CN201111965Y - PWR fuel assembly upper nozzle - Google Patents
PWR fuel assembly upper nozzle Download PDFInfo
- Publication number
- CN201111965Y CN201111965Y CNU2007201815946U CN200720181594U CN201111965Y CN 201111965 Y CN201111965 Y CN 201111965Y CN U2007201815946 U CNU2007201815946 U CN U2007201815946U CN 200720181594 U CN200720181594 U CN 200720181594U CN 201111965 Y CN201111965 Y CN 201111965Y
- Authority
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- Prior art keywords
- fuel assembly
- compression spring
- frame plate
- compression
- spring device
- 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.)
- Expired - Lifetime
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- 239000000446 fuel Substances 0.000 title claims abstract description 27
- 230000006835 compression Effects 0.000 claims abstract description 51
- 238000007906 compression Methods 0.000 claims abstract description 51
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 8
- 239000003758 nuclear fuel Substances 0.000 abstract description 9
- 238000009434 installation Methods 0.000 abstract description 3
- 238000005452 bending Methods 0.000 description 3
- 239000002826 coolant Substances 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 239000000306 component Substances 0.000 description 1
- 239000008358 core component Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000011900 installation process Methods 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
Images
Classifications
-
- 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
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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
本实用新型涉及核燃料元件领域,具体涉及一种压水堆燃料组件上管座。本实用新型的压紧弹簧装置设在上格板与上框板之间,只有压杆的上端从上框板上设有的通孔伸出,由于简化了弹簧装置在上管座上方的部分,节约了空间,所以压紧弹簧装置可以在上管座的四角位置均匀分布,从而使燃料组件受力均匀,提高了安全性能。同时,在四角位置分别对称布置定位销孔,从而使压水堆燃料组件的安装更加灵活方便。
The utility model relates to the field of nuclear fuel elements, in particular to an upper pipe seat of a pressurized water reactor fuel assembly. The compression spring device of the utility model is arranged between the upper grid plate and the upper frame plate, and only the upper end of the pressure rod protrudes from the through hole provided on the upper frame plate, because the part of the spring device above the upper pipe seat is simplified , saving space, so the compression spring device can be evenly distributed at the four corners of the upper pipe seat, so that the fuel assembly is evenly stressed and the safety performance is improved. At the same time, positioning pin holes are arranged symmetrically at the four corners, so that the installation of the PWR fuel assembly is more flexible and convenient.
Description
技术领域 technical field
本实用新型涉及核燃料元件领域,具体涉及一种压水堆燃料组件上管座。The utility model relates to the field of nuclear fuel elements, in particular to an upper pipe seat of a pressurized water reactor fuel assembly.
背景技术 Background technique
压水堆燃料组件是压水堆中的核心部件,是产生热量的地方,它的设计关系到压水堆的安全性、可靠性和经济性。The PWR fuel assembly is the core component of the PWR, where heat is generated, and its design is related to the safety, reliability and economy of the PWR.
压水堆燃料组件上管座中设置有压紧弹簧装置。依靠反应堆压紧部件向下压压紧弹簧装置中的压紧弹簧,使燃料组件承受足够的轴向压力,以防止燃料组件由于冷却剂的向上水力作用而窜动。此外,在反应堆运行时,由于燃料组件被固定在堆芯上下板之间,而燃料组件和堆内构件的热膨胀和辐照生长量不同,因此燃料组件上的压紧弹簧装置还起到了补偿的作用,使燃料组件有更多的生长空间,从而使组件弯曲变形得到适当控制。现有的压水堆燃料组件上管座一般采用四组板弹簧,板弹簧占用空间比较大,只能固定在上管座的两个对角上方,由于非均向布置,燃料组件受力不均匀,可能发生弯曲破坏,此外,现有的压水堆燃料组件上管座在对角位置设有定位销孔,安装方向受到限制。A compression spring device is arranged in the upper pipe seat of the PWR fuel assembly. The compression spring in the compression spring device is pressed down by the reactor compression part, so that the fuel assembly bears sufficient axial pressure to prevent the fuel assembly from moving due to the upward hydraulic action of the coolant. In addition, when the reactor is running, because the fuel assembly is fixed between the upper and lower plates of the core, and the thermal expansion and radiation growth of the fuel assembly and the internal components are different, the compression spring device on the fuel assembly also plays a role in compensating Function, so that the fuel assembly has more growth space, so that the bending deformation of the assembly is properly controlled. The existing PWR fuel assembly upper nozzle generally uses four sets of leaf springs, which occupy a relatively large space and can only be fixed above the two diagonal corners of the upper nozzle. Due to the non-uniform arrangement, the fuel assembly is not stressed. Uniform, bending damage may occur. In addition, the existing PWR fuel assembly upper pipe seat is provided with positioning pin holes at diagonal positions, and the installation direction is limited.
发明内容 Contents of the invention
本实用新型的目的在于提供一种使燃料组件受力均匀,安全性能更高的压水堆燃料组件上管座。The purpose of the utility model is to provide a pressurized water reactor fuel assembly upper nozzle which can make the fuel assembly bear uniform force and have higher safety performance.
本实用新型是这样实现的:一种压水堆燃料组件上管座,它包括上格板,设在上格板上方的上框板,在上格板与上框板之间设有压紧弹簧装置,压紧弹簧装置包括压杆,在压杆外部套有压紧弹簧,在压紧弹簧的上方,穿过压杆设有压帽,压帽在压紧弹簧的作用下紧靠在上框板的下端,压杆的上端从上框板上设有的通孔伸出,压杆8的下端伸入到上格板4所设的通孔中。The utility model is realized in the following way: an upper pipe seat of a pressurized water reactor fuel assembly, which includes an upper grid plate, an upper frame plate arranged above the upper grid plate, and a compression joint between the upper grid plate and the upper frame plate The spring device, the compression spring device includes a compression rod, a compression spring is sheathed outside the compression rod, and a compression cap is provided through the compression rod above the compression spring. The lower end of the frame plate, the upper end of the pressure rod stretches out from the through hole provided on the upper frame plate, and the lower end of the pressure rod 8 stretches into the established through hole of the
本实用新型中,压紧弹簧装置设在上格板与上框板之间,只有压杆的上端从上框板上设有的通孔伸出,由于简化了弹簧装置在上管座上方的部分,节约了空间,所以压紧弹簧装置可以在上管座的四角位置均匀分布,从而使燃料组件受力均匀,提高了安全性能。同时,在四角位置分别对称布置定位销孔,从而使压水堆燃料组件的安装更加灵活方便。In the utility model, the compression spring device is arranged between the upper grid plate and the upper frame plate, and only the upper end of the pressure rod protrudes from the through hole provided on the upper frame plate, since the spring device on the top of the upper pipe seat is simplified. part, saving space, so the compression spring device can be evenly distributed at the four corners of the upper pipe seat, so that the fuel assembly is evenly stressed, and the safety performance is improved. At the same time, positioning pin holes are arranged symmetrically at the four corners, so that the installation of the PWR fuel assembly is more flexible and convenient.
附图说明 Description of drawings
图1为本实用新型所提供的一种压水堆燃料组件上管座的正视图;Fig. 1 is the front view of the upper nozzle of a kind of pressurized water reactor fuel assembly provided by the utility model;
图2为本实用新型所提供的一种压水堆燃料组件上管座的俯视图;Fig. 2 is the top view of the upper nozzle of a kind of pressurized water reactor fuel assembly provided by the utility model;
图3为本实用新型所提供的一种压水堆燃料组件上管座的工作时的示意图;Fig. 3 is the schematic diagram during the work of a kind of pressurized water reactor fuel assembly upper nozzle provided by the utility model;
图中:1定位销孔,2上框板,3压紧弹簧装置,4上格板,5压帽,6销钉,7压紧弹簧,8压杆。Among the figure: 1 positioning pin hole, 2 upper frame plate, 3 compression spring device, 4 upper grid plate, 5 pressure cap, 6 pin, 7 compression spring, 8 pressure bar.
具体实施方式 Detailed ways
如图1~图2所示,一种压水堆燃料组件上管座,它包括上格板4,设在上格板4上方的上框板2,在上格板4与上框板2之间设有压紧弹簧装置3,压紧弹簧装置3包括压杆8,在压杆8外部套有压紧弹簧7,压杆8包括回转直径不同的两段,上端一段粗,下端一段细。在压紧弹簧7的上方,穿过压杆8安装有压帽5,压帽5通过销钉固定在压杆上,压帽5在压紧弹簧7的作用下紧靠在上框板2的下端,压杆8的上端从上框板2上设有的通孔伸出,压杆8的下端伸入到上格板4所设的通孔中。在上框板2的四角位置分别设有定位销孔1。As shown in Figures 1 to 2, a PWR fuel assembly upper nozzle includes an
本实用新型的压紧弹簧装置3的安装过程如下:The installation process of compression spring device 3 of the present utility model is as follows:
将压帽5和压紧弹簧7放入上格板4和上框板2之间,此时压紧弹簧7应被压缩一段距离,产生一定的预紧力;放入压杆8,到达一定位置,压杆8和压帽5配钻一个销钉孔;将销钉6放入所钻的销钉孔,点焊锁死。Put the pressure cap 5 and the compression spring 7 between the
本实用新型的工作原理为:压紧弹簧装置3的这些零件按以上程序组装好后,由于压紧弹簧7设计有一定的预紧力,因此没有外力作用时压紧弹簧装置3将固定在要求的位置上。当压杆8上端受到向下的大于压紧弹簧预紧力的力时,如图3所示,压杆8可沿上框板2和上格板4的通孔向下移动;当撤去这个力后,压紧弹簧装置在弹簧力的作用下复位。The working principle of the utility model is: after these parts of the compression spring device 3 are assembled according to the above procedures, since the compression spring 7 is designed with a certain pre-tightening force, the compression spring device 3 will be fixed at the required position when there is no external force. position. When the upper end of the pressure rod 8 is subjected to a downward force greater than the pre-tightening force of the compression spring, as shown in Figure 3, the pressure rod 8 can move downward along the through holes of the upper frame plate 2 and the
堆内运行时,反应堆压紧部件直接压在燃料组件上管座中均布的多套压紧弹簧装置3上,即压在每个压杆8的顶部。多套压紧弹簧装置3将压紧部件的压力均匀的传递到燃料组件的受力部件上。压紧弹簧装置3在工作状态受到的压力应既可防止燃料组件由于冷却剂的向上水力作用而窜动,又能有效的控制因热膨胀和辐照生长引起的燃料组件弯曲变形,使燃料组件能保持正常的工作状态。When running in the reactor, the reactor pressing parts are directly pressed on multiple sets of pressing spring devices 3 evenly distributed in the fuel assembly upper nozzle, that is, pressing on the top of each pressing rod 8 . Multiple sets of pressing spring devices 3 evenly transmit the pressure of the pressing parts to the stressed parts of the fuel assembly. The pressure on the compression spring device 3 in the working state should not only prevent the fuel assembly from moving due to the upward hydraulic action of the coolant, but also effectively control the bending deformation of the fuel assembly caused by thermal expansion and radiation growth, so that the fuel assembly can Maintain normal working condition.
本实用新型的上框板2的四角位置分别设有定位销孔1,燃料组件能以任意角度装入堆芯,使燃料组件在各个循环中可以以不同角度装入堆芯,从而使组件中燃耗更加均匀。The four corners of the upper frame plate 2 of the utility model are respectively provided with positioning pin holes 1, the fuel assembly can be loaded into the core at any angle, so that the fuel assembly can be loaded into the core at different angles in each cycle, so that the assembly Burnup is more even.
Claims (2)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNU2007201815946U CN201111965Y (en) | 2007-10-19 | 2007-10-19 | PWR fuel assembly upper nozzle |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNU2007201815946U CN201111965Y (en) | 2007-10-19 | 2007-10-19 | PWR fuel assembly upper nozzle |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN201111965Y true CN201111965Y (en) | 2008-09-10 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CNU2007201815946U Expired - Lifetime CN201111965Y (en) | 2007-10-19 | 2007-10-19 | PWR fuel assembly upper nozzle |
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| CN (1) | CN201111965Y (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102136303A (en) * | 2010-01-25 | 2011-07-27 | 韩电原子力燃料株式会社 | Hold-down spring unit for top nozzle of nuclear fuel assembly having improved hold-down performance and top nozzle for nuclear fuel assembly having the same |
| CN104575629A (en) * | 2014-12-05 | 2015-04-29 | 上海核工程研究设计院 | Detachable upper pipe seat and guide pipe connecting structure |
| CN105513658A (en) * | 2010-01-25 | 2016-04-20 | 韩电原子力燃料株式会社 | Top nozzle for nuclear fuel assembly having spring insert hole improved in fastening stability and method of manufacturing the same |
| CN106531230A (en) * | 2016-11-18 | 2017-03-22 | 中国核动力研究设计院 | High stability fuel assembly compacting system with variable rigidity and low radiation slack |
| CN106803432A (en) * | 2017-02-28 | 2017-06-06 | 中国核动力研究设计院 | A kind of ex-reactor experiment structure of fuel assembly |
| CN110993127A (en) * | 2019-11-29 | 2020-04-10 | 广东核电合营有限公司 | A nuclear fuel assembly and variable stiffness pressing device |
-
2007
- 2007-10-19 CN CNU2007201815946U patent/CN201111965Y/en not_active Expired - Lifetime
Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102136303A (en) * | 2010-01-25 | 2011-07-27 | 韩电原子力燃料株式会社 | Hold-down spring unit for top nozzle of nuclear fuel assembly having improved hold-down performance and top nozzle for nuclear fuel assembly having the same |
| CN102136303B (en) * | 2010-01-25 | 2014-10-01 | 韩电原子力燃料株式会社 | Hold-down spring unit for top nozzle of nuclear fuel assembly having improved hold-down performance and top nozzle for nuclear fuel assembly having the same |
| CN105513658A (en) * | 2010-01-25 | 2016-04-20 | 韩电原子力燃料株式会社 | Top nozzle for nuclear fuel assembly having spring insert hole improved in fastening stability and method of manufacturing the same |
| CN105513658B (en) * | 2010-01-25 | 2019-07-19 | 韩电原子力燃料株式会社 | The nuclear fuel assembly pipe top nozzle and its manufacturing method of spring jack with stability maintenance improvement |
| CN104575629A (en) * | 2014-12-05 | 2015-04-29 | 上海核工程研究设计院 | Detachable upper pipe seat and guide pipe connecting structure |
| CN106531230A (en) * | 2016-11-18 | 2017-03-22 | 中国核动力研究设计院 | High stability fuel assembly compacting system with variable rigidity and low radiation slack |
| CN106531230B (en) * | 2016-11-18 | 2018-09-11 | 中国核动力研究设计院 | A kind of high stability fuel assembly pressing system of the low Irradiation slack of variation rigidity |
| CN106803432A (en) * | 2017-02-28 | 2017-06-06 | 中国核动力研究设计院 | A kind of ex-reactor experiment structure of fuel assembly |
| CN106803432B (en) * | 2017-02-28 | 2018-05-25 | 中国核动力研究设计院 | A kind of ex-reactor experiment structure of fuel assembly |
| CN110993127A (en) * | 2019-11-29 | 2020-04-10 | 广东核电合营有限公司 | A nuclear fuel assembly and variable stiffness pressing device |
| CN110993127B (en) * | 2019-11-29 | 2021-08-27 | 广东核电合营有限公司 | Nuclear fuel assembly and variable-rigidity pressing device |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term |
Granted publication date: 20080910 |
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| CX01 | Expiry of patent term |