High-temperature gas cooled reactor fuel loading and unloading system, dredging method and high-temperature gas cooled reactor

Abstract

The invention 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 reactor core falling ball returning pipe section, and the reactor core falling ball returning pipe section conveys circulating fuel elements back to a reactor core. The blockage dredging device is installed on a reactor core falling ball returning pipe section and comprises a telescopic assembly, the telescopic assembly is arranged at the end, away from a reactor core, of the reactor core falling ball returning pipe section and comprises a fixed end and a driving end capable of stretching out and drawing back relative to the fixed end, the fixed end is fixedly arranged, and the driving end faces the reactor core falling ball returning pipe section. The telescopic path of the driving end is arranged in the axial direction of the reactor core falling ball pipe section, and the driving end can enter and exit from the reactor core falling ball pipe section and drive the spherical element. The blocked spherical element is driven through the telescopic assembly, compared with a traditional pneumatic dredging mode, the blocked spherical element can be treated more directly and effectively, the dredging efficiency is greatly improved, dredging time is shortened, and the reliability is also remarkably improved.

Description

Technical Field

[0001] The present invention relates to the technical field of nuclear reactors, and in particular to a high-temperature gas-cooled reactor fuel loading and unloading system, a dredging method and a high-temperature gas-cooled reactor. Background Art

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

[0003] The fuel loading and unloading system is a key system. It is used to reload the spherical elements discharged from the core that have not yet reached the final burnup depth into the core through pneumatic conveying, thereby realizing fuel recycling, or to receive spherical elements from the new fuel supply system and replenish them to the core on a regular and quantitative basis to ensure the continuous and stable operation of the reactor.

[0004] During actual operation, spherical fuel elements are prone to becoming stuck at the core feed point. Currently, the solution to this problem relies primarily on pneumatic suction, which disturbs the spherical element at the stuck location and then clears it using the fuel element's own gravity or the purge effect of high-pressure helium. 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 dredging methods in the related art, which have poor dredging efficiency, long time consumption and poor reliability.

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

[0007] a return-to-core ball drop tube section, the return-to-core ball drop tube section being connected to the core and used for transporting spherical elements;

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

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

[0010] In an optional embodiment, the high-temperature gas-cooled reactor fuel loading and unloading system further includes a first arc-shaped pipe section, the first arc-shaped pipe section connecting the lifting pipe section and the return-to-core ball drop pipe section, a through-hole being provided on a pipe wall of the first arc-shaped pipe section, the through-hole being opposite to the pipe opening of the return-to-core ball drop pipe section and allowing the driving end to pass through;

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

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

[0013] a presence detection device configured to send a presence signal when a spherical element is present in the return-to-core ball drop tube section;

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

[0015] In an optional embodiment, the presence detection device includes a radiation detection device, which is used to detect the radiation amount in the return-to-core ball drop tube section. When the control device determines that the radiation amount exceeds a radiation threshold and the duration exceeds a preset time, the drive end is controlled to extend into the return-to-core ball drop tube section.

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

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

[0018] In which, the force measuring device is arranged 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 an optional embodiment, the high temperature gas-cooled reactor fuel loading and unloading system further includes a position detection device and a control device;

[0020] In which, the position detection device is arranged 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 extending when it is determined that the elongation is greater than or equal to the elongation threshold.

[0021] In an optional embodiment, the telescopic assembly includes a motor, a lead screw, a nut, a drive rod and a guide structure, wherein the motor is fixed, 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 return core ball drop tube section, and the guide structure is fixed and guides the nut along the axial direction of the return core ball drop tube section;

[0022] Alternatively, the telescopic assembly includes a pneumatic cylinder or an oil cylinder.

[0023] In a second aspect, the present invention further provides a dredging method, comprising:

[0024] Acquiring a presence signal, wherein the presence signal is used to indicate a duration of time the spherical element exists in the back-to-core ball drop tube section;

[0025] When the time period for the spherical element to exist in the return-to-core ball drop tube section exceeds a preset time period, the driving end of the telescopic assembly is controlled to extend into the return-to-core ball drop tube section to drive the spherical element.

[0026] In a third aspect, the present invention further provides a high-temperature gas-cooled reactor, comprising the high-temperature gas-cooled reactor fuel loading and unloading system as described above, or using the dredging method as described above.

[0027] The high-temperature gas-cooled reactor fuel loading and unloading system provided by this invention uses a telescopic assembly to actuate a stuck spherical element. Compared to traditional methods that rely on pneumatic unblocking, this system can more directly and effectively address stuck spherical elements, significantly improving unblocking efficiency, reducing unblocking time, and significantly enhancing reliability. For example, it not only resolves blockages caused by wear debris accumulation, but also overcomes mechanical jams caused by machining errors, thermal deformation, and other factors, providing greater adaptability.

[0028] The unclogging method provided by this invention uses a telescopic assembly to actuate a stuck spherical element. Compared to traditional pneumatic unclogging methods, this method can more directly and effectively address a stuck spherical element, significantly improving unclogging efficiency, reducing unclogging time, and significantly enhancing reliability. For example, it not only resolves blockages caused by wear debris accumulation, but also overcomes mechanical jams caused by machining errors, thermal deformation, and other factors, offering greater adaptability.

[0029] The high-temperature gas-cooled reactor provided by the present invention comprises the high-temperature gas-cooled reactor fuel loading and unloading system provided by the present invention or uses the dredging method provided by the present invention, and therefore has corresponding advantages. BRIEF DESCRIPTION OF THE DRAWINGS

[0030] In order to more clearly illustrate the specific embodiments of the present invention or the technical solutions in the prior art, the following briefly introduces the drawings required for use in the specific embodiments or the description of the prior art. Obviously, the drawings described below are some embodiments of the present invention. For ordinary technicians in this field, other drawings can be obtained based on these drawings without paying any creative work.

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

[0032] Figure 2 A schematic diagram of the structure of the telescopic assembly provided in an embodiment of the present invention when dredging the ball drop tube section back into the core;

[0033] Figure 3 A schematic structural diagram of a telescopic assembly provided in an embodiment of the present invention;

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

[0035] Description of reference numerals:

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

[0037] To make the purpose, technical solutions, and advantages of the embodiments of the present invention more clear, the technical solutions in the embodiments of the present invention will be clearly and completely described below in conjunction with the accompanying drawings in the embodiments of the present invention. Obviously, the described embodiments are part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without making creative efforts shall fall within the scope of protection of the present invention.

[0038] The following combination Figures 1 to 4, describing the high temperature gas-cooled reactor fuel loading and unloading system provided in an embodiment 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 return-to-core ball drop tube section 1 is connected to the core 2 and is used to transport spherical elements 12. Optionally, the return-to-core ball drop tube section 1 is tilted, and the height of the return-to-core ball drop tube section 1 near the core 2 is lower than the height of the return-to-core ball drop tube section 1 near the feeding device, so that the spherical elements 12 can move along the return-to-core ball drop tube section 1 under the action of gravity, reducing the pneumatic load.

[0041] The telescopic assembly 3 is located at the end of the return-to-core ball drop tube section 1, away from the core 2. The telescopic assembly 3 includes a fixed end 301 and a driving end 302. The driving end 302 is retractable relative to the fixed end 301. The fixed end 301 is fixed, for example, connected to and fixed to the return-to-core ball drop tube section 1. This allows the telescopic assembly 3 to be integrated into the pipeline, improving the structural compactness of the fuel loading and unloading system.

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

[0043] In this embodiment, when the high-temperature gas-cooled reactor fuel loading and unloading system is operating normally, the spherical element 12 can smoothly pass through the return-to-core ball drop tube section 1 and enter the reactor core 2 under the action of pneumatic force and gravity. However, due to the wear debris generated by the spherical element 12 during operation, the wear debris accumulates in the return-to-core ball drop tube section 1, which can easily cause the spherical element 12 to become stuck. In addition, machining errors or thermal expansion and contraction may also cause the spherical element 12 to become stuck.

[0044] When the spherical element 12 is stuck in the return-to-core ball drop tube section 1, the driving end 302 of the telescopic assembly 3 can be made to enter the return-to-core ball drop tube section 1. Since the thrust direction of the driving end 302 is consistent with the axial direction of the return-to-core ball drop tube section 1, the spherical element 12 can be driven to move toward the core 2, thereby clearing the stuck spherical element 12 in the return-to-core ball drop tube section 1.

[0045] When there is no jamming problem in the return-to-core ball drop tube section 1, the driving end 302 of the telescopic assembly 3 can be discharged from the return-to-core ball drop tube section 1 to prevent the driving end 302 from affecting the normal operation of the spherical element 12 in the return-to-core ball drop tube section 1.

[0046] Compared to traditional pneumatic unclogging methods, this arrangement can more directly and effectively address blocked spherical elements 12, significantly improving unclogging efficiency, reducing unclogging time, and significantly enhancing reliability. For example, it not only resolves blockages caused by wear debris accumulation, but also overcomes mechanical jams caused by machining errors, thermal deformation, and other factors, providing greater adaptability.

[0047] When there is no jamming problem in the return-to-core ball drop tube section 1, the driving end 302 of the telescopic assembly 3 can be discharged from the return-to-core ball drop tube section 1, avoiding interference of the driving end 302 with the normal operation of the spherical element 12 in the return-to-core 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 lifting pipe section 4 is connected to the core ball drop pipe section 1 and the feeding device respectively, and the angle between the core ball drop pipe section 1 and the lifting pipe section 4 is an acute angle. Figure 1 As shown, the lifting pipe section 4 is arranged in the vertical direction, the height of the return core ball drop pipe section 1 near the lifting pipe section 4 is higher than the height of the position near the core 2, and the return core ball drop pipe section 1 is connected to the top of the core 2.

[0050] In this embodiment, the lifting tube section 4 raises the spherical elements 12 to a high position. The return-to-core ball drop tube section 1 utilizes the gravitational potential energy generated by the inclination angle and height difference to convert it into kinetic energy, allowing the elements to slide quickly into the core 2, reducing the reliance on high-pressure helium. The return-to-core ball drop tube section 1 connects to the top of the core 2, evenly distributing the spherical elements 12 from top to bottom to avoid potential localized 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 discharge pipe section 14 is connected to the lower end of the core 2 and is used to discharge the spherical elements 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 special channel for the discharge of the spherical elements 12 inside the core, so that the spherical elements 12 can be smoothly discharged from the core 2 according to a predetermined path and direction, avoiding the disorderly flow or blockage of the spherical elements 12 in the core 2, ensuring the smooth progress of the spherical element 12 unloading process, and maintaining the normal renewal of the fuel in the core 2 and 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 also includes a first arc-shaped pipe section 5, which connects the lifting pipe section 4 and the return-to-core ball drop pipe section 1. A through opening is provided on the pipe wall of the first arc-shaped pipe section 5, which is opposite to the pipe opening of the return-to-core ball drop pipe section 1 and can be passed through by the driving end 302.

[0055] In this embodiment, the first arc-shaped pipe section 5 transitions between the lifting pipe section 4 and the return-to-core ball-dropping pipe section 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 pipe wall, and reducing the generation of wear debris.

[0056] In addition, the through-opening on the first arc-shaped tube segment 5 is opposite to the tube opening of the return-to-core ball-dropping tube segment 1, ensuring that the telescopic path of the driving end 302 is coaxially aligned with the return-to-core ball-dropping tube segment 1, and the thrust direction is consistent with the movement direction of the spherical element 12, avoiding lateral force component causing element displacement or secondary jamming.

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

[0058] The motor 303 is fixedly arranged, for example, the motor 303 is connected to at least one of the first arc-shaped pipe segment 5 and the return-to-core ball-dropping pipe segment 1 .

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

[0060] The guide structure is fixedly mounted and guides the nut 305 axially along the return-to-core ball drop tube segment 1. For example, the guide structure is connected to at least one of the first curved tube segment 5 and the return-to-core ball drop tube segment 1. Alternatively, the guide structure is configured as a guide block, and the nut 305 is provided with a guide groove that slidably engages with the guide block. Alternatively, the guide structure is configured as a guide groove, and the nut 305 is provided with a guide block that slidably engages with the guide groove.

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

[0062] Furthermore, the motor 303 and the guide structure are respectively connected to at least one of the first curved tube segment 5 and the return-to-core ball drop tube segment 1, tightly integrating the telescopic assembly 3 with the fuel loading and unloading system piping, enhancing the overall structural stability. When the drive rod 306 pushes the spherical element 12, it effectively withstands the reaction force, ensuring the stable operation of the telescopic assembly 3 and reducing the impact of vibration or shaking on the system.

[0063] Furthermore, the guide structure guides the nut 305 axially along the return-to-core ball drop tube 1, ensuring the straightness and accuracy of the movement of the nut 305 and the drive rod 306. This helps prevent the drive rod 306 from deflecting or getting stuck during extension and retraction, ensuring that it can smoothly enter and exit the return-to-core ball drop tube 1 and accurately engage a stuck spherical element 12, thereby improving the reliability and stability of the system.

[0064] Optionally, the high temperature gas-cooled reactor fuel loading and unloading system further includes a mounting barrel 13 .

[0065] Specifically, the mounting tube 13 is disposed at the end of the return-to-core ball drop tube section 1, away from the core 2, and extends axially along the return-to-core ball drop tube section 1. One end of the mounting tube 13 is connected to the first curved tube section 5, and the through-opening of the first curved tube section 5 is disposed opposite the mounting tube 13. Optionally, the mounting tube 13 and the first curved tube section 5 are welded.

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

[0067] During the dredging process, the driving rod 306 extends from the installation tube 13 into the return-to-core ball drop tube section 1 . After the dredging is completed, the driving rod 306 retracts into the installation tube 13 .

[0068] In this embodiment, the ends of the mounting tube 13 are connected to the first arc-shaped pipe segment 5 and the motor 303, respectively, forming a closed chamber within the mounting tube 13. This prevents dust and impurities from the external environment from entering the mounting tube 13, thereby preventing damage to precision components such as the lead screw 304. Furthermore, it prevents gas leakage within the pipeline, maintains pressure balance within the system, ensures reliable 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] In addition, the mounting barrel 13 encloses the lead screw 304 and other components, providing good protection for them. The internal components are not easily affected by external environmental factors such as wear and corrosion, which extends the service life of these components and reduces maintenance and replacement costs.

[0070] Optionally, the driving 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 sleeved on the outside of the screw 304, and one end of the rod body 3061 is connected to the nut 305, and the other end of the rod body 3061 is connected to the push plate 3062, and the push plate 3062 is used to resist the spherical element 12.

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

[0072] Furthermore, the space occupied by high-temperature gas-cooled reactor fuel loading and unloading systems is typically quite compact, making efficient use of axial space crucial. Rod body 3061 is sheathed around lead screw 304, allowing the two to share a certain amount of axial space, thus avoiding the increased axial dimensions that would result from their side-by-side arrangement. This design effectively reduces the axial space occupied by telescopic assembly 3, facilitating a compact layout of the entire fuel loading and unloading system and better adapting it to limited installation space.

[0073] Optionally, the push plate 3062 is configured as an arc-shaped plate that is recessed toward the interior of the rod body 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 curved plate better matches the outer surface of the spherical element 12. When the push plate 3062 pushes the spherical element 12, this fit increases the contact area between the two, more evenly applying the thrust to the spherical element 12, avoiding damage to the surface of the spherical element 12 due to localized stress concentration, and ensuring the integrity and performance of the spherical element 12.

[0075] The improved fit makes it less likely that the spherical element 12 will slip or deflect when the push plate 3062 pushes it. Within the core drop tube 1, especially when unblocking a blockage, the spherical element 12 remains relatively fixed, and the curved push plate 3062 effectively grips the spherical element 12, ensuring its movement in the intended direction, improving push accuracy and efficiency.

[0076] Because the arc-shaped push plate 3062 more rationally contacts and pushes the spherical element 12, it can more effectively transmit power when unclogging a spherical element 12 stuck in the core ball drop tube 1, pushing the spherical element 12 out of the jam. In other words, the arc-shaped push plate 3062 achieves a better unclogging effect with less force, improving the reliability and operational efficiency of the entire fuel loading and unloading system.

[0077] In actual operation, the spherical element 12 in the core drop tube section 1 may be stuck in a complex situation. The curved push plate 3062 can better adapt to blockages at different angles and locations. By adjusting the contact point and angle with the spherical element 12, it can more flexibly handle various blockage scenarios, further improving the success rate of clearing the blockage.

[0078] Of course, the telescopic assembly 3 is not limited to the aforementioned form of the lead screw 304. For example, in an unillustrated embodiment of the present invention, the telescopic assembly 3 comprises a pneumatic or hydraulic cylinder. Optionally, the cylinder body of the pneumatic or hydraulic cylinder is connected to the end of the mounting barrel 13 remote from the return-to-core ball drop tube 1. For example, the cylinder body is disposed externally to the mounting barrel 13, and the piston rod of the pneumatic or hydraulic cylinder extends into the mounting barrel 13. Alternatively, it can be understood that the fixed end 301 of the telescopic assembly 3 is disposed externally to the mounting barrel 13 and connected to the end of the mounting barrel 13 remote from the return-to-core ball drop tube 1, while the driving end 302 of the telescopic assembly 3 extends into the mounting barrel 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 curved pipe section 7 connects the transition pipe section 6 and the return-to-core 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 return-to-core ball drop pipe section 1 is obtuse. For example, the transition pipe section 6 is arranged parallel to the riser section 4 and is connected to the top of the core 2.

[0081] In this embodiment, the obtuse-angle connection between the return-to-core ball drop section 1 and the transition section 6 reduces kinetic energy loss of the spherical element 12, maintaining its transit speed within a reasonable range. The first curved section 5 (connecting the riser section 4 and the return-to-core ball drop section 1) and the second curved section 7 (connecting the return-to-core ball drop section 1 and the transition section 6) cooperate to form a continuous and smooth turn, thereby reducing kinetic energy loss during the operation of the spherical element 12 and ensuring smoother operation.

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

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

[0084] The control device 9 is electrically connected to the presence detection device 8 and the telescopic assembly 3. For example, the control device 9 is electrically connected to the motor 303 and the pneumatic or hydraulic cylinder, and can control the rotation of the motor 303 and the extension and retraction of the pneumatic or 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 presence signal exceeds a preset duration, it controls the driving end 302 to extend into the return-to-core ball drop tube section 1, thereby driving the spherical element 12 within the return-to-core ball drop tube section 1 toward the core 2. It will be appreciated that the preset duration can be flexibly adjusted based on actual operating conditions and system requirements to meet the requirements for blockage detection under different operating conditions.

[0086] In this embodiment, the presence detection device 8 monitors the presence of the spherical element 12 in the return-to-core ball drop tube 1 in real time and transmits a presence signal when the presence of the spherical element 12 is detected. The control device 9 determines whether a blockage has occurred based on the duration of the presence signal. If the duration of the presence signal exceeds a preset duration, it indicates that the spherical element 12 has remained in the return-to-core ball drop tube 1 for too long and is likely to have become blocked. In this case, the control device 9 controls the driving end 302 to extend into the return-to-core ball drop tube 1 to clear the blockage.

[0087] This automatic detection and response mechanism can promptly detect jamming problems and take corresponding measures, greatly improving the system's efficiency in handling jamming failures, reducing manual intervention, and lowering the operator's workload and risk of misjudgment.

[0088] Furthermore, by promptly detecting and addressing the jamming issue, the impact of the jamming of the spherical element 12 on the normal operation of the fuel loading and unloading system is avoided. This ensures that the spherical element 12 can be continuously and stably delivered to the core 2, maintaining the normal fuel supply of the reactor. This improves the stability and reliability of the entire high-temperature gas-cooled reactor system, reduces the occurrence of system shutdowns or abnormal operations caused by jamming, and improves the power generation efficiency and safety of the reactor.

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

[0090] The radiation detection device 801 is used to detect the radiation amount in the ball drop tube section 1 returning to the core, 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 device 9 controls the driving end 302 to extend into the back-core ball drop tube section 1.

[0092] In this embodiment, spherical elements 12, serving as reactor fuel assemblies, typically possess high radioactivity. Radiation detection device 801 accurately determines the presence of spherical elements 12 by detecting the amount of radiation returning to the core ball drop tube 1. Radiation detection is unaffected by factors such as the surface condition, color, and material of spherical elements 12, resulting in more reliable detection results and effectively preventing false positives and missed detections. This accurately provides a signal indicating the presence of spherical elements 12 to control device 9.

[0093] Control device 9 determines a jam based on whether the radiation level exceeds a threshold and persists for longer than a preset duration. This dual-detection mechanism is more scientific and rational. Exceeding the threshold indicates the presence of spherical element 12, while persisting for longer than the preset duration indicates that spherical element 12 has been in that position for too long, likely indicating a jam. This approach allows for more accurate identification of jams, avoiding misoperation caused by brief radiation fluctuations or other anomalies, and improving the accuracy and reliability of the system's jam fault detection.

[0094] Radiation detection device 801, based on radiation signals, is immune to interference from factors such as high temperature and high pressure, and exhibits strong environmental adaptability. Even when the environment within the reactor core 2 or around the pipeline changes, it can still accurately detect the radiation level of the spherical element 12, ensuring the system's normal operation under various operating 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 passing counter 802 .

[0097] The ball passing counter 802 is used to detect the number of spherical elements 12 discharged from the ball dropping tube section 1 back into the core, and the ball passing counter 802 is electrically connected to the control device 9 .

[0098] When the control device 9 determines that the number of the spherical elements 12 has not increased and the duration exceeds a preset time, the control device 9 controls the driving end 302 to extend into the back-core ball drop tube section 1.

[0099] In this embodiment, optionally, when the ball-passing counter 802 detects the discharge of the spherical element 12, it transmits a high-level signal to the control device 9; when the ball-passing 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 the preset duration, it controls the telescopic component 3 to operate.

[0100] By detecting the number of spherical elements 12 discharged from the return-to-core ball drop tube 1, the ball-passing counter 802 directly and intuitively displays the flow of spherical elements 12 during fuel loading and unloading. Based on the number of spherical elements 12 provided by the ball-passing counter 802, the control device 9 can clearly determine whether the spherical elements 12 are being discharged normally. If the number of spherical elements 12 does not increase and persists for a predetermined period, it is easily inferred that the spherical elements 12 are stuck or otherwise abnormal within the return-to-core ball drop tube 1, providing a clear basis for subsequent handling.

[0101] Taking quantity as the detection indicator, it is not affected by the radiation intensity fluctuation, appearance change or environmental factors in the pipe section (such as temperature, humidity, etc.) of the spherical element 12. As long as the spherical element 12 passes through the core drop pipe section 1 normally, the ball passing counter 802 can accurately record it, which increases the dimension of judgment and reduces the possibility of misjudgment caused by interference from other factors, thereby improving the accuracy of the detection of the existence status of the spherical element 12 in the pipe section.

[0102] The number of spherical elements 12 recorded by ball counter 802 can be easily integrated into the monitoring platform of the entire high-temperature gas-cooled reactor fuel loading and unloading system. This monitoring platform provides operators with real-time information on the progress and status of fuel loading and unloading. If an abnormal number of spherical elements 12 is detected, the system can promptly issue an alarm and take appropriate measures. This helps to achieve automated monitoring and management of the entire loading and unloading process, improving the system's operational efficiency and reliability.

[0103] Optionally, the ball passing counter 802 may be a photoelectric ball passing counter 802 , an electromagnetic induction ball passing counter 802 , or a capacitive ball passing 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. Alternatively, the force measuring device 10 may be a pressure sensor, for example, disposed between the nut 305 and the drive rod 306. For a pneumatic or oil cylinder, the pressure sensor may 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 it is determined that the driving force is greater than or equal to the driving force threshold.

[0107] In this embodiment, a force-measuring device 10, such as a pressure sensor, is provided on the telescopic assembly 3 to accurately monitor the driving force of the telescopic assembly 3 in real time. When the driving force is greater than or equal to a driving force threshold, the control device 9 promptly controls the extension speed of the telescopic assembly to decrease, effectively preventing the telescopic assembly 3 from causing damage to the spherical element 12, such as excessive squeezing or collision, 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] Among them, the position detection device 11 is arranged 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 extending when it is determined that the elongation is greater than or equal to the elongation threshold.

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

[0111] In addition, preventing the telescopic component 3 from over-extension can protect itself and other components connected to it, such as the drive rod 306, the nut 305, etc., and prevent these components from being deformed or 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 can be a displacement sensor. Optionally, the displacement sensor can detect the displacement of the driving end 302 of the telescopic assembly 3. For example, the displacement sensor is arranged in the mounting tube 13 and detects the displacement of the nut 305 or the piston rod of the driving assembly.

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

[0114] The present invention also provides a method for dredging a fuel loading and unloading system for a warm gas-cooled reactor. It is understood that the method can be implemented based on the above-described high-temperature gas-cooled reactor fuel loading and unloading system. The method can be implemented by the control device 9.

[0115] Specifically, the dredging methods include:

[0116] An existence signal is acquired, where the existence signal is used to indicate the duration of the existence of the spherical element 12 in the back-to-core ball drop tube segment 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 duration of the spherical element 12 existing in the return-to-core ball drop tube section 1 exceeds a preset duration, the driving end 302 of the telescopic assembly 3 is controlled to extend into the return-to-core ball drop tube section 1 to drive the spherical element 12 .

[0119] Specifically, the existence time of the spherical element 12 in the return-to-core ball drop tube section 1 is monitored by acquiring the existence signal. Once the preset time is exceeded, the driving end 302 of the telescopic assembly 3 is promptly controlled to extend into the return-to-core ball drop tube section 1 to drive the spherical element 12. This can quickly respond to possible blockages in the return-to-core ball drop tube section 1, and avoid more serious blockages or impacts on the normal operation of the high-temperature gas-cooled reactor due to the long-term retention of the spherical element 12.

[0120] A high-temperature gas-cooled reactor is also provided in an embodiment of the present invention.

[0121] Specifically, the high-temperature gas-cooled reactor includes the above-mentioned high-temperature gas-cooled reactor fuel loading and unloading system or uses the above-mentioned dredging method.

[0122] The high-temperature gas-cooled reactor includes a high-temperature gas-cooled reactor fuel loading and unloading system or uses the above-mentioned unblocking method, and also has corresponding advantages, so it will not be described in detail.

[0123] Although the embodiments of the present invention have been described with reference to the accompanying drawings, those skilled in the art may make various modifications and variations without departing from the spirit and scope of the present invention. Such modifications and variations are all within the scope defined by the appended claims.

Claims

1. A high temperature gas-cooled reactor fuel loading and unloading system, characterized in that: include: a return-to-core ball-dropping pipe section (1), the return-to-core ball-dropping pipe section (1) being connected to the core (2) and used for conveying the spherical elements (12); A telescopic assembly (3) is provided at one end of the return-core ball drop tube section (1) away from the core (2), the telescopic assembly (3) comprising a fixed end (301) and a driving end (302) that can be telescoped relative to the fixed end (301), the fixed end (301) being fixedly arranged, the driving end (302) facing the return-core ball drop tube section (1), and a telescopic path of the driving end (302) being arranged along the axial direction of the return-core ball drop tube section (1), the driving end (302) being able to enter and exit the return-core 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 further comprises a lifting pipe section (4), wherein the lifting pipe section (4) is respectively connected to the return-to-core ball drop pipe section (1) and the feeding device, and the angle between the return-to-core ball drop pipe section (1) and the lifting pipe 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 further comprises a first arc-shaped pipe section (5), the first arc-shaped pipe section (5) connecting the lifting pipe section (4) and the return-to-core ball-dropping pipe section (1), a through-hole being provided on the pipe wall of the first arc-shaped pipe section (5), the through-hole being opposite to the pipe opening of the return-to-core ball-dropping pipe section (1) and being capable of allowing the driving end (302) to pass through; And / or, the high-temperature gas-cooled reactor fuel loading and unloading system further comprises a transition pipe section (6) and a second arc-shaped pipe section (7), wherein the second arc-shaped pipe section (7) connects the transition pipe section (6) and the return-to-core 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 return-to-core ball drop pipe section (1) is 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 further includes: A presence detection device (8) is used to send a presence signal when a spherical element (12) exists in the return-to-core ball drop tube section (1); A control device (9) is electrically connected to the presence detection device (8) and the telescopic assembly (3) respectively. When the control device (9) determines that the duration of the presence signal exceeds a preset duration, the control device (9) controls the driving end (302) to extend into the return core 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) comprises a radiation detection device (801), the radiation detection device (801) being used to detect the radiation amount in the return-to-core ball drop tube section (1); the control device (9) controls the driving end (302) to extend into the return-to-core ball drop tube section (1) when it is determined that the radiation amount exceeds a radiation threshold value and the duration exceeds a preset duration; And / or, the presence detection device (8) includes a ball passing counter (802), and the ball passing counter (802) is used to detect the number of spherical elements (12) discharged from the return core ball drop tube section (1). When the control device (9) determines that the number of spherical elements (12) has not increased and the duration exceeds a preset time, it controls the driving end (302) to extend into the return core ball drop tube section (1).

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

7. The high temperature gas-cooled reactor fuel loading and unloading system according to any one of claims 1 to 5, characterized in that: The high temperature gas-cooled reactor fuel loading and unloading system further includes a position detection device (11) and a control device (9); The position detection device (11) is provided on the telescopic assembly (3) and is used to detect the extension of the telescopic assembly (3); the control device (9) is electrically connected to the position detection device (11) and the telescopic assembly (3), respectively, and is used to control the telescopic assembly to stop extending when it is determined that the extension is greater than or equal to an extension threshold.

8. The high temperature gas-cooled reactor fuel loading and unloading system according to any one of claims 1 to 5, characterized in that: The telescopic assembly (3) comprises a motor (303), a lead screw (304), a nut (305), a driving rod (306) and a guide structure, wherein the motor (303) is fixedly arranged, 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 driving rod (306) is connected to the nut (305) and can enter and exit the return core ball drop tube section (1), and the guide structure is fixedly arranged and guides the nut (305) along the axial direction of the return core ball drop tube section (1); Alternatively, the telescopic assembly (3) comprises an air cylinder or an oil cylinder.

9. A dredging method, characterized in that: include: Acquiring a presence signal, wherein the presence signal is used to indicate the duration of the presence of the spherical element (12) in the back-core ball drop tube section (1); When the duration of the existence of the spherical element (12) in the return core ball drop tube section (1) exceeds a preset duration, the driving end (302) of the telescopic assembly (3) is controlled to extend into the return core ball drop tube section (1) to drive the spherical element (12).

10. A high temperature gas-cooled reactor, characterized in that: It comprises the high temperature gas-cooled reactor fuel loading and unloading system according to any one of claims 1 to 8, or uses the dredging method according to claim 9.

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