CN111028968A - Reactor loading and unloading system and method thereof - Google Patents
Reactor loading and unloading system and method thereof Download PDFInfo
- Publication number
- CN111028968A CN111028968A CN201911402973.7A CN201911402973A CN111028968A CN 111028968 A CN111028968 A CN 111028968A CN 201911402973 A CN201911402973 A CN 201911402973A CN 111028968 A CN111028968 A CN 111028968A
- Authority
- CN
- China
- Prior art keywords
- fuel assembly
- loading
- fixed sleeve
- ball valve
- telescopic
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 238000000034 method Methods 0.000 title claims abstract description 25
- 239000000446 fuel Substances 0.000 claims abstract description 70
- 230000007246 mechanism Effects 0.000 claims abstract description 23
- 238000007789 sealing Methods 0.000 claims description 11
- 239000000463 material Substances 0.000 claims description 7
- 230000005855 radiation Effects 0.000 claims description 4
- 230000003471 anti-radiation Effects 0.000 claims description 3
- 230000008569 process Effects 0.000 abstract description 14
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract description 8
- 238000012546 transfer Methods 0.000 abstract description 6
- 230000002285 radioactive effect Effects 0.000 abstract description 5
- 230000009471 action Effects 0.000 description 4
- 230000000712 assembly Effects 0.000 description 3
- 238000000429 assembly Methods 0.000 description 3
- 230000008901 benefit Effects 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 238000012544 monitoring process Methods 0.000 description 2
- 230000004075 alteration Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 229920002379 silicone rubber Polymers 0.000 description 1
- 239000004945 silicone rubber Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
- G21C19/105—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with grasping or spreading coupling elements
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
Abstract
本发明提供了一种反应堆用装卸料系统及其方法，涉及核工程设备技术领域，通过设置安装在装卸料机小车上的固定套筒，与提升机构连接的伸缩抓具，安装在所述固定套筒下端开口处的球阀；所述提升机构安装在所述装卸料机小车上，并带动所述伸缩抓具在所述固定套筒内上下运动；所述伸缩抓具用于燃料组件的抓取和上下移动；所述球阀用以实现所述固定套筒下端开口的打开和封闭。本发明能够实现燃料组件或乏燃料组件转移过程被密封包容，即使发生地震等外部事件造成燃料组件意外拖抓，也可以保证燃料组件不会跌落地面，仍密封于固定套筒内部，更不会造成严重的放射性释放，具有高安全性。
The invention provides a loading and unloading system for a reactor and a method thereof, and relates to the technical field of nuclear engineering equipment. The ball valve at the opening of the lower end of the sleeve; the lifting mechanism is installed on the loader trolley, and drives the telescopic grabber to move up and down in the fixed sleeve; the telescopic grabber is used for grabbing the fuel assembly Take and move up and down; the ball valve is used to realize the opening and closing of the opening at the lower end of the fixed sleeve. The invention can realize that the fuel assembly or the spent fuel assembly is sealed and contained during the transfer process. Even if the fuel assembly is accidentally dragged by an external event such as an earthquake, it can also ensure that the fuel assembly will not fall to the ground, and is still sealed inside the fixed sleeve, and will not Causes serious radioactive release with high safety.
Description
Technical Field
The invention relates to the technical field of nuclear engineering equipment, in particular to a material loading and unloading system for a reactor and a method thereof.
Background
The function of a nuclear reactor handler is to transfer new fuel assemblies and load them into the reactor core; spent fuel assemblies are received from the reactor and discharged into a spent fuel transport facility. The loading and unloading machine is generally composed of a bridge frame, a cart and a running mechanism, a trolley and a running mechanism, a lifting mechanism, a telescopic sleeve, an electric control system and the like.
When the reactor of the conventional nuclear power station is loaded and unloaded, the fuel assemblies are protected by water layers with certain thicknesses in the processes of entering and leaving the reactor core, the radioactivity of spent fuel is effectively shielded by the water layers, the risk of radioactive leakage is reduced, and the radioactive hazards possibly suffered by workers and the public are reduced. For some special nuclear reactors, the loading and unloading process of the spent fuel assembly is in an air environment, and the spent fuel assembly without water layer protection puts higher requirements on the safety and reliability of operating equipment. Therefore, the invention improves the mechanical structure of the traditional loading and unloading machine and provides a loading and unloading protection scheme with a redundant safety design.
Disclosure of Invention
The invention aims to provide a material loading and unloading system for a reactor and a method thereof, aiming at improving the safety of the fuel assembly transfer process at the present stage.
In order to achieve the purpose, the invention is realized by the following technical scheme:
a loading and unloading system for a reactor and a method thereof comprise a fixed sleeve arranged on a trolley of a loading and unloading machine, a telescopic gripping apparatus connected with a lifting mechanism, and a ball valve arranged at an opening at the lower end of the fixed sleeve;
the lifting mechanism is arranged on the trolley of the loading and unloading machine and drives the telescopic gripping apparatus to move up and down in the fixed sleeve;
the telescopic gripping apparatus is used for gripping and moving the fuel assembly up and down; the ball valve is used for opening and closing the lower end opening of the fixed sleeve.
Optionally, a camera is further provided; the camera is arranged on the fixed sleeve and used for observing the condition of the inner side of the fixed sleeve.
Optionally, the camera is a radiation-resistant camera.
Optionally, a channel for the fuel assembly to move up and down is arranged on the valve body of the ball valve; and the through hole is communicated and isolated with the hollow cylinder of the fixed sleeve by turning the ball valve.
Optionally, the upper part of the fixed sleeve is also provided with a sealing element in a positioning way; and a lifting part of the lifting mechanism penetrates through the sealing element and then is connected with the telescopic gripping apparatus.
Optionally, a safety interlock is arranged between the telescopic gripping apparatus and the ball valve at the lower end of the fixed sleeve.
Optionally, a position sensing device is arranged on the telescopic gripper.
Optionally, the operations of the mechanical parts such as the telescopic gripper, the ball valve and the anti-radiation camera are controlled by remote control.
A material loading and unloading method for a reactor comprises the following steps:
s10, adjusting the position of the trolley of the loading and unloading machine according to the coordinates of the target fuel assembly to ensure that the fixed sleeve is accurately positioned above the grabbed fuel assembly in the reactor;
s20, the lifting mechanism drives the telescopic gripping apparatus to descend above the fuel assembly, and the telescopic gripping apparatus grips the fuel assembly;
s30, the telescopic gripping apparatus drives the fuel assembly to lift upwards and move to completely enter the fixed sleeve, then the fuel assembly stops moving, and the ball valve at the lower end of the fixed sleeve is closed;
s40, the trolley of the loading and unloading machine drives the fixed sleeve to move, the telescopic gripping apparatus is in a locking state in the moving process, the ball valve is in a closing state, and the fuel assembly is in a sealed accommodating state;
s50, after the trolley of the loading and unloading machine moves to a specified position, the ball valve is opened, the telescopic gripping apparatus drives the fuel assembly to move downwards to the specified position, and the telescopic gripping apparatus releases the fuel assembly.
Compared with the prior art, the invention has the beneficial effects that:
the invention can realize that the transfer process of the fuel assembly or the spent fuel assembly is sealed and contained, even if the fuel assembly is accidentally dragged and grabbed due to external events such as earthquake and the like, the fuel assembly can be ensured not to fall down to the ground and still be sealed in the fixed sleeve, further serious radioactive release can not be caused, and the invention has high safety.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the drawings without creative efforts.
FIG. 1 is a schematic structural view of the present invention, FIG. 1;
FIG. 2 is a schematic view of a fuel assembly capture configuration of the present invention;
FIG. 3 is a schematic view of the fuel assembly moving state structure of the present invention;
FIG. 4 is a schematic view of a fuel assembly in a release state according to the present invention;
the reference numbers in the figures illustrate:
1. fixing the sleeve; 2. a telescopic gripper; 3. a ball valve; 4. a camera; 5. a loading and unloading machine trolley; 6. a seal member; 7. a fuel assembly; 8. a lifting mechanism; 9. a reactor; 10. and (4) storage equipment.
Detailed Description
In order to make the objects, technical solutions and advantages of the embodiments of the present invention clearer, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the embodiments of the present invention, and it is obvious that the described embodiments are some embodiments of the present invention, but not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
With reference to fig. 1 to 4, the present invention provides a reactor loading and unloading system and a method thereof, which aims to improve the safety of the fuel assembly transfer process at the present stage.
Specifically, with reference to fig. 1, the device comprises a fixed sleeve 1 mounted on a trolley 5 of a loading and unloading machine, a telescopic gripping apparatus 2 connected with a lifting mechanism 8, and a ball valve 3 mounted at an opening at the lower end of the fixed sleeve 1;
the lifting mechanism 8 is arranged on the loading and unloading machine trolley 5 and drives the telescopic gripping apparatus 2 to move up and down in the fixed sleeve 1;
the telescopic gripper 2 is used for gripping and moving the fuel assembly 7 up and down; the ball valve 3 is used for opening and closing the lower end opening of the fixed sleeve 1.
The invention can realize that the transfer process of the fuel assembly or the spent fuel assembly is sealed and contained, even if the fuel assembly is accidentally dragged and grabbed due to external events such as earthquake and the like, the fuel assembly can be ensured not to fall down to the ground and still be sealed in the fixed sleeve, further serious radioactive release can not be caused, and the invention has high safety.
In another embodiment, a camera 4 is also provided; the camera 4 is arranged on the fixed sleeve 1 and used for observing the condition of the inner side of the fixed sleeve 1.
Preferably, the camera 4 is arranged at the lower part of the fixed sleeve 1 and at the upper part of the ball valve 3; for observing and monitoring the entry of the gripped fuel assembly 7 into the stationary sleeve 1, and for observing and monitoring the opening and closing of the sealing of the ball valve 3.
Preferably, the camera 4 is a radiation-resistant camera; the camera 4 camera lens is wrapped up by the plumbous collimator, and the plumbous collimator restricts the camera lens field of vision, makes other direction rays shielded, improves camera 4 life under the strong radiation field.
In another embodiment, the valve body of the ball valve 3 is provided with a passage for the fuel assembly 7 to move up and down.
Preferably, the valve body of the ball valve 3 is a spherical structure with a through hole in the middle; the valve body is matched with the inner diameter of the cylinder body of the fixed sleeve in size; through the upset of ball valve 3 realize the perforation with the cavity barrel intercommunication and the wall of fixed sleeve 1, simultaneously the cavity barrel of fixed sleeve 1 provides the direction for flexible gripping apparatus 2 removes, and the structure is simpler, design benefit.
Preferably, the ball valve 3 may be a gate valve or a stop valve or other forms.
In another embodiment, the upper part of the fixed sleeve 1 is also positioned with a sealing member 6; the telescopic device of the lifting mechanism 8 penetrates through the sealing element 6 and then is connected with the telescopic gripper 2; the upper protection and limitation of the fuel assembly 7 contained in the fixed sleeve 1 is achieved by the dynamic sealing of the telescopic device and the sealing element 6.
Preferably, the seal 6 is a silicone rubber sealing gasket construction.
In another embodiment, a safety interlock is arranged between the telescopic gripper 2 and the ball valve 3 at the lower end of the fixed sleeve 1; when the ball valve 3 is in a closed state, the telescopic gripper 2 can only be in a gripping state, and the fuel assembly 7 on the telescopic gripper 2 is prevented from falling.
Preferably, a position sensing device (a position sensor and the like) is arranged on the telescopic gripper 2, and after the telescopic gripper 2 moves upwards or downwards to a set position, the automatic stop action of the telescopic gripper is controlled by a control system.
Preferably, the operations of the telescopic gripper 2, the ball valve 3, the anti-radiation camera and other mechanical parts are controlled remotely.
With reference to fig. 2, fig. 3 and fig. 4, the method for loading and unloading the reactor comprises the following steps:
s10, adjusting the position of the trolley 5 of the loading and unloading machine according to the coordinates of the target fuel assembly 7, so that the fixed sleeve 1 is accurately positioned above the fuel assembly 7 which is grabbed in the reactor 9;
s20, the lifting mechanism 8 drives the telescopic gripper 2 to descend above the fuel assembly 7, and the telescopic gripper 2 grips the fuel assembly 7;
s30, the telescopic gripper 2 drives the fuel assembly 7 to lift upwards and stop moving until the fuel assembly completely enters the fixed sleeve 1, and the ball valve 3 at the lower end of the fixed sleeve 1 is closed;
s40, the trolley 5 of the loading and unloading machine drives the fixed sleeve 1 to move, the telescopic gripper 2 is in a locking state in the moving process, the ball valve 3 is in a closing state, and the fuel assembly 7 is in a sealed accommodating state;
s50, after the trolley 5 of the loading and unloading machine moves to a designated position, the ball valve 3 is opened, the telescopic gripper 2 drives the fuel assembly 7 to move downwards to the designated position, and the telescopic gripper 2 releases the fuel assembly 7.
The method for loading and unloading the reactor material of the present invention includes three parts of grasping, moving, and releasing.
Wherein, in the grabbing state, the following steps are specifically included:
1) the fixed sleeve 1 is accurately positioned above a fuel assembly 7 which is grabbed in a reactor 9 through the movement of a trolley 5 of the loading and unloading machine, and the positioning precision of the fixed sleeve 1 is generally better than 1 mm;
2) opening the ball valve 3, driving the telescopic gripper 2 to descend to a position above the fuel assembly 7 by the lifting mechanism 8, and finishing the gripping of the fuel assembly 7 by the telescopic gripper 2;
3) the lifting mechanism 8 drives the telescopic gripper 2 to ascend until the fuel assembly 7 completely enters the fixed sleeve 1;
4) after the camera 4 observes and confirms that the fuel assembly 7 is lifted to the appointed position, the ball valve 3 is closed;
5) after the camera 4 observes and confirms that the ball valve 3 is in a sealed closed state, the moving action of the loading and unloading machine can be carried out.
In the moving state, the trolley 5 of the loading and unloading machine moves accurately, so that the telescopic gripping apparatus 2 is accurately positioned above the fuel assembly 7 transferring or storing device 10; a safety interlocking control program is arranged between the telescopic gripping apparatus 2 and the ball valve 3, the telescopic gripping apparatus 2 cannot move when the ball valve 3 is in a closed state, the ball valve 3 must be in a closed state and the telescopic gripping apparatus 2 must be in a locking state when the loading and unloading machine cart and the loading and unloading machine trolley 5 move.
In the release state, the following steps are specifically included:
1) after the cart and the trolley of the loading and unloading machine move to the designated positions, the ball valve 3 is opened, the telescopic gripping apparatus 2 drives the fuel assembly 7 to move downwards to the designated positions, and the telescopic gripping apparatus 2 releases the fuel assembly 7;
2) opening the ball valve 3, driving the telescopic gripper 2 to descend to a release position of the fuel assembly 7 by the lifting mechanism 8, and driving the telescopic gripper 2 to complete the release of the fuel assembly 7 by the lifting mechanism 8;
3) the lifting mechanism 8 drives the telescopic gripping apparatus 2 to rise to completely enter the fixed sleeve 1 and then closes the ball valve 3;
4) after the camera 4 observes and confirms that the ball valve 3 is in a sealed closed state, the loading and unloading machine can be used for carrying out next moving action.
In the using process, the ball valve 3 is arranged at the lower part of the fixed sleeve 1, in the process of grabbing the fuel assembly 7, the ball valve 3 is opened, the lifting mechanism 8 drives the telescopic gripping apparatus 2 to descend above the fuel assembly 7 to grab the fuel assembly 7, the telescopic gripping apparatus 2 drives the fuel assembly 7 to lift upwards and move to completely enter the fixed sleeve 1, then the action is stopped, and the ball valve 3 at the lower end of the fixed sleeve 1 is closed; in the transferring process of the fuel assembly 7, the cart and the trolley of the loading and unloading machine move to drive the telescopic sleeve to move, the telescopic gripping apparatus 2 is in a locking state, and the ball valve 3 is in a closing state in the moving process of the cart and the trolley; in the process of releasing the fuel assembly 7, after the cart and the trolley of the loading and unloading machine move to the designated positions, the ball valve 3 is opened, the telescopic gripping apparatus 2 drives the fuel assembly 7 to descend downwards to the designated position, and the gripping apparatus is released. The invention has the advantages of redundant safety, simple structure, convenient operation, economy, practicality, flexible use, reasonable design, compact structure and good market prospect.
It should be noted that the detailed description of the invention is not included in the prior art, or can be directly obtained from the market, and the detailed connection mode can be widely applied in the field or daily life without creative efforts, and the detailed description is not repeated here.
In the description of the present invention, it is to be understood that the terms "central," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," "circumferential," and the like are used in the orientations and positional relationships indicated in the drawings for convenience in describing the invention and to simplify the description, and are not intended to indicate or imply that the referenced devices or elements must have a particular orientation, be constructed and operated in a particular orientation, and are therefore not to be considered limiting of the invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present invention, "a plurality" means at least two, e.g., two, three, etc., unless specifically limited otherwise.
In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," "secured," and the like are to be construed broadly and can, for example, be fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; they may be directly connected or indirectly connected through intervening media, or they may be connected internally or in any other suitable relationship, unless expressly stated otherwise. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
In the present invention, unless otherwise expressly stated or limited, the first feature "on" or "under" the second feature may be directly contacting the first and second features or indirectly contacting the first and second features through an intermediate. Also, a first feature "on," "over," and "above" a second feature may be directly or diagonally above the second feature, or may simply indicate that the first feature is at a higher level than the second feature. A first feature being "under," "below," and "beneath" a second feature may be directly under or obliquely under the first feature, or may simply mean that the first feature is at a lesser elevation than the second feature.
In the description herein, references to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the invention. In this specification, the schematic representations of the terms used above are not necessarily intended to refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, various embodiments or examples and features of different embodiments or examples described in this specification can be combined and combined by one skilled in the art without contradiction.
Although embodiments of the present invention have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention, and that variations, modifications, substitutions and alterations can be made to the above embodiments by those of ordinary skill in the art within the scope of the present invention.
Claims (9)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201911402973.7A CN111028968A (en) | 2019-12-31 | 2019-12-31 | Reactor loading and unloading system and method thereof |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201911402973.7A CN111028968A (en) | 2019-12-31 | 2019-12-31 | Reactor loading and unloading system and method thereof |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN111028968A true CN111028968A (en) | 2020-04-17 |
Family
ID=70196670
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201911402973.7A Pending CN111028968A (en) | 2019-12-31 | 2019-12-31 | Reactor loading and unloading system and method thereof |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN111028968A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113593737A (en) * | 2021-07-14 | 2021-11-02 | 中国科学院上海应用物理研究所 | Automatic discharging device |
| CN113724905A (en) * | 2021-08-24 | 2021-11-30 | 中国原子能科学研究院 | Grabbing equipment |
| CN116588787A (en) * | 2023-05-16 | 2023-08-15 | 中广核研究院有限公司 | A stack internal component hoisting system |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB977293A (en) * | 1961-10-25 | 1964-12-02 | Commissariat Energie Atomique | Sealing system for the charge/discharge of a nuclear reactor |
| CN104919535A (en) * | 2013-01-15 | 2015-09-16 | 西屋电气有限责任公司 | Method and apparatus for shielded migration of nuclear components |
| CN105551545A (en) * | 2016-01-12 | 2016-05-04 | 中广核研究院有限公司 | Refueling device and method for fuel assembly |
| CN108648840A (en) * | 2018-06-11 | 2018-10-12 | 中广核研究院有限公司 | Device for reactor fuel assemblies handling |
| CN109979626A (en) * | 2017-12-27 | 2019-07-05 | 核动力运行研究所 | A kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system and method |
| CN209487163U (en) * | 2018-12-29 | 2019-10-11 | 国家电投集团科学技术研究院有限公司 | The refuelling system of pool reactor |
-
2019
- 2019-12-31 CN CN201911402973.7A patent/CN111028968A/en active Pending
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB977293A (en) * | 1961-10-25 | 1964-12-02 | Commissariat Energie Atomique | Sealing system for the charge/discharge of a nuclear reactor |
| CN104919535A (en) * | 2013-01-15 | 2015-09-16 | 西屋电气有限责任公司 | Method and apparatus for shielded migration of nuclear components |
| CN105551545A (en) * | 2016-01-12 | 2016-05-04 | 中广核研究院有限公司 | Refueling device and method for fuel assembly |
| CN109979626A (en) * | 2017-12-27 | 2019-07-05 | 核动力运行研究所 | A kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system and method |
| CN108648840A (en) * | 2018-06-11 | 2018-10-12 | 中广核研究院有限公司 | Device for reactor fuel assemblies handling |
| CN209487163U (en) * | 2018-12-29 | 2019-10-11 | 国家电投集团科学技术研究院有限公司 | The refuelling system of pool reactor |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113593737A (en) * | 2021-07-14 | 2021-11-02 | 中国科学院上海应用物理研究所 | Automatic discharging device |
| CN113593737B (en) * | 2021-07-14 | 2024-03-08 | 中国科学院上海应用物理研究所 | Automatic discharging device |
| CN113724905A (en) * | 2021-08-24 | 2021-11-30 | 中国原子能科学研究院 | Grabbing equipment |
| CN113724905B (en) * | 2021-08-24 | 2024-02-20 | 中国原子能科学研究院 | Grabbing equipment |
| CN116588787A (en) * | 2023-05-16 | 2023-08-15 | 中广核研究院有限公司 | A stack internal component hoisting system |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN111028968A (en) | Reactor loading and unloading system and method thereof | |
| JP6655541B2 (en) | System and method for transferring spent nuclear fuel from wet storage to dry storage | |
| US5661768A (en) | Spent nuclear fuel (SNF) dry transfer system | |
| CN101916605B (en) | Complete device of spent fuel storage tank and shielding cover of nuclear power plant | |
| CN105355248B (en) | Filter core transferring apparatus | |
| JP2009534678A (en) | Cask for loading at least one nuclear fuel assembly into a container, capturing means, and loading method | |
| US9449722B2 (en) | Gripping and locking/unlocking system, and application to the handling of nuclear materials specimen holders | |
| SE405903B (en) | DEVICE FOR RECEIVING AND PROTECTING AN ELONG-RADIOACTIVE NUCLEAR FUEL PATTERN | |
| CN201956081U (en) | Shielding transferring device for radioactive substance | |
| JP4958954B2 (en) | Control rod handling method and control rod handling device | |
| JP2023538079A (en) | Systems, layouts and processes of fuel handling for nuclear reactors | |
| WO2021248388A1 (en) | Nuclear fuel assembly loading/unloading container and method for loading/unloading nuclear fuel assembly | |
| US6047037A (en) | Multi-lift tool and method for moving control rods in a nuclear reactor | |
| CN109979626A (en) | A kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system and method | |
| CN205122210U (en) | Filter core transfer device | |
| WO2025041038A1 (en) | Fuel assembly handling system and process | |
| RU69305U1 (en) | DEVICE FOR RELOADING WASTE HEATED ASSEMBLIES | |
| RU2348084C1 (en) | Device for withdrawal of spent fuel assemblies | |
| CN108313713A (en) | A kind of spherical shape nuclear fuel element turnery processing automatic charging device | |
| CN114220583B (en) | Ball bed type high Wen Duika fuel blocking element storage and transfer device | |
| RU2569336C1 (en) | Pick-and-place device with transient unit for installation into and removal from nuclear reactor of core elements | |
| CN102208221A (en) | Tank plug claw for nuclear power station spent fuel storage tank | |
| CN116153540A (en) | Clamping device | |
| US20210296016A1 (en) | Fuel assembly handling device and handling assembly comprising such a device | |
| CN211125062U (en) | Transportation device of fuel assembly gripping apparatus |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20200417 |
|
| RJ01 | Rejection of invention patent application after publication |