High-temperature gas cooled reactor fuel handling system, unblocking method, and high-temperature gas cooled reactor

Abstract

The present application relates to the field of nuclear reactors, and discloses a high-temperature gas-cooled reactor fuel loading and unloading system, a dredging method and a high-temperature gas-cooled reactor. The high-temperature gas-cooled reactor fuel loading and unloading system comprises: a back-to-core drop tube section, which transports the circulating fuel elements back to the core. The blockage dredging device is installed on the back-to-core drop tube section and comprises an extension assembly, which is arranged at one end of the back-to-core drop tube section away from the core. The extension assembly comprises a fixed end and a driving end that can extend and retract relative to the fixed end. The fixed end is fixedly arranged, and the driving end faces the back-to-core drop tube section. The extension path of the driving end is arranged along the axial direction of the back-to-core drop tube section. The driving end can enter and exit the back-to-core drop tube section and drive the spherical elements. By driving the blocked spherical elements through the extension assembly, compared with the traditional pneumatic dredging method, the blocked spherical elements can be processed more directly and effectively, the dredging efficiency is greatly improved, the dredging time is reduced, and the reliability is significantly improved.

Description

Technical Field

[0001] This invention relates to the field of nuclear reactor technology, specifically to a high-temperature gas-cooled reactor fuel loading and unloading system, a dredging method, and a high-temperature gas-cooled reactor. Background Technology

[0002] In high-temperature cold reactor nuclear power plants, spherical elements are used as fuel assemblies for the reactor. This design allows for fuel cycling and loading / unloading without shutting down the reactor, so as to continuously meet the reactivity requirements of the reactor core.

[0003] As a critical system, the fuel loading and unloading system is used to reload spherical elements that have not yet reached their final burnup depth into the reactor core via pneumatic conveying, thereby achieving fuel recycling. Alternatively, it can receive spherical elements from the new fuel supply system and replenish the reactor core according to the principle of regular and quantitative replenishment, ensuring the continuous and stable operation of the reactor.

[0004] In actual operation, spherical fuel elements are prone to jamming at the fuel feed point. Currently, the main solution for clearing this problem relies on pneumatic suction. This method involves disturbing the jammed fuel element using pneumatic suction, and then clearing the blockage using the weight of the fuel element itself or the purging effect of high-pressure helium gas. However, this method is inefficient, time-consuming, and unreliable. Summary of the Invention

[0005] In view of this, the present invention provides a high-temperature gas-cooled reactor fuel loading and unloading system, a dredging method, and a high-temperature gas-cooled reactor to solve or improve the problems of poor dredging efficiency, long time consumption, and poor reliability in related technologies.

[0006] In a first aspect, the present invention provides a high-temperature gas-cooled reactor fuel loading and unloading system, comprising:

[0007] The core return ball drop tube section is connected to the core and is used to transport spherical components;

[0008] A telescopic assembly is provided at the end of the core return ball drop tube section away from the core. The telescopic assembly includes a fixed end and a drive end that can extend and retract relative to the fixed end. The fixed end is fixedly disposed, and the drive end faces the core return ball drop tube section. The extension and retraction path of the drive end is arranged along the axial direction of the core return ball drop tube section. The drive end can enter and exit the core return ball drop tube section and drive the spherical element.

[0009] In one optional embodiment, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a lift section, which is connected to the core return ball drop section and the feeding device, respectively, and the included angle between the core return ball drop section and the lift section is an acute angle.

[0010] In one optional embodiment, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a first arc-shaped pipe section, which connects the lifting pipe section and the core return ball dropping pipe section. The pipe wall of the first arc-shaped pipe section is provided with a through-hole, which is opposite to the pipe opening of the core return ball dropping pipe section and allows the drive end to pass through.

[0011] And / or, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a transition pipe section and a second arc-shaped pipe section, the second arc-shaped pipe section connecting the transition pipe section and the core return ball drop pipe section, the transition pipe section being connected to the reactor core, and the included angle between the transition pipe section and the core return ball drop pipe section being an obtuse angle.

[0012] In one optional embodiment, the high-temperature gas-cooled reactor fuel loading and unloading system further includes:

[0013] A presence detection device is provided, which is used to send a presence signal when a spherical element is present in the core return ball drop tube section;

[0014] A control device is electrically connected to the presence detection device and the telescopic assembly. When the control device determines that the duration of the presence signal exceeds a preset duration, it controls the drive end to extend into the core return ball drop tube section.

[0015] In one optional embodiment, the presence detection device includes a radiation detection device for detecting the amount of radiation in the core return ball drop tube section. When the control device determines that the amount of radiation exceeds a radiation threshold and the duration exceeds a preset duration, it controls the drive end to extend into the core return ball drop tube section.

[0016] And / or, the presence detection device includes a ball counter, which is used to detect the number of spherical elements discharged from the core return ball drop tube section. When the control device determines that the number of spherical elements has not increased and the duration exceeds a preset duration, it controls the drive end to extend into the core return ball drop tube section.

[0017] In one optional embodiment, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a force measuring device and a control device.

[0018] The force measuring device is disposed on the telescopic component and is used to detect the driving force of the telescopic component. The control device is electrically connected to the force measuring device and the telescopic component respectively, and is used to control the extension speed of the telescopic component to decrease when it is determined that the driving force is greater than or equal to the driving force threshold.

[0019] In one optional embodiment, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a position detection device and a control device.

[0020] The position detection device is disposed on the telescopic component and is used to detect the elongation of the telescopic component. The control device is electrically connected to the position detection device and the telescopic component respectively, and is used to control the telescopic component to stop elongating when the elongation is determined to be greater than or equal to the elongation threshold.

[0021] In one optional embodiment, the telescopic assembly includes a motor, a lead screw, a nut, a drive rod, and a guide structure. The motor is fixedly installed, the lead screw is connected to the output shaft of the motor, the nut is threadedly connected to the lead screw, the drive rod is connected to the nut and can enter and exit the core return ball drop tube section, and the guide structure is fixedly installed and guides the nut along the axial direction of the core return ball drop tube section.

[0022] Alternatively, the telescopic assembly may include a pneumatic cylinder or a hydraulic cylinder.

[0023] Secondly, the present invention also provides a method for unblocking blockages, comprising:

[0024] Acquire a presence signal, which indicates the duration of the presence of a spherical element within the core return ball drop section;

[0025] When the duration of the presence of the spherical element in the core return ball drop tube exceeds a preset duration, the drive end of the telescopic component is controlled to extend into the core return ball drop tube to drive the spherical element.

[0026] Thirdly, the present invention also provides a high-temperature gas-cooled reactor, including the high-temperature gas-cooled reactor fuel loading and unloading system as described above, or using the unblocking method as described above.

[0027] The high-temperature gas-cooled reactor fuel loading and unloading system provided by this invention drives the stuck spherical element through a telescopic component. Compared with the traditional method of relying on pneumatic force to clear blockages, it can more directly and effectively deal with the stuck spherical element, greatly improving clearing efficiency, reducing clearing time, and significantly enhancing reliability. For example, it can not only solve blockages caused by wear debris accumulation, but also overcome mechanical jamming caused by processing errors, thermal deformation, etc., making it more adaptable.

[0028] The unblocking method provided by this invention drives the stuck spherical element through a telescopic component. Compared with the traditional method that relies on pneumatic force, it can more directly and effectively deal with the stuck spherical element, greatly improving unblocking efficiency, reducing unblocking time, and significantly enhancing reliability. For example, it can not only solve the blockage caused by the accumulation of grinding debris, but also overcome mechanical jamming caused by processing errors, thermal deformation, etc., making it more adaptable.

[0029] The high-temperature gas-cooled reactor provided by this invention has corresponding advantages because it includes the high-temperature gas-cooled reactor fuel loading and unloading system provided by this invention or uses the unblocking method provided by this invention. Attached Figure Description

[0030] To more clearly illustrate the specific embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the specific embodiments or the prior art will be briefly introduced below. Obviously, the drawings described below are some embodiments of the present invention. For those skilled in the art, other drawings can be obtained from these drawings without creative effort.

[0031] Figure 1 This is a schematic diagram of a high-temperature gas-cooled reactor fuel loading and unloading system provided in an embodiment of the present invention;

[0032] Figure 2 This is a schematic diagram of the structure of the telescopic assembly used to clear the core return ball drop tube section according to an embodiment of the present invention;

[0033] Figure 3 This is a schematic diagram of the structure of a telescopic component provided in an embodiment of the present invention;

[0034] Figure 4 This is a control principle diagram of a high-temperature gas-cooled reactor fuel loading and unloading system provided in an embodiment of the present invention.

[0035] Explanation of reference numerals in the attached figures:

[0036] 1. Core return ball drop pipe section; 2. Core; 3. Telescopic assembly; 301. Fixed end; 302. Drive end; 303. Motor; 304. Lead screw; 305. Nut; 306. Drive rod; 3061. Rod body; 3062. Push plate; 4. Lifting pipe section; 5. First arc-shaped pipe section; 6. Transition pipe section; 7. Second arc-shaped pipe section; 8. Presence detection device; 801. Radiation detection device; 802. Ball counter; 9. Control device; 10. Force measuring device; 11. Position detection device; 12. Spherical element; 13. Mounting cylinder; 14. Core unloading pipe section. Detailed Implementation

[0037] To make the objectives, technical solutions, and advantages of the embodiments of the present invention clearer, the technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0038] The following is combined with Figures 1 to 4This describes the high-temperature gas-cooled reactor fuel loading and unloading system provided in the embodiments of the present invention.

[0039] Specifically, the high-temperature gas-cooled reactor fuel loading and unloading system includes a core return ball drop tube section 1 and a telescopic assembly 3.

[0040] The core return ball drop section 1 is connected to the core 2 and is used to transport the spherical element 12. Optionally, the core return ball drop section 1 is inclined, and the height of the end of the core return ball drop section 1 near the core 2 is less than the height of the end near the feeding device, so that the spherical element 12 can run along the core return ball drop section 1 under the action of gravity, reducing the pneumatic load.

[0041] The telescopic assembly 3 is located at the end of the core return ball drop pipe section 1 away from the core 2. The telescopic assembly 3 includes a fixed end 301 and a driving end 302, and the driving end 302 can extend and retract relative to the fixed end 301. The fixed end 301 is fixedly installed, for example, the fixed end 301 is connected and fixed to the core return ball drop pipe section 1, so that the telescopic assembly 3 can be integrated into the pipeline, improving the structural compactness of the fuel loading and unloading system.

[0042] The drive end 302 faces the core return ball drop tube section 1, and the extension path of the drive end 302 is arranged along the axial direction of the core return ball drop tube section 1. The drive end 302 can enter and exit the core return ball drop tube section 1 and drive the spherical element 12. Specifically, it can drive the spherical element 12 in the core return ball drop tube section 1 to move closer to the core 2.

[0043] In this embodiment, during normal operation of the high-temperature gas-cooled reactor fuel loading and unloading system, the spherical element 12 can smoothly pass through the core return spherical drop pipe section 1 and enter the reactor core 2 under the action of pneumatic force and gravity. However, since the spherical element 12 generates abrasive debris during operation, the debris accumulates in the core return spherical drop pipe section 1, which can easily lead to the spherical element 12 getting stuck. In addition, due to processing errors or thermal expansion and contraction, the spherical element 12 may also get stuck.

[0044] When a problem occurs where the spherical element 12 is stuck in the core return ball drop tube section 1, the drive end 302 of the telescopic assembly 3 can be allowed to enter the core return ball drop tube section 1. Since the thrust direction of the drive end 302 is consistent with the axial direction of the core return ball drop tube section 1, the spherical element 12 can be driven to move closer to the core 2, thereby clearing the stuck spherical element 12 in the core return ball drop tube section 1.

[0045] When there is no blockage problem in the core return ball drop tube section 1, the drive end 302 of the telescopic component 3 can be discharged from the core return ball drop tube section 1 to avoid the drive end 302 affecting the normal operation of the ball element 12 in the core return ball drop tube section 1.

[0046] This design, compared to traditional methods that rely on pneumatic force for unblocking, can more directly and effectively address the blockage of the spherical element 12, significantly improving unblocking efficiency, reducing unblocking time, and also significantly enhancing reliability. For example, it can not only solve blockages caused by the accumulation of grinding debris, but also overcome mechanical jamming caused by machining errors, thermal deformation, etc., making it more adaptable.

[0047] When there is no blockage problem in the core return ball drop tube section 1, the drive end 302 of the telescopic component 3 can be discharged from the core return ball drop tube section 1, avoiding interference of the drive end 302 on the normal operation of the spherical element 12 in the core return ball drop tube section 1, and ensuring that the system can smoothly transport the spherical element 12 under normal operating conditions.

[0048] In some embodiments provided by the present invention, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a riser section 4.

[0049] The riser section 4 is connected to both the core return ball drop section 1 and the feeding device, and the angle between the core return ball drop section 1 and the riser section 4 is an acute angle. For example, refer to... Figure 1 As shown, the lift section 4 is set vertically, and the height of the end of the return core ball drop section 1 near the lift section 4 is higher than the height of the end near the core 2. The return core ball drop section 1 is connected to the top of the core 2.

[0050] In this embodiment, the lift section 4 raises the spherical element 12 to a high position, and the return-to-core ball drop section 1 utilizes the tilt angle and height difference to convert gravitational potential energy into kinetic energy, allowing the element to slide quickly into the core 2, reducing dependence on high-pressure helium. The return-to-core ball drop section 1 connects to the top of the core 2, and the spherical elements 12 are evenly distributed from top to bottom, avoiding potential local accumulation.

[0051] In some embodiments provided by the present invention, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a core unloading pipe section 14.

[0052] The core unloading pipe section 14 is connected to the lower end of the core 2 and is used to discharge the spherical element 12 inside the core 2.

[0053] In this embodiment, the core unloading pipe section 14 is connected to the lower end of the core 2, providing a dedicated channel for the discharge of the spherical element 12 inside the core. This allows the spherical element 12 to be discharged smoothly from the core 2 along a predetermined path and direction, avoiding disordered flow or blockage of the spherical element 12 within the core 2. This ensures the smooth progress of the unloading process of the spherical element 12, maintains the normal renewal of fuel within the core 2, and ensures the stable operation of the core 2.

[0054] In some embodiments provided by the present invention, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a first arc-shaped pipe section 5, which connects the lifting pipe section 4 and the core return ball dropping pipe section 1. The pipe wall of the first arc-shaped pipe section 5 is provided with a through port, which is opposite to the pipe opening of the core return ball dropping pipe section 1 and can be passed through by the drive end 302.

[0055] In this embodiment, the first arc-shaped tube segment 5 transitions between the lifting tube segment 4 and the core return ball dropping tube segment 1, so that the movement direction of the spherical element 12 naturally transitions from vertical lifting to inclined ball dropping, avoiding the problem of sudden speed drop, reducing the probability of collision between the element and the tube wall, and reducing the generation of wear debris.

[0056] In addition, the through-hole on the first arc-shaped pipe section 5 is opposite to the pipe opening of the core return ball drop pipe section 1, ensuring that the extension path of the drive end 302 is coaxially aligned with the core return ball drop pipe section 1, and the thrust direction is consistent with the movement direction of the spherical element 12, so as to avoid the lateral component force causing the element to shift or be blocked twice.

[0057] In some embodiments provided by the present invention, the telescopic component 3 includes a motor 303, a lead screw 304, a nut 305, a drive rod 306, and a guide structure.

[0058] The motor 303 is fixedly installed, for example, the motor 303 is connected to at least one of the first arc-shaped tube section 5 and the core return ball drop tube section 1.

[0059] The lead screw 304 is connected to the output shaft of the motor 303, the nut 305 is threadedly connected to the lead screw 304, and the drive rod 306 is connected to the nut 305 and can enter and exit the core return ball drop tube section 1. It can be understood that the lead screw 304 is arranged along the axial direction of the core return ball drop tube section 1, for example, the lead screw 304 is arranged coaxially with the core return ball drop tube section 1.

[0060] The guide structure is fixedly installed and guides the nut 305 along the axial direction of the core return ball drop tube section 1. For example, the guide structure is connected to at least one of the first arc-shaped tube section 5 and the core return ball drop tube section 1. Optionally, the guide structure is configured as a guide block, and the nut 305 is provided with a guide groove that slides with the guide block; or, the guide structure is configured as a guide groove, and the nut 305 is provided with a guide block that slides with the guide groove.

[0061] In this embodiment, the motor 303 serves as a power source, providing stable and precisely controllable power output. Through the threaded connection between the lead screw 304 and the nut 305, the rotational motion of the motor 303 is converted into the linear motion of the nut 305, which in turn drives the drive rod 306 to move axially along the core return ball drop pipe section 1. This transmission method allows for precise control of the extension and retraction distance and speed of the drive rod 306, thereby accurately driving the jammed spherical element 12 and improving the accuracy of unblocking.

[0062] Furthermore, the motor 303 and the guide structure are respectively connected to at least one of the first arc-shaped pipe section 5 and the core return ball drop pipe section 1, so that the telescopic assembly 3 is tightly integrated with the pipeline structure of the fuel loading and unloading system, enhancing the overall structural stability. When the drive rod 306 pushes the spherical element 12, it can effectively withstand the reaction force, ensuring the stable operation of the telescopic assembly 3 and reducing the impact of vibration or swaying on the system.

[0063] In addition, the guide structure guides the nut 305 along the axial direction of the core return ball drop tube section 1, ensuring the straightness and accuracy of the nut 305 and the drive rod 306 during movement. This helps to prevent the drive rod 306 from shifting or jamming during extension and retraction, ensuring that it can smoothly enter and exit the core return ball drop tube section 1 and accurately act on the jamming spherical element 12, thus improving the reliability and stability of the system.

[0064] Optionally, the high-temperature gas-cooled reactor fuel loading and unloading system also includes an installation cylinder 13.

[0065] Specifically, the mounting cylinder 13 is located at the end of the core return ball drop tube section 1 away from the core 2, and extends axially along the core return ball drop tube section 1. One end of the mounting cylinder 13 is connected to the first arc-shaped tube section 5, and the through port on the first arc-shaped tube section 5 is opposite to the mounting cylinder 13. Optionally, the mounting cylinder 13 is welded to the first arc-shaped tube section 5.

[0066] A motor 303 is mounted at the other end of the mounting cylinder 13. For example, the motor shaft of the motor 303 extends into the mounting cylinder 13, the motor housing of the motor 303 is located outside the mounting cylinder 13, and the lead screw 304 is located inside the mounting cylinder 13. A guide structure can be provided on the inner wall of the mounting cylinder 13. Optionally, a sealing structure is provided between the motor 303 and the mounting cylinder 13.

[0067] During the unblocking process, the drive rod 306 extends from the mounting cylinder 13 into the core return ball drop pipe section 1. After the unblocking is completed, the drive rod 306 retracts into the mounting cylinder 13.

[0068] In this embodiment, the two ends of the mounting cylinder 13 are connected to the first arc-shaped pipe section 5 and the motor 303, respectively, forming a closed chamber inside the mounting cylinder 13. This prevents dust and impurities from the external environment from entering the mounting cylinder 13 and damaging precision components such as the lead screw 304. Simultaneously, it prevents gas leakage from the pipeline, maintains pressure balance within the system, ensures reliable system operation, reduces the risk of failure due to poor sealing, and improves the stability and reliability of the entire high-temperature gas-cooled reactor fuel loading and unloading system.

[0069] Furthermore, the mounting sleeve 13 encloses components such as the lead screw 304, providing them with excellent protection. The internal components are less susceptible to external environmental factors such as wear and corrosion, extending their service life and reducing maintenance and replacement costs.

[0070] Optionally, the drive rod 306 includes a rod body 3061 and a push plate 3062. For example, the rod body 3061 is a hollow cylindrical structure. The rod body 3061 is fitted on the outside of the lead screw 304, and one end of the rod body 3061 is connected to the nut 305. The other end of the rod body 3061 is connected to the push plate 3062, which is used to abut against the spherical element 12.

[0071] In this embodiment, the rod 3061 adopts a hollow cylindrical structure, which greatly reduces the weight of the drive rod 306. This helps to reduce the load on the motor 303, reduce energy consumption, and also makes the movement of the drive rod 306 more flexible, enabling it to respond more quickly to the drive of the motor 303 and improve the unblocking efficiency of the spherical element 12.

[0072] Furthermore, the space in a high-temperature gas-cooled reactor fuel loading and unloading system is typically quite compact, making efficient use of axial space crucial. The rod 3061 is fitted onto the outside of the lead screw 304, allowing them to share a certain space in the axial direction, thus avoiding an increase in axial dimensions due to their side-by-side arrangement. This design effectively reduces the space occupied by the telescopic assembly 3 in the axial direction, facilitating a compact layout of the entire fuel loading and unloading system and better adapting to limited installation space.

[0073] Optionally, the push plate 3062 is configured as an arc-shaped plate recessed into the rod 3061. For example, the radius of the arc-shaped plate is greater than or equal to the radius of the spherical element 12.

[0074] In this embodiment, the spherical element 12 is the object to be transported in the high-temperature gas-cooled reactor fuel loading and unloading system. The shape of the arc-shaped plate can better fit the outer surface of the spherical element 12. When the pusher plate 3062 pushes the spherical element 12, this fit increases the contact area between the two, allowing the thrust to be applied to the spherical element 12 more evenly. This avoids damage to the surface of the spherical element 12 due to local stress concentration, ensuring the integrity and performance of the spherical element 12.

[0075] The improved fit makes it less likely for the spherical element 12 to slip or deviate when the pusher plate 3062 pushes it. Within the core return ball drop tube section 1, especially in the case of clearing blockages, the position of the spherical element 12 is relatively fixed. The arc-shaped pusher plate 3062 can effectively grasp the spherical element 12, ensuring that it moves along the predetermined direction, thus improving the accuracy and efficiency of the push.

[0076] Because the contact and pushing method between the arc-shaped pusher plate 3062 and the spherical element 12 is more reasonable, it can more effectively transmit power when clearing the spherical element 12 stuck in the core return spool pipe section 1, pushing the spherical element 12 out of the stuck position. That is, the arc-shaped pusher plate 3062 can achieve a better clearing effect with less force, improving the reliability and operating efficiency of the entire fuel loading and unloading system.

[0077] In actual operation, the spherical element 12 in the core return ball drop tube section 1 may become stuck in a complex manner. The arc-shaped pusher plate 3062 can better adapt to the sticking at different angles and positions. By adjusting the contact point and angle with the spherical element 12, it can more flexibly deal with various sticking scenarios, further improving the success rate of unblocking.

[0078] Of course, the telescopic assembly 3 is not limited to the form of the lead screw 304 described above. For example, in the embodiment not shown in this invention, the telescopic assembly 3 includes a cylinder or a hydraulic cylinder. Optionally, the cylinder body of the cylinder or hydraulic cylinder is connected to the end of the mounting cylinder 13 away from the core return ball drop tube section 1. For example, the cylinder body is located outside the mounting cylinder 13, and the piston rod of the cylinder or hydraulic cylinder extends into the mounting cylinder 13. Alternatively, it can be understood that the fixed end 301 of the telescopic assembly 3 is located outside the mounting cylinder 13 and connected to the end of the mounting cylinder 13 away from the core return ball drop tube section 1, and the driving end 302 of the telescopic assembly 3 extends into the mounting cylinder 13.

[0079] In some embodiments provided by the present invention, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a transition pipe section 6 and a second arc-shaped pipe section 7.

[0080] The second arc-shaped pipe section 7 connects the transition pipe section 6 and the core return ball drop pipe section 1. The transition pipe section 6 is connected to the core 2, and the angle between the transition pipe section 6 and the core return ball drop pipe section 1 is an obtuse angle. For example, the transition pipe section 6 is arranged parallel to the riser pipe section 4, and the transition pipe section 6 is connected to the top of the core 2.

[0081] In this embodiment, the obtuse angle connection between the core return ball drop section 1 and the transition section 6 reduces the kinetic energy loss of the spherical element 12, keeping its speed within a reasonable range. The first arc-shaped section 5 (connecting the lift section 4 and the core return ball drop section 1) and the second arc-shaped section 7 (connecting the core return ball drop section 1 and the transition section 6) work together to form a continuous and smooth turning, thereby reducing the kinetic energy loss of the spherical element 12 during operation and making its operation smoother.

[0082] In some embodiments provided by the present invention, the high-temperature gas-cooled reactor fuel loading and unloading system further includes an presence detection device 8 and a control device 9.

[0083] The presence detection device 8 is used to send a presence signal when the spherical element 12 is present in the core return ball drop tube section 1.

[0084] The control device 9 is electrically connected to both the presence detection device 8 and the telescopic assembly 3. For example, the control device 9 is electrically connected to the motor 303, a pneumatic cylinder, or a hydraulic cylinder, and can control the rotation of the motor 303, the extension and retraction of the pneumatic cylinder, or the extension and retraction of the hydraulic cylinder. The control device 9 can be a programmable logic controller, a digital signal processor, or an industrial computer.

[0085] When the control device 9 determines that the duration of the signal exceeds a preset duration, the control drive end 302 extends into the core return ball drop tube section 1 to drive the spherical element 12 inside the core return ball drop tube section 1 to move towards the core 2. It is understood that the preset duration can be flexibly adjusted according to actual operating conditions and system requirements to adapt to the requirements for jamming judgment under different operating conditions.

[0086] In this embodiment, the presence detection device 8 can monitor the presence of the spherical element 12 in the core return ball drop tube section 1 in real time. When the presence of the spherical element 12 is detected, a presence signal is sent. The control device 9 determines whether a blockage has occurred based on the duration of the presence signal. Once it is determined that the duration of the presence signal exceeds a preset duration, it indicates that the spherical element 12 has stayed in the core return ball drop tube section 1 for too long, and a blockage is very likely to have occurred. At this time, the control drive end 302 extends into the core return ball drop tube section 1 to clear the blockage.

[0087] This automatic detection and response mechanism can promptly identify blockage problems and take corresponding measures, greatly improving the system's efficiency in handling blockage faults, reducing manual intervention, and lowering the workload and risk of misjudgment for operators.

[0088] Furthermore, by promptly detecting and addressing the jamming issue, the impact of spherical element 12 jamming on the normal operation of the fuel loading and unloading system was avoided. This ensured that spherical element 12 could be continuously and stably delivered to core 2, maintaining the normal fuel supply to the reactor, thereby improving the stability and reliability of the entire high-temperature gas-cooled reactor system, reducing system shutdowns or operational anomalies caused by jamming, and improving the reactor's power generation efficiency and safety.

[0089] In some embodiments provided by the present invention, the detection device 8 includes a radiation detection device 801.

[0090] Among them, the radiation detection device 801 is used to detect the amount of radiation in the core return ball drop tube section 1, and the radiation detection device 801 is electrically connected to the control device 9.

[0091] When the control device 9 determines that the radiation amount exceeds the radiation threshold and the duration exceeds the preset duration, the control drive end 302 extends into the core return ball drop tube section 1.

[0092] In this embodiment, the spherical element 12 serves as a fuel assembly in the reactor and typically exhibits high radioactivity. The radiation detection device 801 can accurately determine the presence of the spherical element 12 by detecting the radiation level within the core return spherical tube section 1. The radiation detection is unaffected by factors such as the surface condition, color, and material of the spherical element 12, resulting in more reliable detection results. This effectively avoids false positives and false negatives, thereby accurately providing the control device 9 with a signal indicating the presence of the spherical element 12.

[0093] Control device 9 determines the blockage situation based on whether the radiation level exceeds the radiation threshold and the duration exceeds a preset duration. This dual-judgment mechanism is more scientific and reasonable. Radiation exceeding the threshold indicates the presence of the spherical element 12, while the duration exceeding the preset duration indicates that the spherical element 12 has remained at that position for too long, likely indicating blockage. This method can more accurately identify blockage faults, avoid misoperation caused by brief radiation fluctuations or other abnormalities, and improve the accuracy and reliability of the system's blockage fault judgment.

[0094] The radiation detection device 801 operates on the principle of radiation signals and is not affected by factors such as high temperature or high pressure, exhibiting strong environmental adaptability. Even when the environment inside the reactor core 2 or around the pipeline changes, it can still accurately detect the radiation level of the spherical element 12, ensuring that the system can operate normally under various conditions.

[0095] Optionally, the radiation detection device 801 may be a gas ionization detector, a scintillation detector, or a semiconductor detector.

[0096] In some embodiments provided by the present invention, the presence detection device 8 includes a ball counter 802.

[0097] Among them, the ball counter 802 is used to detect the number of spherical elements 12 discharged from the core return ball drop tube section 1, and the ball counter 802 is electrically connected to the control device 9.

[0098] When the control device 9 determines that the number of spherical elements 12 has not increased and the duration exceeds the preset duration, the control drive end 302 extends into the core return ball drop tube section 1.

[0099] In this embodiment, optionally, when the ball counter 802 detects the discharge of the spherical element 12, it transmits a high-level signal to the control device 9; when the ball counter 802 does not detect the discharge of the spherical element 12, it transmits a low-level signal to the discharge device. That is, when the control device 9 determines that the duration of the low-level signal exceeds a preset duration, it controls the telescopic component 3 to operate.

[0100] The ball counter 802 directly and intuitively displays the flow of spherical elements 12 during fuel loading and unloading by detecting the number of spherical elements 12 discharged from the core return ball drop tube section 1. Based on the number of spherical elements 12 provided by the ball counter 802, the control device 9 can clearly determine whether the spherical elements 12 are being discharged normally. If the number does not increase and the duration exceeds a preset time, it is easy to infer that the spherical elements 12 are experiencing abnormalities such as blockage within the core return ball drop tube section 1, providing a clear basis for subsequent handling.

[0101] Using quantity as the detection indicator, it is not affected by the radiation intensity fluctuations, appearance changes, or environmental factors (such as temperature and humidity) of the spherical element 12. As long as the spherical element 12 passes through the core return ball drop tube 1 normally, the ball counter 802 can accurately record it, which increases the dimensions of judgment and reduces the possibility of misjudgment caused by interference from other factors, thereby improving the accuracy of detecting the state of the spherical element 12 in the tube.

[0102] The quantity information of the spherical elements 12 recorded by the spherical counter 802 can be easily integrated into the monitoring platform of the entire high-temperature gas-cooled reactor fuel loading and unloading system. Operators can monitor the progress and status of fuel loading and unloading in real time through the monitoring platform. When abnormal quantities occur, the system can issue alarms in a timely manner and take corresponding measures, which helps to achieve automated monitoring and management of the entire loading and unloading process, and improve the system's operating efficiency and reliability.

[0103] Optionally, the ball counter 802 can be a photoelectric ball counter 802, an electromagnetic induction ball counter 802, or a capacitive ball counter 802.

[0104] In some embodiments provided by the present invention, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a force measuring device 10 and a control device 9.

[0105] The force measuring device 10 is disposed on the telescopic assembly 3 and is used to detect the driving force of the telescopic assembly 3. Optionally, the force measuring device 10 can be a pressure sensor, for example, a pressure sensor disposed between the nut 305 and the drive rod 306. For a cylinder or hydraulic cylinder, the pressure sensor can be disposed between the piston rod and the corresponding drive rod 306.

[0106] The control device 9 is electrically connected to the force measuring device 10 and the telescopic assembly, and is used to control the extension speed of the telescopic assembly to decrease when the driving force is determined to be greater than or equal to the driving force threshold.

[0107] In this embodiment, by setting a force measuring device 10, such as a pressure sensor, on the telescopic component 3, the driving force of the telescopic component 3 can be monitored accurately in real time. When the driving force is greater than or equal to the driving force threshold, the control device 9 promptly controls the extension speed of the telescopic component to decrease, which can effectively prevent the telescopic component 3 from causing excessive compression, collision, or other damage to the spherical element 12 due to excessive driving force.

[0108] In some embodiments provided by the present invention, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a position detection device 11 and a control device 9.

[0109] The position detection device 11 is disposed on the telescopic component 3 and is used to detect the elongation of the telescopic component 3. The control device 9 is electrically connected to the position detection device 11 and the telescopic component respectively, and is used to control the telescopic component to stop elongating when the elongation is determined to be greater than or equal to the elongation threshold.

[0110] In this embodiment, the position detection device 11 can monitor the elongation of the telescopic component 3 in real time with precision. When the elongation reaches a preset elongation threshold, the control device 9 immediately controls the telescopic component to stop elongating. This ensures that the components driven by the telescopic component 3 (such as the drive end 302 extending into the core return ball drop tube section 1) accurately reach the expected position, avoiding damage to the internal structure of the high-temperature gas-cooled reactor due to excessive elongation, or failure to complete the unblocking due to insufficient elongation, thereby achieving precise control of the fuel loading and unloading position.

[0111] In addition, preventing the telescopic component 3 from over-stretching can protect itself and other connected components, such as the drive rod 306 and nut 305, and prevent these components from deforming or being damaged due to excessive pressure or tension, thereby extending the service life of each component of the system and reducing maintenance costs.

[0112] In some embodiments provided by the present invention, the position detection device 11 may be a displacement sensor. Optionally, the displacement sensor may detect the displacement of the drive end 302 of the telescopic component 3. For example, the displacement sensor may be disposed inside the mounting cylinder 13 and detect the displacement of the nut 305 or piston rod of the drive component.

[0113] Of course, the position detection device 11 is not limited to being a displacement sensor. For example, in other embodiments provided by the present invention, the position detection device 11 can be an encoder, which can be connected to the rotor of the motor 303, so that the control device 9 can calculate the displacement of the nut 305 by the amount of rotation of the rotor and the pitch of the lead screw 304.

[0114] This invention also provides a method for unblocking a gas-cooled reactor fuel loading and unloading system. Specifically, it refers to a method for unblocking a gas-cooled reactor fuel loading and unloading system. It is understood that the unblocking method can be implemented based on the aforementioned gas-cooled reactor fuel loading and unloading system. The main implementer of the unblocking method can be the control device 9.

[0115] Specifically, the methods for clearing blockages include:

[0116] Obtain a presence signal, which indicates the duration of the presence of the spherical element 12 within the core return ball drop tube section 1.

[0117] Specifically, the presence signal can be detected by the presence detection device 8. For example, the presence detection device 8 includes at least one of the radiation detection device 801 and the spherical element 12. The specific detection principle can be referred to the above discussion.

[0118] When the time that the spherical element 12 is present in the core return ball drop tube section 1 exceeds the preset time, the drive end 302 of the control telescopic component 3 extends into the core return ball drop tube section 1 to drive the spherical element 12.

[0119] Specifically, the presence duration of the spherical element 12 in the core return ball drop tube section 1 is monitored by acquiring the presence signal. Once the preset duration is exceeded, the drive end 302 of the telescopic component 3 is promptly controlled to extend into the core return ball drop tube section 1 to drive the spherical element 12. This can quickly respond to possible blockages in the core return ball drop tube section 1 and avoid more serious blockages or disruptions to the normal operation of the high-temperature gas-cooled reactor caused by the prolonged presence of the spherical element 12.

[0120] This invention also provides a high-temperature gas-cooled reactor.

[0121] Specifically, high-temperature gas-cooled reactors include the high-temperature gas-cooled reactor fuel loading and unloading system described above or use the unblocking methods described above.

[0122] High-temperature gas-cooled reactors include high-temperature gas-cooled reactor fuel loading and unloading systems or use the above-mentioned unblocking methods, and thus have corresponding advantages, so they will not be elaborated further.

[0123] Although embodiments of the invention have been described in conjunction with the accompanying drawings, those skilled in the art can make various modifications and variations without departing from the spirit and scope of the invention, and such modifications and variations all fall within the scope defined by the appended claims.

Claims

1. A fuel loading and unloading system for a high-temperature gas-cooled reactor, characterized in that, include: The core return ball drop tube section (1) is connected to the core (2) and is used to transport spherical elements (12). The telescopic assembly (3) is located at one end of the core return ball drop tube section (1) away from the core (2). The telescopic assembly (3) includes a fixed end (301) and a drive end (302) that can extend and retract relative to the fixed end (301). The fixed end (301) is fixedly arranged, and the drive end (302) faces the core return ball drop tube section (1). The telescopic path of the drive end (302) is arranged along the axial direction of the core return ball drop tube section (1). The drive end (302) can enter and exit the core return ball drop tube section (1) and drive the spherical element (12).

2. The high-temperature gas-cooled reactor fuel loading and unloading system according to claim 1, characterized in that, The high-temperature gas-cooled reactor fuel loading and unloading system also includes a lift section (4), which is connected to the core return ball drop section (1) and the feeding device respectively. The included angle between the core return ball drop section (1) and the lift section (4) is an acute angle.

3. The high-temperature gas-cooled reactor fuel loading and unloading system according to claim 2, characterized in that, The high-temperature gas-cooled reactor fuel loading and unloading system also includes a first arc-shaped pipe section (5), which connects the lifting pipe section (4) and the core return ball dropping pipe section (1). The pipe wall of the first arc-shaped pipe section (5) is provided with a through-hole, which is opposite to the pipe opening of the core return ball dropping pipe section (1) and can be passed through by the drive end (302). And / or, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a transition pipe section (6) and a second arc-shaped pipe section (7), the second arc-shaped pipe section (7) connecting the transition pipe section (6) and the core return ball drop pipe section (1), the transition pipe section (6) being connected to the reactor core (2), and the included angle between the transition pipe section (6) and the core return ball drop pipe section (1) being an obtuse angle.

4. The high-temperature gas-cooled reactor fuel loading and unloading system according to claim 1, characterized in that, The high-temperature gas-cooled reactor fuel loading and unloading system also includes: The presence detection device (8) is used to send a presence signal when a spherical element (12) is present in the core return ball drop tube section (1); The control device (9) is electrically connected to the presence detection device (8) and the telescopic component (3) respectively. When the control device (9) determines that the duration of the presence signal exceeds the preset duration, it controls the drive end (302) to extend into the core return ball drop tube section (1).

5. The high-temperature gas-cooled reactor fuel loading and unloading system according to claim 4, characterized in that, The presence detection device (8) includes a radiation detection device (801), which is used to detect the amount of radiation in the core return ball drop tube section (1). When the control device (9) determines that the amount of radiation exceeds the radiation threshold and the duration exceeds the preset duration, it controls the drive end (302) to extend into the core return ball drop tube section (1). And / or, the presence detection device (8) includes a ball counter (802) for detecting the number of spherical elements (12) discharged from the core return ball drop tube section (1), and the control device (9) controls the drive end (302) to extend into the core return ball drop tube section (1) when it is determined that the number of spherical elements (12) has not increased and the duration exceeds a preset duration.

6. The high-temperature gas-cooled reactor fuel loading and unloading system according to any one of claims 1-5, characterized in that, The high-temperature gas-cooled reactor fuel loading and unloading system also includes a force measuring device (10) and a control device (9). The force measuring device (10) is disposed on the telescopic component (3) and is used to detect the driving force of the telescopic component (3). The control device (9) is electrically connected to the force measuring device (10) and the telescopic component respectively, and is used to control the extension speed of the telescopic component to decrease when the driving force is determined to be greater than or equal to the driving force threshold.

7. The high-temperature gas-cooled reactor fuel loading and unloading system according to any one of claims 1-5, characterized in that, The high-temperature gas-cooled reactor fuel loading and unloading system also includes a position detection device (11) and a control device (9). The position detection device (11) is disposed on the telescopic component (3) and is used to detect the elongation of the telescopic component (3). The control device (9) is electrically connected to the position detection device (11) and the telescopic component (3) respectively, and is used to control the telescopic component to stop elongating when the elongation is determined to be greater than or equal to the elongation threshold.

8. The high-temperature gas-cooled reactor fuel loading and unloading system according to any one of claims 1-5, characterized in that, The telescopic assembly (3) includes a motor (303), a lead screw (304), a nut (305), a drive rod (306), and a guide structure. The motor (303) is fixedly installed. The lead screw (304) is connected to the output shaft of the motor (303). The nut (305) is threadedly connected to the lead screw (304). The drive rod (306) is connected to the nut (305) and can enter and exit the core return ball drop tube section (1). The guide structure is fixedly installed and guides the nut (305) along the axial direction of the core return ball drop tube section (1). Alternatively, the telescopic assembly (3) may include a cylinder or a hydraulic cylinder.

9. A method for unblocking blockages, characterized in that, Based on the high-temperature gas-cooled reactor fuel loading and unloading system as described in any one of claims 1-8, including: Obtain an presence signal, which is used to indicate the duration of the presence of the spherical element (12) in the core return ball drop tube section (1); When the time that the spherical element (12) exists in the core return ball drop tube section (1) exceeds the preset time, the drive end (302) of the control telescopic component (3) extends into the core return ball drop tube section (1) to drive the spherical element (12).

10. A high-temperature gas-cooled reactor, characterized in that, This includes the high-temperature gas-cooled reactor fuel loading and unloading system as described in any one of claims 1-8, or the unblocking method as described in claim 9.

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