Vertical transfer system for moving radioactive substances

Abstract

The invention relates to a vertical transfer system for moving radioactive materials, which is an automatic system capable of realizing safe and accurate butt joint and vertical transfer of the radioactive materials between two stations in the field of nuclear industry, and can be widely applied to high-radiation environments such as nuclear fuel circulation, radioactive waste treatment and isotope production.

Description

Technical Field

[0001] The present invention relates to the field of radioactive material transportation technology, specifically to an automated system for achieving safe and precise docking and vertical transportation of radioactive materials between two workstations in the nuclear industry. The system can be widely used in high-radiation environments such as nuclear fuel cycles, radioactive waste treatment, and isotope production. Background Art

[0002] With the rapid development of my country's nuclear industry in recent years, the safe transport of radioactive materials has become a key link in the operation of nuclear facilities. Existing radioactive material transport systems are mostly imported equipment or early domestically produced equipment, and they generally have the following technical problems:

[0003] 1) Inadequate sealing performance: Existing equipment is prone to poor sealing and high leakage risks during transportation, making it difficult to meet the high standards for radioactive material isolation;

[0004] 2) Low positioning accuracy: The mechanical positioning error during the transfer process is large, which can easily lead to poor docking or even material leakage;

[0005] 3) Poor radiation resistance: Ordinary materials and components are prone to performance degradation when working in a high-radiation environment for a long time, resulting in a short equipment life and increased safety risks;

[0006] 4) Low degree of automation: requires a lot of manual intervention, which increases the risk of radiation exposure for operators;

[0007] 5) Low system integration: Most existing equipment is designed for a single function and lacks a linkage and collaboration mechanism, which reduces overall operational efficiency.

[0008] Therefore, there is an urgent need to design a vertical transfer system with reliable safety performance, strong sealing performance, corrosion resistance and radiation resistance, and high degree of operation automation to solve the above-mentioned technical problems existing in the existing technology. Summary of the Invention

[0009] The purpose of the present invention is to provide a radioactive material vertical transport system, aiming to overcome the deficiencies in the prior art and achieve the following technical goals:

[0010] 1) Design a transport mechanism with multiple shielding and sealing functions to ensure that radioactive materials do not leak during transport;

[0011] 2) Use high-precision positioning mechanism to achieve accurate docking of transfer parts;

[0012] 3) Select radiation-resistant materials and components to extend the service life of the equipment in high radiation environments;

[0013] 4) Achieve fully automated operation, reduce manual intervention, and reduce the risk of radiation exposure to operators;

[0014] 5) Improve system integration, achieve collaborative work of various components, and improve overall transportation efficiency.

[0015] To achieve the above object, the present invention provides the following technical solutions:

[0016] A vertical transfer system for moving radioactive materials, comprising:

[0017] 1) A hot chamber slide assembly, which is installed at the bottom of the transfer channel between the shielding operation room and the raw material cutting line operation room, and is characterized by:

[0018] It includes shielding longitudinal beam, shielding moving slide, electric push rod and locking device;

[0019] The shielding longitudinal beam is made of boron-containing stainless steel and has excellent radiation shielding performance;

[0020] The shield moving slide is connected to the shield longitudinal beam through a high-precision linear guide rail to ensure smooth movement;

[0021] The electric push rod is driven by a servo motor to accurately control the displacement distance and speed of the slide;

[0022] The locking device adopts a double locking mechanism to ensure the sealing and stability of the slide plate after docking with the protective container slide plate;

[0023] 2) Cantilever cover assembly,

[0024] The cantilever cover assembly is composed of the following components:

[0025] Cantilever cover: Made of boron steel alloy, it is equipped with a trapezoidal sealing ring and a high-precision six-claw shaft, which can achieve precise locking and unlocking with the 200L drum cover;

[0026] Rotation device: driven by a precision reduction motor, it can realize 360° rotation positioning of the cantilever cover, with a positioning accuracy of ±0.1°; lifting device: composed of a radiation-resistant spiral elevator, it can realize vertical lifting and precise positioning, and the lifting stroke accuracy is controlled within the range of ±0.5mm;

[0027] Counterweight system: adopts counterweight design to reduce driving force requirements and improve system stability;

[0028] Hinge-type pull rod assembly: realizes flexible locking of double covers and compensates for minor errors during docking.

[0029] 3) Protective container components,

[0030] The protective container assembly includes: an outer shell made of high-strength stainless steel with a special surface treatment to improve corrosion resistance; a lead shielding layer with an internal high-purity lead plate with an optimized thickness to effectively shield the gamma rays generated by radioactive materials, reducing the radiation dose rate to the environmental background level; a container slide plate used in conjunction with the hot chamber slide plate, adopting a double sealing structure to ensure airtightness after docking; a self-locking mechanism using a mechanical self-locking principle to ensure the stability and safety of the container during vertical transportation;

[0031] The sealing monitoring system monitors the sealing status of the container in real time, and immediately issues an alarm and initiates emergency procedures in the event of a leak.

[0032] 4) Transfer vehicle components and tracks,

[0033] The transport assembly comprises:

[0034] Body frame: Made of high-strength aluminum alloy material to reduce overall weight while ensuring structural strength; Centering cone: Ensures precise docking between the transfer vehicle and the work station, with positioning error controlled within ±1mm; Lifting platform: Driven by a precision hydraulic system, it can accurately control the lifting height of a 200L barrel; Lifting device: Adopts radiation-proof electric hoist with a load capacity of not less than 500kg; Container guide device: Ensures the stability and positioning accuracy of the protective container during loading and unloading; The track is made of wear-resistant steel and surface hardened to ensure smooth operation of the transfer.

[0035] ) Intelligent control system

[0036] The redundantly designed PLC controller is used as the core, integrating the following functions:

[0037] Operation interface: adopts industrial-grade touch screen to realize parameter setting and status monitoring;

[0038] Positioning control: Through high-precision servo motors and position sensors, accurate positioning of each mechanism is achieved;

[0039] Safety monitoring: integrated with multiple limit detection, pressure monitoring and radiation monitoring functions;

[0040] Emergency handling: equipped with emergency stop function and automatic fault diagnosis system;

[0041] Operation records: Automatically record key parameters and operation steps of the transfer process for easy traceability.

[0042] The vertical transfer system of the present invention has the following significant advantages over the prior art:

[0043] 1) Significantly improved safety: The double-cover sealing design combined with the lead shielding layer reduces the radiation leakage rate by at least 95%, effectively protecting the safety of operators and the environment;

[0044] 2) Significantly improved positioning accuracy: Vertical lifting and rotational positioning are achieved through a high-precision servo system, with positioning accuracy reaching ±0.5mm and ±0.1°, far superior to the existing technology of ±3mm and ±1°;

[0045] 3) Outstanding radiation resistance: Key components are made of radiation-resistant materials, which increases the cumulative radiation dose tolerance by 300% and extends the equipment service life by at least 5 years;

[0046] 4) High degree of automation: The entire process is automated, reducing manual intervention by more than 80%, significantly reducing the operator's radiation exposure risk;

[0047] 5) High system integration: All components work together to increase transfer efficiency by 50%, shortening each transfer cycle from the traditional 30 minutes to less than 15 minutes;

[0048] 6) Strong adaptability: Modular design allows for flexible configuration according to the needs of different nuclear facilities and has a wide range of applications. BRIEF DESCRIPTION OF THE DRAWINGS

[0049] Figure 1 Schematic diagram of the vertical transfer system of the present invention, wherein: 101-cantilever cover assembly, 102-hot chamber slide assembly, 103-protective container assembly, 104-200L barrel, 105-transfer assembly, 106-track;

[0050] Figure 2 This is the structural diagram of the hot chamber slide assembly, where: 201-shielding longitudinal beam, 202-shielding movable slide, 203-guide rail, 204-limit switch, 205-pull plate, 206-electric push rod, 207-locking device;

[0051] Figure 3 This is an exploded view of the cantilever cover assembly, including: 301-cantilever cover (including 30101-seal ring, 30102-cover plate, 30103-movable plate, 30104-sleeve, 30105-rotating rod, 30106-six-claw shaft, 30107-rotating handle, 30108-hinge-type pull rod assembly, 30109-counterweight); 302-slewing device (including 30201-support base, 30202-reduction motor, 30203-transmission chain); 303-lifting device (including 30301-support frame, 30302-drive motor, 30303-screw elevator);

[0052] Figure 4 This is a structural diagram of a 200L barrel, where: 401-barrel body, 402-barrel cover, 403-sealing ring, 404-lifting hole, 405-locking device, 406-locating pin;

[0053] Figure 5This is a structural diagram of the protective container assembly, where: 501 - container slide, 502 - guide groove, 503 - locking mechanism, 504 - outer shell, 505 - lead shielding layer, 506 - sealing ring, 507 - support frame, 508 - self-locking mechanism;

[0054] Figure 6 This is a structural diagram of the transfer component, where: 601-centering cone, 602-body frame, 603-driving wheel, 604-driven wheel, 605-electrical control box, 606-operation panel, 607-lifting device, 608-lifting platform, 609-container guide device. Figure 7 It is the initial state diagram of the device; Figure 8 Schematic diagram of the transfer vehicle's movement; Figure 9 Schematic diagram of the transfer vehicle lifting platform rising to the upper limit; Figure 10 This is a schematic diagram of the hot chamber slide and the container slide being locked and then pulled apart, with the transfer channel connected; Figure 11 This is a schematic diagram of the lifting device rising (dual cover docking process); Figure 12 This is a schematic diagram of the six-claw shaft rotation (double cover locking process); Figure 13 It is a schematic diagram of double cover lifting; Figure 14 It is a schematic diagram of cantilever rotation. DETAILED DESCRIPTION

[0055] The present invention will be further described in detail below with reference to the accompanying drawings and embodiments:

[0056] Example 1:

[0057] This embodiment demonstrates the complete workflow of a vertical transfer system for moving radioactive materials, including the following key steps: Initially, the transfer assembly 105 moves along track 106 to the receiving station, and the protective container assembly 103 is hoisted and secured to the transfer station via a lifting device 607. A 200L drum 104 containing the radioactive material to be transferred is pre-placed within the protective container.

[0058] The hot chamber slide assembly 102 is in a closed state, and the cantilever cover assembly 101 is in a standby position.

[0059] Skateboard docking

[0060] After the transfer and positioning, the lifting platform 608 lifts the protective container assembly 103 to a height aligned with the hot chamber slide assembly 102. The container slide 501 and the hot chamber slide 202 are initially activated by the locking device 207 / 503 through the guide groove 502 and the two slides are firmly connected.

[0061] The electric push rod 206 drives the slides to open in a coordinated manner, connecting the transfer channel. During this process, the positioning accuracy is controlled within the range of ±0.5mm, ensuring perfect docking and sealing.

[0062] Double cover locking

[0063] The transfer lift platform 608 precisely lifts the 200L drum 104 to the bottom of the cantilevered cover 301. The six-claw shaft 30106 on the cantilevered cover aligns with the locking device 405 on the drum lid 402. The lid is securely locked by turning the handle 30107 or by electrically rotating the six-claw shaft. Once locked, the lifting device 303 is activated, and the spiral elevator 30303 lifts the cantilevered cover vertically to a preset height, separating the cover from the drum body. During this process, the sealing ring 30101 / 403 ensures an airtight connection between the drum lid and the cantilevered cover, preventing leakage of radioactive materials.

[0064] Cantilever rotation

[0065] Once the drum lid is lifted, the swivel mechanism 302 activates, driving the cantilevered lid assembly to rotate 180°, fully connecting the 200L drum opening to the hot chamber access. Radioactive materials can now be safely transferred to the upper workstation via the vertical access. During rotation, the counterweight system 30109 ensures smooth operation, while the hinged tie rod assembly 30108 provides additional support and flexibility. Rotational positioning accuracy is controlled within ±0.1°, ensuring precise docking.

[0066] Material Transfer

[0067] Once the tunnel is open, robotic arms or automated equipment at upper stations can safely remove or place radioactive materials in 200L drums. Throughout the transfer process, the 505-layer lead shielding provides comprehensive radiation protection, reducing the radiation dose rate to environmental background levels and ensuring operator safety.

[0068] Reset operation

[0069] After the material transfer is completed, the system performs the reset operation in the reverse order: the rotating device 302 rotates the cantilever cover back to its original position; the lifting device 303 descends and reinstalls the barrel cover back to the 200L barrel; the six-claw shaft 30106 unlocks the barrel cover; the electric push rod 206 drives the slide to close; the locking device 207 / 503 is unlocked; the transfer component 105 lowers the lifting platform and returns to its original position along the track.

[0070] Example 2:

[0071] Control system implementation

[0072] This embodiment describes in detail the implementation of the intelligent control system of the vertical transfer system:

[0073] The control system utilizes a redundant architecture, including a Siemens S7-1500 series master PLC and a backup PLC to ensure system reliability. The control cabinet is equipped with servo drives, safety relays, and a power management system to achieve precise control of each actuator.

[0074] The operator interface uses a 19-inch industrial touch screen to display real-time system status, operating parameters, and alarm information. Operators can use this interface to set transfer parameters, monitor the transfer process, and perform emergency interventions.

[0075] The safety monitoring system includes a multi-sensor network: position sensors monitor the position status of each mechanism; pressure sensors monitor the pressure of hydraulic and pneumatic systems; radiation detectors monitor the radiation level in the working area in real time; and sealing detection devices monitor the airtightness of key sealing parts.

[0076] The control logic utilizes a state machine design, dividing the system workflow into multiple state nodes. Each node has preconditions and completion conditions, ensuring operations are executed in the correct sequence. Any anomaly triggers a safety response, including automatic shutdown, alarm, and safe position reset.

[0077] The system also integrates remote monitoring functions, enabling data exchange with the nuclear facility's central control room via industrial Ethernet, facilitating remote supervision and coordinated operations.

[0078] Example 3:

[0079] Material selection and special treatment

[0080] This embodiment details the material selection and special processing techniques for key system components: Shielding Material: Lead shielding layer 505 utilizes 99.99% high-purity lead, with a thickness optimized based on the intensity of the radiation source, typically 50-100 mm. For neutron sources, a 5-10 mm layer of boron polyethylene is added to the lead layer to enhance neutron shielding effectiveness.

[0081] Structural materials: The load-bearing structure is made of 316L stainless steel, and the surface is electrochemically polished to reduce the adhesion of radioactive substances; the pneumatic and hydraulic components use fluororubber and polytetrafluoroethylene seals, which improve the radiation resistance by 300%.

[0082] Surface treatment:

[0083] All surfaces that come into contact with radioactive materials are treated with a special decontamination coating, with the surface roughness controlled below Ra0.4 to facilitate decontamination and prevent the accumulation of radioactive materials.

[0084] Electrical components: Radiation-hardened electronic components are used, the control system adopts an isolated design, and critical circuits are protected by radiation shielding covers to extend the service life of the electrical system in high radiation environments.

[0085] Sealing material: Using specially formulated fluororubber sealing ring, the radiation resistance is improved by 400%, 6 Gy cumulative dose, it still maintains good elasticity and sealing properties. like Figures 7 to 14 As shown, a schematic diagram of the workflow process of the present invention is given. The workflow of the present invention comprises: Step 1, such as Figure 7 and Figure 8 As shown, the transfer vehicle stops at the equipment receiving station, waiting for the crane to lift the protective container. It runs at a slower speed when starting and stopping, and runs at a higher speed in the middle section. Step 2, such as Figure 9 As shown, after the trolley moves into position, the trolley lifting platform is raised to the upper limit. Step 3, such as Figure 10 As shown, the hot chamber slide locking pin is locked together with the container slide; then the two slides are pulled apart together, and the transfer channel is now connected. Step 4, such as Figure 11 As shown, the lifting device of the transfer vehicle is started to lift the 200L barrel in the protective container into the channel and dock it with the cantilever cover. This action is driven by a servo motor and the sensor assists in detecting the position. Step 5, such as Figure 12 As shown, the lock tongue motor is operated to drive the six-claw shaft to rotate, so that the double covers are locked. At the same time, the 200L barrel cover is separated from the barrel body and the cantilever cover is separated from the channel. Step 6, such as Figure 13 As shown in the figure, operate the lifting device to lift the double cover and make the bottom of the barrel cover completely higher than the upper surface of the sealing flange. Step 7, such as Figure 14 As shown, operate the slewing device to rotate the cantilever, and the 200L barrel is connected with the red zone to prepare for receiving materials.

Claims

1. A vertical transport system for moving radioactive materials, characterized in that: include: The hot chamber slide assembly (102) is installed on the transfer channel at the bottom of the shielding operation room and the raw material cutting line operation room. The hot chamber slide assembly (102) includes a shielding longitudinal beam (201), a shielding moving slide (202), an electric push rod (206) and a locking device ( 207), the slide is driven to move and lock by an electric push rod; A cantilever cover assembly (101) comprises a cantilever cover (301), a slewing device (302) and a lifting device (303); the cantilever cover is locked with the cover of a container of radioactive material to be transported via a six-claw shaft (30106), and is equipped with a lifting device and a slewing device to achieve vertical lifting and rotation; The protective container assembly (103) includes an outer shell (504), a lead shielding layer (505), a container slide (501) and a self-locking mechanism (508), wherein the container slide is docked with the hot chamber slide to achieve the connection of the transfer channel; A transfer assembly (105) and a track (106), wherein the transfer assembly (105) includes a vehicle frame (602), a lifting platform (608) and a lifting device (607) for horizontally transporting and lifting the protective container; The control system, including PLC controller, operation interface, positioning control unit and safety monitoring device, realizes the automatic control and safety monitoring of the system.

2. The vertical transfer system according to claim 1, characterized in that: The cantilever cover assembly (101) includes a sealing ring (30101), a counterweight (30109) and a hinged pull rod assembly (30108), wherein the sealing ring realizes an airtight connection between the cantilever belt cover and the container cover, the counterweight is used to balance the cantilever weight, and the hinged pull rod assembly provides additional support and flexible adjustment.

3. The vertical transfer system according to claim 1, characterized in that: The lead shielding layer (505) of the protective container assembly (103) has a thickness of 50-100 mm, which can reduce the radiation dose rate generated by the radioactive material in the container to the environmental background level.

4. The vertical transfer system according to claim 1, characterized in that: The transfer assembly (105) is equipped with a centering cone (601) and a container guide device (609). The centering cone ensures the precise docking of the transfer vehicle with the work station, and the container guide device ensures the stability and positioning accuracy of the protective container during loading and unloading.

5. The vertical transfer system according to claim 1, characterized in that: The control system adopts a redundant architecture design, including a main control PLC and a backup PLC, integrating a servo drive, a position sensor, a pressure sensor, a radiation detector and a sealing detection device to achieve precise control and safety monitoring of the system.

6. The vertical transfer system according to claim 1, characterized in that: The key components of the system are made of radiation-resistant materials, including 316L stainless steel structural parts, fluororubber sealing rings and radiation-hardened electronic components. 6 Gy and still maintain normal working performance.

7. The vertical transfer system according to claim 1, characterized in that: The positioning accuracy of the slewing device (302) of the cantilever cover assembly (101) is ±0.1°, and the lifting accuracy of the lifting device (303) is ±0.5mm, ensuring accurate docking during the transportation process.

8. The vertical transfer system according to claim 1, characterized in that: The workflow for achieving automated control and safety monitoring of the system includes six steps: initial positioning, slide docking, double cover locking, cantilever rotation, material transfer, and reset operation. Each step is set with preconditions and completion conditions to ensure that the operations are performed in the correct order.

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