CN113838593B - Nuclear waste's unloader and processing system - Google Patents

Nuclear waste's unloader and processing system Download PDF

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Publication number
CN113838593B
CN113838593B CN202111116429.3A CN202111116429A CN113838593B CN 113838593 B CN113838593 B CN 113838593B CN 202111116429 A CN202111116429 A CN 202111116429A CN 113838593 B CN113838593 B CN 113838593B
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China
Prior art keywords
plate
groove
nuclear waste
clamping
pressing plate
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CN202111116429.3A
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CN113838593A (en
Inventor
夏国正
宋红攀
王天浩
李铮
张果
臧少锋
吴华
胡锡文
杨宏悦
李玮
王倜嘉
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China Nuclear Power Engineering Co Ltd
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China Nuclear Power Engineering Co Ltd
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Priority to CN202111116429.3A priority Critical patent/CN113838593B/en
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/34Disposal of solid waste
    • G21F9/36Disposal of solid waste by packaging; by baling
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B28WORKING CEMENT, CLAY, OR STONE
    • B28BSHAPING CLAY OR OTHER CERAMIC COMPOSITIONS; SHAPING SLAG; SHAPING MIXTURES CONTAINING CEMENTITIOUS MATERIAL, e.g. PLASTER
    • B28B13/00Feeding the unshaped material to moulds or apparatus for producing shaped articles; Discharging shaped articles from such moulds or apparatus
    • B28B13/02Feeding the unshaped material to moulds or apparatus for producing shaped articles

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  • Engineering & Computer Science (AREA)
  • Environmental & Geological Engineering (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Manufacturing & Machinery (AREA)
  • Chemical & Material Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Processing Of Solid Wastes (AREA)

Abstract

The invention discloses a nuclear waste discharging device and a nuclear waste treatment system comprising the same. The blanking device comprises a stirrer and a blanking cover, wherein the blanking cover comprises a protection plate, a pressing plate and a clamping plate unit, the pressing plate is arranged below the stirrer, a curing barrel is used for loading nuclear waste, a first opening is formed in the pressing plate, the first opening is located right below a discharge opening of the stirrer, the protection plate is arranged above the pressing plate and used for fixing the pressing plate, a second opening corresponding to the first opening is formed in the protection plate, the clamping plate unit is fixedly arranged on the periphery of the protection plate and comprises a clamping plate, a clamping seat and a rotating shaft assembly, the clamping plate is movably arranged in a storage groove of the clamping seat and used for supporting the pressing plate when the clamping plate is rotated out of the storage groove, and the rotating shaft assembly is used for controlling the clamping plate to rotate out or retract the storage groove. The pressing plate is lapped on the clamping plate unit, and can be flexibly and rapidly replaced along with the rotation of the clamping plate out of and the retraction of the storage groove.

Description

Nuclear waste's unloader and processing system
Technical Field
The invention belongs to the technical field of nuclear industry, and particularly relates to a nuclear waste discharging device and a nuclear waste treatment system comprising the same.
Background
In the outside-barrel cement curing production line, the middle-low radioactive waste liquid and cement are required to be stirred by a stirring mixer outside the barrel, and the cement paste which is uniformly mixed is filled into a curing barrel for curing treatment. In order to ensure that the slurry discharged from the mixer is accurately introduced into the solidification barrel and to reduce external environmental pollution due to the sputtering of the slurry, a blanking cover is generally provided under the outlet of the mixer in the prior art.
In the prior art, the blanking cover adopts an integral structure, personnel are required to operate to detach the blanking cover integrally during replacement, the detachment process is difficult, and the irradiation dose of personnel can be increased; the disassembled blanking cover needs to be treated as solid waste, and the waste amount is large. The existing blanking cover is seriously polluted, is difficult to treat, has shorter maintenance and replacement period, takes longer time for each replacement, influences the operation of equipment and seriously increases the irradiation dose of personnel.
Disclosure of Invention
The present invention has been made to solve the above-mentioned problems occurring in the prior art, and an object of the present invention is to provide a nuclear waste discharging device and a nuclear waste disposal system including the same. The blanking cover adopted by the blanking device of the nuclear waste is of split design, and is convenient to detach and replace.
In order to solve the problems, the invention adopts the following technical scheme:
the utility model provides a unloader of nuclear waste, includes agitator, unloading cover, the agitator is used for stirring the nuclear waste, the unloading cover includes guard plate, clamp plate, cardboard unit, the clamp plate sets up the below of agitator for with the sealed laminating of solidification bucket of its below, solidification bucket is used for loading the nuclear waste, has seted up first opening on the clamp plate, first opening is in under the bin outlet of agitator, the guard plate sets up in the clamp plate top, and be in under the agitator, be used for fixing the clamp plate, seted up the second opening that corresponds with first opening on the guard plate, the cardboard unit includes cardboard, cassette and pivot subassembly, cassette fixed mounting is in the periphery of guard plate, the cardboard activity is located in the storage tank of cassette, be used for supporting the clamp plate when rolling out the storage tank, the pivot subassembly is used for controlling the cardboard to roll out or retrieve the storage tank.
Preferably, the pivot subassembly includes first pivot, second pivot, adapter sleeve, first draw-in groove and second draw-in groove have been seted up at the top of cassette, first pivot with second pivot parallel arrangement is at the top surface of cassette, and distance between first draw-in groove and the second pivot is equal with distance between second draw-in groove and the second pivot, when the storage tank was taken out in the groove in the one end of cardboard, first pivot activity card was located in the first draw-in groove, the second pivot passed the cassette and arrived the storage tank and with be in the other end fixed connection of the cardboard of storage tank, the both ends of adapter sleeve are overlapped respectively in first pivot and second pivot, works as first pivot is pulled out from first draw-in groove and is removed to in the second draw-in groove, and the adapter sleeve drives the axis rotation of second pivot around the second pivot, and then makes the cardboard roll out the one end of storage tank and withdraws the storage tank.
Preferably, the notch of the storage groove is arranged on the side face of the clamping seat, and the rotating radian of the connecting sleeve from the first clamping groove to the second clamping groove is 90 degrees.
Preferably, the clamping plate unit further comprises a pressing block, wherein the pressing block is fixedly installed on the clamping seat and located at the top end of the second rotating shaft, and is used for preventing the connecting sleeve from slipping from the second rotating shaft.
Preferably, the number of the clamping plate units is multiple, and the clamping plate units are uniformly arranged outside the outer circumference of the protection plate.
Preferably, the blanking cover further comprises a sealing gasket, and the sealing gasket is arranged between the protection plate and the pressing plate.
Preferably, the blanking cover further comprises a fixing plate and a connecting plate, the fixing plate is fixed on the stirrer, the protection plate is installed on the fixing plate, one end of the connecting plate is connected with the fixing plate, and the other end of the connecting plate is connected with the protection plate.
Preferably, the pressing plate adopts a foldable structure.
The invention also provides a treatment system of the nuclear waste, which comprises a conveying mechanism, a jacking mechanism, a control mechanism and the unloading device of the nuclear waste, wherein the conveying mechanism comprises a roller way assembly and a curing barrel, the roller way assembly is used for conveying the curing barrel to the jacking mechanism, the jacking mechanism comprises a driving motor and a lifting table, the lifting table is arranged under an unloading cover of the unloading device, the driving motor is used for driving the lifting table to lift, so that the curing barrel is jacked, the opening end of the curing barrel is attached to the unloading cover, the control mechanism comprises a controller and a torque measuring instrument, the torque measuring instrument is arranged on an output shaft of the driving motor and is electrically connected with the controller, the torque measuring instrument is used for measuring the torque value of the output shaft of the driving motor in real time and transmitting the measured torque value to the controller, and the controller is electrically connected with the driving motor and is used for comparing the torque value received in real time with a torque threshold stored in the driving motor and controlling the driving motor to stop working when the received torque value is larger than the torque threshold.
Preferably, the nuclear waste disposal system further includes a robot for pulling, rotating the first rotation shaft, and folding the pressing plate and putting it into the curing tub.
According to the arrangement of the blanking device, nuclear waste is sputtered on the pressing plate in a concentrated mode, the pressing plate is lapped on the rotatable clamping plate of the clamping plate unit, and the clamping plate can be flexibly and rapidly replaced along with the retraction of the clamping plate into the containing groove, so that the whole blanking cover does not need to be replaced, the replacement process is easy to process, the maintenance and replacement period of the blanking cover is shortened, smooth running of equipment is ensured, and the irradiation dose of personnel can be reduced.
Drawings
Fig. 1 is a schematic configuration diagram of a treatment system for nuclear waste in embodiment 2 of the present invention;
FIG. 2 is a schematic structural view of a blanking cover in embodiment 1 of the present invention;
fig. 3 is a schematic structural diagram of a card unit in embodiment 1 of the present invention;
in the figure: the device comprises a stirrer, a blanking cover, a curing barrel, a roller way assembly, a 5-jacking mechanism, a 6-fixing plate, a 7-protection plate, a 8-sealing gasket, a 9-pressing plate, a 10-clamping plate unit, an 11-clamping seat, a 12-first rotating shaft, a 13-connecting sleeve, a 14-second rotating shaft, a 15-pressing block, a 16-clamping plate, a 17-connecting plate, a 18-first clamping groove and a 19-second clamping groove.
Detailed Description
The following description of the embodiments of the present invention will be made more apparent, and the embodiments described in detail, but not necessarily all, in connection with the accompanying drawings. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to fall within the scope of the invention.
In the description of the present invention, it should be noted that the orientation or positional relationship indicated by "upper" or the like is based on the orientation or positional relationship shown in the drawings, and is merely for convenience and simplicity of description, and is not meant to indicate or imply that the apparatus or element to be referred to must be provided with a specific orientation, be configured and operated in a specific orientation, and thus should not be construed as limiting the present invention.
In the description of the present invention, the terms "first," "second," and "second" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present invention, it should be noted that, unless explicitly specified and limited otherwise, the terms "connected," "configured," "mounted," "secured," and the like are to be construed broadly and may be either fixedly connected or detachably connected, or integrally connected, for example; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present invention will be understood by those skilled in the art in specific cases.
The invention provides a blanking device for nuclear waste, which comprises a stirrer and a blanking cover, wherein the stirrer is used for stirring the nuclear waste, the blanking cover comprises a protection plate, a pressing plate and a clamping plate unit, the pressing plate is arranged below the stirrer and is used for being in sealing fit with a solidifying barrel below the stirrer, the solidifying barrel is used for loading the nuclear waste, a first opening is formed in the pressing plate, the first opening is positioned right below a discharge opening of the stirrer, the protection plate is arranged above the pressing plate and is positioned below the stirrer and is used for fixing the pressing plate, a second opening corresponding to the first opening is formed in the protection plate, the clamping plate unit comprises a clamping plate, a clamping seat and a rotating shaft assembly, the clamping seat is fixedly arranged on the periphery of the protection plate, the clamping plate is movably arranged in a containing groove of the clamping seat and is used for supporting the pressing plate when the clamping plate is rotated out of the containing groove, and the rotating shaft assembly is used for controlling the clamping plate to rotate out or retract the containing groove.
The invention also provides a treatment system of the nuclear waste, which comprises a conveying mechanism, a jacking mechanism, a control mechanism and the unloading device of the nuclear waste, wherein the conveying mechanism comprises a roller way assembly and a curing barrel, the roller way assembly is used for conveying the curing barrel to the jacking mechanism, the jacking mechanism comprises a driving motor and a lifting table, the lifting table is arranged under an unloading cover of the unloading device, the driving motor is used for driving the lifting table to lift, so that the curing barrel is jacked, the opening end of the curing barrel is attached to the unloading cover, the control mechanism comprises a controller and a torque measuring instrument, the torque measuring instrument is arranged on an output shaft of the driving motor and is electrically connected with the controller, the torque measuring instrument is used for measuring the torque value of the output shaft of the driving motor in real time and transmitting the measured torque value to the controller, and the controller is electrically connected with the driving motor and is used for comparing the torque value received in real time with a torque threshold stored in the driving motor and controlling the driving motor to stop working when the received torque value is larger than the torque threshold.
Example 1
As shown in fig. 1, the embodiment discloses a blanking device for nuclear waste, including a stirrer 1 and a blanking cover 2, the stirrer 1 is used for stirring the nuclear waste, the stirrer 1 comprises a barrel and a discharge port, the nuclear waste stirred in the barrel is discharged from the discharge port, the blanking cover 2 comprises a protection plate 7, a pressing plate 9 and a clamping plate unit 10, the pressing plate 9 is arranged below the discharge port of the stirrer 1 and is used for being in sealing fit with a curing barrel 3 below the stirring device, the curing barrel 3 is used for loading the nuclear waste, a first opening is formed in the pressing plate 9, the first opening is positioned right below the discharge port of the stirrer 1, the protection plate 7 is arranged above the pressing plate 9 and below the discharge port of the stirrer 1 and is used for fixing the pressing plate 9, a second opening corresponding to the first opening is formed in the protection plate 7, and the nuclear waste discharged from the discharge port passes through the first opening and the second opening and then reaches the curing barrel 3. The clamping plate unit 10 comprises a clamping plate 16, a clamping seat 11 and a rotating shaft assembly, wherein the clamping seat is fixedly arranged on the periphery of the protective plate, the clamping plate 16 is movably arranged in a storage groove, the storage groove is formed in the lower portion of the clamping seat, the clamping plate is used for supporting the pressing plate 9 when the clamping plate rotates out of the storage groove, and the rotating shaft assembly is used for controlling the clamping plate 16 to rotate out of or retract into the storage groove.
In the present embodiment, the nuclear waste is discharged from the discharge port of the agitator 1, passes through the first opening and the second opening, and finally falls into the solidification barrel 3. Thus, the contamination generated by the sputtering of the nuclear waste during the falling process is substantially concentrated on the pressing plate 9, and the pressing plate 9 is overlapped on the clamping plate 16, and when the clamping plate 16 is retracted into the receiving groove, the pressing plate 9 automatically falls onto the curing barrel 3 below, thereby rapidly completing the replacement of the pressing plate 9.
As shown in fig. 2 and 3, the rotating shaft assembly includes a first rotating shaft 12, a second rotating shaft 14, and a connecting sleeve 13, a first clamping groove 18 and a second clamping groove 19 are provided at the top of the clamping seat 11, the first rotating shaft 12 and the second rotating shaft 14 are parallel to each other and are disposed on the top surface of the clamping seat, the distance between the first clamping groove 18 and the second rotating shaft 14 is equal to the distance between the second clamping groove 19 and the second rotating shaft 14, when one end of the clamping plate 16 is in a rotating-out state, the first rotating shaft 12 is clamped in the first clamping groove 18, the second rotating shaft 14 passes through the clamping seat 11 and is fixedly connected with the other end of the clamping plate 16 in the containing groove, two ends of the connecting sleeve 13 are respectively sleeved on the first rotating shaft 12 and the second rotating shaft 14, when the first rotating shaft 12 is pulled out from the first clamping groove 18 and moves into the second clamping groove 19, the connecting sleeve 13 drives the second rotating shaft 14 to rotate around the axis of the second rotating shaft, and one end of the clamping plate 16 is retracted into the containing groove.
Optionally, the notch of the accommodating groove is formed on the side surface of the clamping seat 11, and the rotating radian of the connecting sleeve 13 from the first clamping groove 18 to the second clamping groove 19 is 90 degrees. Specifically, when the first shaft 12 is moved to the second clamping groove 19, the rotation direction is clockwise, and the first shaft 12 is clamped in the second clamping groove 19 after being rotated to the second clamping groove 19, so that one end of the clamping plate 16 is driven to retract into the storage groove. Similarly, when one end of the clamping plate 16 is rotated out of the accommodating groove, the first rotating shaft 12 is lifted from the second clamping groove 19, then rotated by 90 degrees anticlockwise, and the first rotating shaft 12 is clamped in the first clamping groove 18.
Optionally, the clamping plate unit 10 further includes a pressing block 15, where the pressing block 15 is fixedly installed on the top surface of the clamping seat 11 and located at the top end of the second rotating shaft 14, and is used to prevent the connecting sleeve 13 from slipping off the second rotating shaft 14.
Alternatively, the number of the card units 10 is plural, and the plurality of card units 10 are uniformly arranged outside the outer circumference of the shielding plate 7. In this embodiment, the number of the card board units 10 is three, the three card board units are uniformly arranged along the outer circumferential edge of the protection plate 7 at intervals, and the edges of the pressing plate 9 are lapped on the card boards 16 of the three card board units 10, so that the pressing plate 9 can be stably placed.
In this embodiment, the blanking cover 2 further includes a sealing pad 8, the sealing pad 8 is arranged between the protection plate 7 and the pressing plate 9, the sealing pad 8 can adapt to the height deviation of different curing barrels 3, and when the different curing barrels 3 are in contact extrusion with the lower part of the blanking cover 2, a certain compressible allowance can be reserved by arranging the sealing pad.
In this embodiment, blanking cover 2 still includes fixed plate 6 and connecting plate 17, agitator 1 includes churn and the drive assembly who is located its below, churn and drive assembly pass through the shielding wall and keep apart, this shielding wall includes vertical section and horizontal segment, the top of vertical section and the one end fixed connection of horizontal segment, the through-hole has been seted up at the horizontal segment, drive unit sets up in the below of horizontal segment, and be connected with the bottom of churn through this through-hole, the bin outlet of agitator 1 stretches out from the top of the vertical section of shielding wall, fixed plate 6 is fixed on the vertical section upper portion of shielding wall, and set up along vertical direction, guard plate 7 is installed on fixed plate 6, set up along horizontal direction, the one end of connecting plate 17 is connected with the upper end of fixed plate 6, the other end is connected with guard plate 7, thereby constitute the structure of tripod, be favorable to improving the structural stability and the shock resistance of blanking cover 2.
Specifically, the pressing plate 9 adopts a foldable structure, and since the contamination generated by the nuclear waste during the discharging process is substantially concentrated on the pressing plate 9, the pressing plate 9 needs to be frequently detached and replaced to generate a large amount of fixed waste, and the volume of the amount of solid waste can be effectively reduced by adopting the foldable structure, thereby improving the waste treatment efficiency of the pressing plate 9.
In this embodiment, all the contamination in the unloading in-process is concentrated on clamp plate 9, and clamp plate 9 overlap joint is on the cardboard 16 of cardboard unit 10, can be through the flexible installation of turning out and retrieving of cardboard 16 and dismantle to need not to dismantle whole unloading cover 2, dismantle convenient and swift, because clamp plate 9 adopts collapsible structure, the solid waste volume of production is few, easy processing.
Example 2
The embodiment discloses a processing system of nuclear waste, including transport mechanism, climbing mechanism 5, control mechanism, and the unloader of nuclear waste in embodiment 1, transport mechanism includes roller table subassembly 4 and solidification bucket 3, roller table subassembly 4 is used for transporting solidification bucket 3 to climbing mechanism 5, climbing mechanism 5 includes driving motor and elevating platform, the elevating platform is located under unloader's unloading cover 2, driving motor is used for driving elevating platform to the solidification bucket 3 is risen, so that the open end and the unloading cover 2 laminating of solidification bucket 3, control mechanism includes controller and torque measuring apparatu, torque measuring apparatu installs on driving motor's output shaft, and be connected with the controller electricity, be used for real-time measurement driving motor's output shaft's torque value, send to the controller, the controller is connected with driving motor electricity, be used for comparing the torque value that receives in real time with its internal storage's torque threshold value, and when the torque value that receives is greater than torque threshold value, control driving motor stops work.
In this embodiment, the treatment system for nuclear waste further includes a manipulator for pulling up and rotating the first rotating shaft 12 to detach or mount the pressing plate, specifically, when the manipulator pulls up the first rotating shaft 12 from the first clamping groove 18 and rotates it to the second clamping groove 19, the clamping plate 16 is retracted into the receiving groove, the pressing plate 9 loses the support of the clamping plate 16 and falls onto the curing barrel 3, at this time, the manipulator clamps and folds the fallen pressing plate 9 and then places it into the curing barrel 3, thereby effectively reducing the volume of waste of the pressing plate 9; the new clamp plate 9 is placed on the solidification bucket 3, and after the jacking mechanism 5 jacks the clamp plate 9 to be attached to the sealing gasket 10, when the mechanical arm lifts the first rotating shaft 12 from the second clamping groove 19 to rotate the first rotating shaft to the first clamping groove 18, the clamping plate 16 rotates out of the storage groove, and the replaced clamp plate 9 is pressed.
The working procedure of the treatment system of nuclear waste in this embodiment is as follows:
the roller way assembly 4 conveys the curing barrel 3 to a lifting table of the lifting mechanism 5, and the lifting table lifts the curing barrel 3 under the drive of a driving motor so that the opening end of the curing barrel 3 is attached to the blanking cover 2;
when the torque value transmitted by the torque measuring instrument is larger than the torque threshold value stored in the controller, the controller controls the driving motor to stop working, and at the moment, the opening end of the curing barrel 3 is completely attached to the blanking cover 2;
starting the stirrer 1, discharging the nuclear waste in the stirrer through a discharge hole, and enabling the nuclear waste to pass through the blanking cover 2 and then reach the curing barrel 3;
the first rotating shaft 12 is lifted out of the first clamping groove 18 through the operation of a mechanical arm, then the first rotating shaft 12 is rotated 90 degrees clockwise to reach the position above the second clamping groove 19, so that the first rotating shaft 12 is inserted into the second clamping groove 19, at the moment, one end of the clamping plate 16, which is rotated out of the storage groove, is retracted into the storage groove, the pressing plate 9 automatically falls onto the curing barrel 3, and the mechanical arm is operated to fold the pressing plate 9 and put the pressing plate 9 into the curing barrel 3;
a new pressing plate 9 is taken to be placed on the curing barrel 3, the first rotating shaft 12 is lifted out of the second clamping groove 19 through the operation of a mechanical arm, then the first rotating shaft 12 is rotated anticlockwise by 90 degrees to reach the position above the first clamping groove 18, so that the first rotating shaft 12 is inserted into the first clamping groove 18, at the moment, one end of the clamping plate 16 is rotated out of the accommodating groove, and the new pressing plate 9 is placed on the clamping plate 16.
In this embodiment, through measuring driving motor's moment of torsion value in real time to combine the stroke judgement, can guarantee effectively that solidification bucket 3 and blanking cover 2 close contact, do not leave the clearance, thereby prevent that radioactive waste from spilling in the unloading process, the sealed pad 8 of locating between guard plate 7 and clamp plate 9 can adapt to the high deviation of different buckets when jacking, in order to ensure solidification bucket 3 and blanking cover 2 sealed laminating. Because the clamping plate unit is adopted in the discharging device, the pressing plate can be detached by operating the manipulator outside the hot chamber by workers, and the workers do not need to enter the hot chamber for operation, so that the workers can be prevented from being irradiated.
It is to be understood that the above embodiments are merely illustrative of the application of the principles of the present invention, but not in limitation thereof. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the invention, and are also considered to be within the scope of the invention.

Claims (9)

1. A nuclear waste blanking device is characterized by comprising a stirrer (1) and a blanking cover (2),
the stirrer (1) is used for stirring nuclear waste,
the blanking cover (2) comprises a protection plate (7), a pressing plate (9) and a clamping plate unit (10),
the pressing plate (9) is arranged below the stirrer (1) and is used for being in sealing fit with the curing barrel (3) below the stirrer, the curing barrel (3) is used for loading nuclear waste, the pressing plate (9) is provided with a first opening, the first opening is positioned right below a discharge hole of the stirrer (1),
the protection plate (7) is arranged above the pressing plate (9) and below the stirrer (1) and is used for fixing the pressing plate (9), the protection plate (7) is provided with a second opening corresponding to the first opening,
the clamping plate unit (10) comprises a clamping plate (16), a clamping seat (11) and a rotating shaft assembly,
the clamping seat (11) is fixedly arranged at the periphery of the protection plate (7), the clamping plate (16) is movably arranged in a containing groove of the clamping seat (11) and used for supporting the pressing plate (9) when the clamping plate (16) is rotated out of the containing groove, the rotating shaft component is used for controlling the clamping plate (16) to be rotated out of or retracted into the containing groove,
the rotating shaft assembly comprises a first rotating shaft (12), a second rotating shaft (14) and a connecting sleeve (13),
first draw-in groove (18) and second draw-in groove (19) have been seted up at the top of cassette (11), first pivot (12) with second pivot (14) parallel arrangement is on the top surface of cassette, and distance between first draw-in groove (18) and second pivot (14) and distance between second draw-in groove (19) and second pivot (14) are equal, the one end of cardboard (16) is rotated out from accomodating the groove and is accomodate the groove, first pivot (12) activity card is located in first draw-in groove (18), second pivot (14) pass cassette (11) reach accomodate the groove and with be in the other end fixed connection of cardboard (16) in accomodating the groove, on first pivot (12) and second pivot (14) are located respectively to the both ends of adapter sleeve (13), when first pivot (12) are pulled out from first draw-in groove (18) and are removed to second draw-in groove (19), adapter sleeve (13) drive second (14) and are rotated around the axis of second pivot (16) and are taken in groove, make in the cardboard (16) of accomodating the groove.
2. The blanking device of nuclear waste as claimed in claim 1, wherein the notch of the receiving groove is opened at the side of the clamping seat (11), and the rotating radian of the connecting sleeve (13) from the first clamping groove (18) to the second clamping groove (19) is 90 degrees.
3. The nuclear waste blanking apparatus of claim 1, wherein the card plate unit (10) further includes a pressing block (15),
the pressing block (15) is fixedly arranged on the clamping seat (11) and is positioned at the top end of the second rotating shaft (14) and used for preventing the connecting sleeve (13) from slipping off the second rotating shaft (14).
4. A nuclear waste blanking apparatus according to claim 3, characterized in that the number of the card units (10) is plural, and the plurality of card units (10) are uniformly arranged outside the outer circumference of the shielding plate (7).
5. The blanking device of nuclear waste as claimed in any one of claims 1-4, characterized in that the blanking cover (2) further comprises a sealing gasket (8),
the sealing gasket (8) is arranged between the protection plate (7) and the pressing plate (9).
6. The device for blanking nuclear waste according to claim 5, characterized in that the blanking cover (2) further comprises a fixing plate (6) and a connecting plate (17),
the fixed plate (6) is fixed on the stirrer (1), the protection plate (7) is installed on the fixed plate (6), one end of the connecting plate (17) is connected with the fixed plate (6), and the other end is connected with the protection plate (7).
7. The nuclear waste blanking apparatus of claim 6, wherein the pressing plate (9) adopts a foldable structure.
8. A system for treating nuclear waste, comprising a transporting mechanism, a lifting mechanism (5), a control mechanism, and a device for discharging nuclear waste according to any one of claims 1 to 7,
the conveying mechanism comprises a roller way assembly (4) and a curing barrel (3), the roller way assembly (4) is used for conveying the curing barrel (3) to the jacking mechanism (5),
the lifting mechanism (5) comprises a driving motor and a lifting table, the lifting table is arranged under the blanking cover (2) of the blanking device, the driving motor is used for driving the lifting table to lift, so as to lift the curing barrel (3) to enable the opening end of the curing barrel (3) to be attached to the blanking cover (2),
the control mechanism comprises a controller and a torque measuring instrument,
the torque measuring instrument is arranged on the output shaft of the driving motor and is electrically connected with the controller for measuring the torque value of the output shaft of the driving motor in real time and transmitting the measured torque value to the controller,
the controller is electrically connected with the driving motor and is used for comparing the torque value received in real time with the torque threshold value stored in the controller, and controlling the driving motor to stop working when the received torque value is larger than the torque threshold value.
9. The system for processing nuclear waste according to claim 8, further comprising a robot for pulling, rotating the first rotation shaft (12), and folding the platen (9) and placing it into the curing vat (3).
CN202111116429.3A 2021-09-23 2021-09-23 Nuclear waste's unloader and processing system Active CN113838593B (en)

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CN113838593B true CN113838593B (en) 2023-12-19

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Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4234447A (en) * 1978-07-17 1980-11-18 The Dow Chemical Company Mixing method and container therefor
TW432147B (en) * 1997-09-17 2001-05-01 Southco Apparatus and method for mounting latching devices
CN206590622U (en) * 2017-03-30 2017-10-27 中国核动力研究设计院 Cement sealing adjusting means
CN109801729A (en) * 2019-01-29 2019-05-24 中广核工程有限公司 Increase the method and maintenance sealing device of grout cap in nuclear power plant's waste canister
CN210820195U (en) * 2019-05-17 2020-06-23 中核四川环保工程有限责任公司 Take radioactive liquid waste cement solidification bucket of oar formula
CN211858177U (en) * 2020-03-03 2020-11-03 河北骞海鼓风机有限公司 Waste liquid cement curing line splashproof cover convenient to disassemble
CN112151201A (en) * 2020-09-25 2020-12-29 中国原子能科学研究院 Filling device
CN112242208A (en) * 2020-09-30 2021-01-19 郑州贝贝生物科技有限公司 Cement solidification device for radioactive waste liquid treatment and use method thereof

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4234447A (en) * 1978-07-17 1980-11-18 The Dow Chemical Company Mixing method and container therefor
TW432147B (en) * 1997-09-17 2001-05-01 Southco Apparatus and method for mounting latching devices
CN206590622U (en) * 2017-03-30 2017-10-27 中国核动力研究设计院 Cement sealing adjusting means
CN109801729A (en) * 2019-01-29 2019-05-24 中广核工程有限公司 Increase the method and maintenance sealing device of grout cap in nuclear power plant's waste canister
CN210820195U (en) * 2019-05-17 2020-06-23 中核四川环保工程有限责任公司 Take radioactive liquid waste cement solidification bucket of oar formula
CN211858177U (en) * 2020-03-03 2020-11-03 河北骞海鼓风机有限公司 Waste liquid cement curing line splashproof cover convenient to disassemble
CN112151201A (en) * 2020-09-25 2020-12-29 中国原子能科学研究院 Filling device
CN112242208A (en) * 2020-09-30 2021-01-19 郑州贝贝生物科技有限公司 Cement solidification device for radioactive waste liquid treatment and use method thereof

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