodiments, the cover plate 7 can be movably disposed on the cabinet 1 through a guide rail structure. Its movement path can include a first position and a second position. When it is in the first position, the cover plate 7 is disposed adjacent to the inclined wall to open the operation window 104. When it is in the second position, the cover plate 7 covers the operation window 104.

[0086] As Figure 1 shown in the drawings, in some embodiments, the cover plate 7 can further be provided with a device placing assembly 8, through which the dry ice spraying device 6 can be fixed in the working space 101 when performing dry ice decontamination operation.

[0087] Specifically, the device placing assembly 8 can include a support rod 81 and at least one hanger 82. The hanger 82 is movably arranged on the support rod 81, so as to detachably pass / hang the dry ice spraying device 6 on the hanger 82.

[0088] The support rod 81 can be arranged on one side end surface of the cover plate 7, and when it is arranged in abutment with the inclined wall and the operation window 104 is opened, the support rod 81 can be located on the side of the cover plate 7 away from the inclined wall. When the cover plate 7 is capped on the operation window 104, the support rod 81 can be located in the working space 101.

[0089] It should be understood that the dry ice spraying device 6 can be an existing dry ice spraying gun or the like.

[0090] In other optional embodiments, the dry ice spraying device 6 can also be passed through the cabinet 1 and one end extends into the working space 101.

[0091] As Figure 2 shown in the drawings, in some embodiments, the cabinet 1 can further be formed with a first communication port (not shown in the drawings), which communicates the air isolation space 103 with the outside. The operator can clean the air isolation space 103 through the first communication port, and can also maintain, disassemble and assemble the device in the air isolation space 103. The dry ice decontamination device for nuclear power plant can further include a first disassembly plate 11, which is openably capped on the first communication port, so as to relatively close the air isolation space 103 when it is not necessary to open the air isolation space 103, and ensure the integrity of the appearance of the cabinet 1.

[0092] In Figure 2 the embodiment shown in the drawings, the first communication port is formed on the rear wall and located at the bottom end of the rear wall. The first disassembly plate 11 is generally in the shape of a rectangular plate, one side thereof is rotatably connected with one of the polygonal side walls of the cabinet 1 through a hinge structure, and the remaining sides thereof are detachably connected with the rear wall, the other polygonal side wall and the bottom wall through connecting structures.

[0093] Referring to Figure 1In some embodiments, a second communication port (not shown in the figure) is formed on the casing 1, which communicates the waste collection space 102 with the outside. The waste in the waste collection space 102 can be collected and cleaned by the operator through the second communication port. The nuclear power plant dry ice decontamination device can further include a second detachable plate 12, which is openably capped on the second communication port to ensure the relative independence of the waste collection space 102 during operation, and to avoid the external escape of radioactive aerosols.

[0094] In Figure 1 In the embodiment shown, the second communication port is formed on the front wall and located at the bottom end of the front wall. The second detachable plate 12 is generally in the shape of a rectangular plate, and the bottom end side thereof is rotatably connected to the bottom wall of the casing 1 through a hinge structure, and the remaining sides thereof are detachably connected to the front wall, the two polygonal side walls, respectively, through connecting structures.

[0095] In other optional embodiments, the first communication port can also be formed on the portion of one of the polygonal side walls, or the bottom wall, or the top wall corresponding to the air isolation space 103. The second communication port 106 can also be formed on the portion of one of the polygonal side walls, or the bottom wall corresponding to the waste collection space 102.

[0096] In other optional embodiments, the first communication port and / or the second communication port can also be provided in other shapes such as circular, polygonal, irregular, etc., and the first detachable plate 11 and / or the second detachable plate 12 can also correspondingly adjust the shape thereof. The shape or size of the first communication port and the first detachable plate 11 can be the same or different. The shape or size of the second communication port and the second detachable plate 12 can be the same or different.

[0097] In other optional embodiments, the connection between each side of the first detachable plate 11 and / or the second detachable plate 12 and the casing 1 can also be detachable.

[0098] It should be understood that the connection between the first detachable plate 11 and / or the second detachable plate 12 and the casing 1 can be bolted connection or locking structure such as lock, without specific limitation here.

[0099] As Figure 1 and Figure 2 In some embodiments, the nuclear power plant dry ice decontamination device can further include a plurality of moving wheels 13 provided on the casing 1 and located at the bottom end of the casing 1, so as to facilitate the movement of the nuclear power plant dry ice decontamination device.

[0100] As Figure 2As shown, in some embodiments, the nuclear power plant dry ice decontamination device can further comprise a main control mechanism, which can comprise a control cabinet (not shown in the figure) and a control panel 10. The control panel 10 and the illuminating lamp are respectively electrically connected with the control cabinet. The control cabinet can control the operation of the nuclear power plant dry ice decontamination device.

[0101] In Figure 2 In the embodiment shown, the control panel 10 is arranged on one of the polygonal side walls and has at least one key to control the operation switch of the nuclear power plant dry ice decontamination device by controlling the key. The control cabinet can be arranged in the air isolation space 103.

[0102] The present application also provides a nuclear power plant dry ice decontamination system, which can comprise a nuclear air purifier and the nuclear power plant dry ice decontamination device of any of the above embodiments. The nuclear air purifier can be connected to the exhaust port 105 of the casing 1, and the radioactive aerosol in the operation space 101 (or the operation space 101 and the waste collection space 102) can enter the nuclear air purifier through the air suction mechanism 9 to be purified, so as to avoid nuclear pollution.

[0103] It should be understood that the nuclear air purifier can be selected from existing nuclear air purification trolleys and the like, which are internally provided with filter structures with higher filtering performance to achieve the filtering and purification of radioactive aerosols.

[0104] It should be understood that the above embodiments only express part of the embodiments of the present application, which are described in detail and in detail, but cannot be construed as limiting the scope of the patent of the present application; it should be pointed out that for ordinary skilled in the art, the above embodiments or technical features can be freely combined without departing from the concept of the present application, and a number of modifications and improvements can be made, which all belong to the protection scope of the present application, i.e. the embodiments described in "in some embodiments" can be freely combined with any of the above and below embodiments; therefore, any equivalent transformation and modification within the scope of the claims of the present application shall belong to the scope of the claims of the present application.

Claims

1. A dry ice decontamination device for nuclear power plants, characterized in that, include: The casing (1) has an operating window (104) and an exhaust port (105), and defines a working space (101) and an air isolation space (103); the operating window (104) connects the working space (101) to the outside, and the exhaust port (105) corresponds to the air isolation space (103); at least one first air extraction port (41) is formed between the working space (101) and the air isolation space (103); A dry ice spraying device (6) for spraying dry ice into the work space (101); and An air extraction mechanism (9) is provided to create a negative pressure in the working space (101). The air extraction mechanism (9) is located in the air isolation space (103). Its first end is connected to the at least one first air extraction port (41), and its second end is connected to the exhaust port (105).

2. The dry ice decontamination device for nuclear power plants according to claim 1, characterized in that, The casing (1) also defines a waste collection space (102), which is located at the bottom of the working space (101) and is connected to the working space (101) through at least one through hole (31) and to the air isolation space (103) through at least one second air extraction port. The first end of the air extraction mechanism (9) is also connected to the at least one second air extraction port.

3. The dry ice decontamination device for nuclear power plants according to claim 2, characterized in that, It also includes a work platform (3), a first partition plate (4) and a second partition plate (5); the work platform (3) separates the work space (101) from the waste collection space (102), and at least one through hole (31) is formed on the work platform (3); the first partition plate (4) separates the work space (101) from the air isolation space (103), and at least one first air extraction port (41) is formed on the first partition plate (4); the second partition plate (5) separates the waste collection space (102) from the air isolation space (103), and at least one second air extraction port is formed on the second partition plate (5).

4. The dry ice decontamination device for nuclear power plants according to claim 2, characterized in that, It also includes a filter plate, which is at least configured to correspond to the second air extraction port.

5. The dry ice decontamination device for nuclear power plants according to claim 2, characterized in that, The housing (1) also forms a first communication port, which connects the air isolation space (103) to the outside; the nuclear power plant dry ice decontamination device also includes a first disassembly plate (11), which can be opened to seal the first communication port. And / or, the housing (1) also forms a second communication port, which connects the waste collection space (102) to the outside; the nuclear power plant dry ice decontamination device also includes a second disassembly plate (12), which can be opened to seal the second communication port.

6. The dry ice decontamination apparatus for nuclear power plants according to any one of claims 1 to 5, characterized in that, The work space (101) is equipped with at least one fixed mechanism (2) for suspending and fixing nuclear contamination equipment.

7. The dry ice decontamination apparatus for nuclear power plants according to any one of claims 1 to 5, characterized in that, The air extraction mechanism (9) includes at least one air extraction pipe and an air extraction pump (93) installed on the air extraction pipe.

8. The dry ice decontamination apparatus for nuclear power plants according to any one of claims 1 to 5, characterized in that, It also includes a cover plate (7) that can be opened to cover the operating window (104).

9. The dry ice decontamination device for nuclear power plants according to claim 8, characterized in that, The cover plate (7) is provided with a device placement assembly (8) that is detachably connected to the dry ice spraying device (6).

10. A dry ice decontamination system for nuclear power plants, characterized in that, It includes a nuclear air purifier and a nuclear power plant dry ice decontamination device as described in any one of claims 1 to 9, wherein the nuclear air purifier is connected to the exhaust port (105).

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