CN103985419A - Fuel assembly locking device of liquid-state heavy metal reactor - Google Patents

Fuel assembly locking device of liquid-state heavy metal reactor Download PDF

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CN103985419A
CN103985419A CN201410247684.5A CN201410247684A CN103985419A CN 103985419 A CN103985419 A CN 103985419A CN 201410247684 A CN201410247684 A CN 201410247684A CN 103985419 A CN103985419 A CN 103985419A
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fuel assembly
guide groove
reactor
grid plate
pin
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CN103985419B (en
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何梅生
柏云清
吴宜灿
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Hefei Institutes of Physical Science of CAS
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Hefei Institutes of Physical Science of CAS
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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract

本发明提供一种液态重金属反应堆的燃料组件锁紧装置。所述装置包括:堆芯燃料组件(1)、堆芯下栅板(2)、栅板导槽(3)、燃料组件管脚(4)、固定套筒(5)和固定凸台(6);堆芯燃料组件(1)与燃料组件管脚(4)焊接为一体;固定套筒(5)通过螺纹轴向固定在燃料组件管脚(4)的外侧,并能够绕燃料组件管脚(4)的中心轴转动;固定凸台(6)焊接在固定套筒(5)的表面,栅板导槽(3)为位于堆芯下栅板(2)的孔内,固定凸台(6)与栅板导槽(3)的配合,将燃料组件(1)固定在堆芯下栅板(2)上。本实施例的装置结构简单,使用方便,且使用时位于中子辐照较弱的位置,安全性高。

The invention provides a fuel assembly locking device for a liquid heavy metal reactor. The device includes: core fuel assembly (1), core lower grid plate (2), grid plate guide groove (3), fuel assembly pins (4), fixing sleeve (5) and fixing boss (6 ); the core fuel assembly (1) is welded together with the fuel assembly pin (4); the fixing sleeve (5) is axially fixed on the outside of the fuel assembly pin (4) through threads, and can wrap around the fuel assembly pin The central axis of (4) rotates; the fixed boss (6) is welded on the surface of the fixed sleeve (5), the grid plate guide groove (3) is in the hole of the grid plate (2) under the core, and the fixed boss ( 6) Cooperate with the grid plate guide groove (3) to fix the fuel assembly (1) on the core lower grid plate (2). The device in this embodiment has a simple structure and is easy to use, and is located at a place where neutron radiation is relatively weak during use, so it has high safety.

Description

一种液态重金属反应堆的燃料组件锁紧装置A fuel assembly locking device for a liquid heavy metal reactor

技术领域technical field

本发明涉及重金属冷却核反应堆的堆芯部件设计技术领域,尤其涉及一种液态重金属反应堆的燃料组件锁紧装置。The invention relates to the technical field of core component design of a heavy metal cooling nuclear reactor, in particular to a fuel assembly locking device of a liquid heavy metal reactor.

背景技术Background technique

液态铅铋合金以其良好的中子学性能、优良的抗辐照性能、传热性能和安全特性,已经成为目前加速器驱动次临界系统(Accelerator driven system;ADS)系统散裂靶兼冷却剂的首选材料,同时铅铋冷却剂也是先进快中子堆的冷却剂首选材料。由于铅铋冷却剂固有的物理性质,其密度远大于液态金属快堆的燃料组件,密度差将使燃料组件产生较大的浮力,且需要考虑冷却剂自堆芯向上流动对组件产生的流致振动问题,所以燃料组件无法依靠自身重量进行固定。燃料组件一旦在堆芯中产生窜动,对安全影响较大。Liquid lead-bismuth alloy has become the main choice of spallation target and coolant in accelerator driven subcritical system (Accelerator driven system; ADS) system due to its good neutronics performance, excellent radiation resistance performance, heat transfer performance and safety characteristics. The material of choice, while lead-bismuth coolant is also the material of choice for the coolant of advanced fast neutron reactors. Due to the inherent physical properties of the lead-bismuth coolant, its density is much higher than that of the fuel assembly of the liquid metal fast reactor, and the density difference will cause the fuel assembly to generate greater buoyancy, and it is necessary to consider the flow induced by the upward flow of the coolant from the core to the assembly. Vibration issues, so the fuel assembly cannot be held in place by its own weight. Once the fuel assembly moves in the core, it will have a great impact on safety.

目前,国际上大部分的液态金属冷却的快中子堆,都采用池式结构。对于池式研究堆,一回路全部浸泡在堆池中,反应堆处于密封的状态,且在上部设有覆盖气体(通常选择氩气)保护。因此为了不破坏反应堆密封状态,防止放射性物质外泻,反应堆的换料系统优选采用机械进行远程遥控操作换料,以保证完整的反应堆边界。At present, most of the fast neutron reactors cooled by liquid metal in the world adopt pool structure. For pool-type research reactors, the primary circuit is completely immersed in the reactor pool, the reactor is in a sealed state, and the upper part is protected by a covering gas (usually argon). Therefore, in order not to damage the sealed state of the reactor and prevent the leakage of radioactive substances, the refueling system of the reactor preferably adopts mechanical remote control operation to refuel, so as to ensure the integrity of the reactor boundary.

在目前液态重金属反应堆燃料组件设计方案中,有俄罗斯模块式铅铋快堆(Svintsovo-Vismutovyi Bystryi Reaktor'-lead-bismuth fast reactor;俄罗斯SVBR)燃料组件方案、欧盟实验加速器驱动次临界系统(The eXperimental Accelerator DrivenSystem;XADS)燃料组件方案和欧洲先进铅冷示范快堆(The Advanced Lead Fast ReactorEuropean Demonstrator;ALFRED)燃料组件方案,以及比利时高科技应用多功能混合动力研究反应堆(Multi-purpose hybrid research reactor for high-tech applications;MYRRHA)燃料组件方案。其中SVBR燃料组件固定连接在堆芯内,无法进行在线换料。XADS燃料组件在管脚中设置活扣,通过与活扣相连的导杆,控制活扣的关闭和开启实现燃料组件的装卸。该方案在燃料组件的中心位置用导杆代替了燃料棒,降低了燃料组件内的燃料密度,降低了反应堆堆芯的经济性,同时导杆位于活性区,承受高强中子辐照,其安全性无法保证。ALFRED燃料组件通过延长操作头,将操作头直接露出反应堆,在堆外进行燃料组件的固定。该方案由于需要打开顶盖换料,其内的放射性气体会进入反应堆外部空间,需要在反应堆外部增加其他屏蔽,防止高放射性气体泄漏。MYRRHA堆燃料组件是将堆芯栅板置于顶部,通过堆芯栅板压住燃料组件,利用浮力实现燃料组件的固定。该方案需要在堆芯下部预留交大的换料操作空间,且该区域需充满铅铋合金,大大减低了反应堆的经济性。Among the current liquid heavy metal reactor fuel assembly design schemes, there are the Russian modular lead-bismuth fast reactor (Svintsovo-Vismutovyi Bystryi Reaktor'-lead-bismuth fast reactor; Russian SVBR) fuel assembly scheme, the EU experimental accelerator-driven subcritical system (The eXperimental Accelerator DrivenSystem; XADS) fuel assembly program and the Advanced Lead Fast Reactor European Demonstrator (ALFRED) fuel assembly program, as well as the Belgian high-tech application multi-purpose hybrid research reactor (Multi-purpose hybrid research reactor for high -tech applications; MYRRHA) fuel assembly program. Among them, the SVBR fuel assembly is fixedly connected in the core and cannot be refueled online. The XADS fuel assembly is equipped with a snap button in the tube pin, and through the guide rod connected with the snap button, the closing and opening of the snap button is controlled to realize the loading and unloading of the fuel assembly. In this scheme, the fuel rod is replaced by a guide rod at the center of the fuel assembly, which reduces the fuel density in the fuel assembly and reduces the economy of the reactor core. Sex is not guaranteed. The ALFRED fuel assembly extends the operating head to directly expose the operating head to the reactor, and fixes the fuel assembly outside the reactor. Since the solution needs to open the top cover for refueling, the radioactive gas inside will enter the space outside the reactor, and other shielding needs to be added outside the reactor to prevent the leakage of highly radioactive gas. The MYRRHA stack fuel assembly places the core grid on the top, presses the fuel assembly through the core grid, and uses buoyancy to fix the fuel assembly. This scheme needs to reserve a large refueling operation space in the lower part of the core, and this area needs to be filled with lead-bismuth alloy, which greatly reduces the economical efficiency of the reactor.

总之,上述现有的俄罗斯SVBR燃料组件方案、欧盟XADS燃料组件方案和ALFRED燃料组件方案,以及比利时MYRRHA燃料组件方案存在不同的缺陷。In a word, the above-mentioned existing Russian SVBR fuel assembly scheme, EU XADS fuel assembly scheme and ALFRED fuel assembly scheme, as well as the Belgian MYRRHA fuel assembly scheme have different defects.

发明内容Contents of the invention

本发明提供一种液态重金属反应堆的燃料组件锁紧装置,用以解决现有技术中各种燃料组件方案的缺陷。The invention provides a fuel assembly locking device for a liquid heavy metal reactor, which is used to solve the defects of various fuel assembly solutions in the prior art.

本发明提供一种液态重金属反应堆的燃料组件锁紧装置,所述装置包括:堆芯燃料组件(1)、堆芯下栅板(2)、栅板导槽(3)、燃料组件管脚(4)、固定套筒(5)和固定凸台(6);The invention provides a fuel assembly locking device for a liquid heavy metal reactor, the device comprising: core fuel assembly (1), core lower grid plate (2), grid plate guide groove (3), fuel assembly pins ( 4), fixed sleeve (5) and fixed boss (6);

其中,所述堆芯燃料组件(1)与所述燃料组件管脚(4)焊接为一体;所述固定套筒(5)通过螺纹轴向固定在所述燃料组件管脚(4)的外侧,并能够绕所述燃料组件管脚(4)的中心轴转动;所述固定凸台(6)焊接在所述固定套筒(5)的表面,所述栅板导槽(3)为位于所述堆芯下栅板(2)的孔内,所述固定凸台(6)与所述栅板导槽(3)的配合,将所述燃料组件(1)固定在所述堆芯下栅板(2)上。Wherein, the core fuel assembly (1) is welded together with the fuel assembly pin (4); the fixing sleeve (5) is axially fixed on the outside of the fuel assembly pin (4) through threads , and can rotate around the central axis of the fuel assembly pin (4); the fixed boss (6) is welded on the surface of the fixed sleeve (5), and the grid guide groove (3) is located In the hole of the grid plate (2) under the core, the fixing boss (6) cooperates with the guide groove (3) of the grid plate to fix the fuel assembly (1) under the core on the grille (2).

可选地,如上所述的装置中,其中,所述堆芯燃料组件(1)为六边形柱体。Optionally, in the above device, wherein, the core fuel assembly (1) is a hexagonal cylinder.

可选地,如上所述的装置中,其中,所述燃料组件管脚(4)为圆柱型。Optionally, in the above-mentioned device, wherein, the fuel assembly pin (4) is cylindrical.

可选地,如上所述的装置中,其中,所述栅板导槽(3)为内锯齿形槽。Optionally, in the above-mentioned device, wherein, the grid guide groove (3) is an inner zigzag groove.

可选地,如上所述的装置中,其中,所述固定凸台(6)的数目与所述栅板导槽(3)的内锯齿形槽的数目相同。Optionally, in the above-mentioned device, wherein, the number of the fixing bosses (6) is the same as the number of the inner zigzag grooves of the grid guide groove (3).

可选地,如上所述的装置中,其中,所述固定凸台(6)的数目与所述栅板导槽(3)的内锯齿形槽的数目均为三个。Optionally, in the above-mentioned device, the number of the fixing bosses (6) and the number of inner zigzag grooves of the grid guide groove (3) are both three.

可选地,如上所述的装置中,其中,所述燃料组件管脚(4)包括所述燃料组件管脚(4)的上部(41)和所述燃料组件管脚(4)的下部(42)两部分,所述固定套筒(5)套入所述燃料组件管脚(4)的所述上部(41),所述燃料组件管脚(4)的所述下部(42)通过螺纹与所述燃料组件管脚(4)的所述上部(41)连接,将所述固定套筒(5)轴向固定在所述燃料组件管脚(4)上。Optionally, in the above-mentioned device, wherein, the fuel assembly pin (4) includes an upper part (41) of the fuel assembly pin (4) and a lower part ( 42) Two parts, the fixing sleeve (5) is inserted into the upper part (41) of the fuel assembly pin (4), and the lower part (42) of the fuel assembly pin (4) is threaded It is connected with the upper part (41) of the fuel assembly pin (4), and axially fixes the fixing sleeve (5) on the fuel assembly pin (4).

可选地,如上所述的装置中,其中,所述燃料组件管脚(4)与所述固定套筒(5)之间为圆锥与圆弧的线接触。Optionally, in the above-mentioned device, wherein, the line contact between the fuel assembly pin (4) and the fixing sleeve (5) is a cone or an arc.

本发明还提供一种使用如上任一所述的液态重金属反应堆的燃料组件锁紧装置进行燃料组件换料的方法,包括如下步骤:The present invention also provides a method for fuel assembly refueling using the fuel assembly locking device of any one of the above liquid heavy metal reactors, comprising the following steps:

当进行装料时,换料机构通过控制所述堆芯燃料组件(1)将所述燃料组件管脚(4)插入所述堆芯下栅板(2)中的安装孔,将所述固定套筒(5)连同所述固定凸台(6)滑入所述栅板导槽(3),使得所述固定凸台(6)沿着所述栅板导槽(3)下平面旋转直至最底部;When charging, the refueling mechanism controls the core fuel assembly (1) to insert the fuel assembly pins (4) into the installation holes in the lower grid plate (2) of the core to fix the The sleeve (5) slides into the grid guide groove (3) together with the fixing boss (6), so that the fixing boss (6) rotates along the lower plane of the grid guide groove (3) until the bottom;

换料机构拉动所述堆芯燃料组件(1)向上提升,使得所述固定凸台(6)沿着所述栅板导槽(3)上平面旋转至最顶部,并在此位置通过球与面的接触固定;The refueling mechanism pulls the core fuel assembly (1) to lift up, so that the fixed boss (6) rotates to the top along the upper plane of the grid guide groove (3), and at this position passes the ball and surface contact fixation;

当进行换料时,换料机构将所述堆芯燃料组件(1)再次下压,所述固定凸台(6)沿着栅板导槽(3)下平面旋转直至最底部后,换料机构向上提升,所述堆芯燃料组件(1)脱离所述堆芯下栅板(2),实现换料。When refueling, the refueling mechanism presses down the core fuel assembly (1) again, and the fixed boss (6) rotates along the lower plane of the grid guide groove (3) until it reaches the bottom, then the refueling The mechanism is lifted upwards, and the core fuel assembly (1) is detached from the lower core grid (2) to realize refueling.

本发明的液态重金属反应堆的燃料组件锁紧装置,通过栅板和燃料组件的配合,既为燃料组件提供了足够的轴向约束,又不影响燃料组件向上取出换料。本发明的液态重金属反应堆的燃料组件锁紧装置,结构简单,使用非常方便,且能够多次使用,能够有效地降低换料成本。且使用时位于中子辐照较弱的位置,安全性高;还可以有效防止燃料元件在液态重金属堆中的窜动,并能够实现反应堆的在线换料。此外,此种锁紧装置能较好的克服组件受热轴向变形引起的热应力。The fuel assembly locking device of the liquid heavy metal reactor of the present invention not only provides sufficient axial restraint for the fuel assembly through the cooperation of the grid plate and the fuel assembly, but also does not affect the upward removal of the fuel assembly for refueling. The fuel assembly locking device of the liquid heavy metal reactor of the present invention has a simple structure, is very convenient to use, can be used many times, and can effectively reduce the cost of refueling. And when used, it is located at a position where neutron irradiation is relatively weak, and has high safety; it can also effectively prevent the movement of fuel elements in the liquid heavy metal pile, and can realize online refueling of the reactor. In addition, this locking device can better overcome the thermal stress caused by thermal axial deformation of the components.

附图说明Description of drawings

为了更清楚地说明本发明实施例或现有技术中的技术方案,下面将对实施例或现有技术描述中所需要使用的附图作一简单地介绍,显而易见地,下面描述中的附图是本发明的一些实施例,对于本领域普通技术人员来讲,在不付出创造性劳动性的前提下,还可以根据这些附图获得其他的附图。In order to more clearly illustrate the technical solutions in the embodiments of the present invention or the prior art, the following will briefly introduce the drawings that need to be used in the description of the embodiments or the prior art. Obviously, the accompanying drawings in the following description These are some embodiments of the present invention. For those skilled in the art, other drawings can also be obtained according to these drawings without any creative effort.

图1为本发明实施例提供的液态重金属反应堆的燃料组件锁紧装置的剖面示意图。Fig. 1 is a schematic cross-sectional view of a fuel assembly locking device of a liquid heavy metal reactor provided by an embodiment of the present invention.

图2为本发明实施例提供的液态重金属反应堆的燃料组件锁紧装置中局部的轴向剖面图。Fig. 2 is a partial axial sectional view of the fuel assembly locking device of the liquid heavy metal reactor provided by the embodiment of the present invention.

图3为本发明实施例提供的液态重金属反应堆的燃料组件锁紧装置中局部的纵向剖面图。Fig. 3 is a partial longitudinal sectional view of the fuel assembly locking device of the liquid heavy metal reactor provided by the embodiment of the present invention.

图4为本发明实施例提供的液态重金属反应堆的燃料组件锁紧装置中局部的轴向展开图。Fig. 4 is a partial axial expansion view of the fuel assembly locking device of the liquid heavy metal reactor provided by the embodiment of the present invention.

图5为本发明实施例提供的使用如上实施例的液态重金属反应堆的燃料组件锁紧装置进行燃料组件换料的方法流程图。Fig. 5 is a flowchart of a method for refueling a fuel assembly using the fuel assembly locking device of the liquid heavy metal reactor in the above embodiment provided by an embodiment of the present invention.

具体实施方式Detailed ways

为使本发明实施例的目的、技术方案和优点更加清楚,下面将结合本发明实施例中的附图,对本发明实施例中的技术方案进行清楚、完整地描述,显然,所描述的实施例是本发明一部分实施例,而不是全部的实施例。基于本发明中的实施例,本领域普通技术人员在没有作出创造性劳动前提下所获得的所有其他实施例,都属于本发明保护的范围。In order to make the purpose, 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 in conjunction with the drawings in the embodiments of the present invention. Obviously, the described embodiments It is a part of embodiments of the present invention, but not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by persons of ordinary skill in the art without creative efforts fall within the protection scope of the present invention.

图1为本发明实施例提供的液态重金属反应堆的燃料组件锁紧装置的剖面示意图。如图1所示,本实施例的液态重金属反应堆的燃料组件锁紧装置包括:堆芯燃料组件1、堆芯下栅板2、栅板导槽3、燃料组件管脚4、固定套筒5和固定凸台6。Fig. 1 is a schematic cross-sectional view of a fuel assembly locking device of a liquid heavy metal reactor provided by an embodiment of the present invention. As shown in Figure 1, the fuel assembly locking device of the liquid heavy metal reactor in this embodiment includes: core fuel assembly 1, core lower grid plate 2, grid plate guide groove 3, fuel assembly pin 4, fixed sleeve 5 And fixed boss 6.

其中,堆芯燃料组件1与燃料组件管脚4焊接为一体;固定套筒5通过螺纹轴向固定在燃料组件管脚4的外侧,并能够绕燃料组件管脚4的中心轴转动;固定凸台6焊接在固定套筒5的表面,栅板导槽3为位于堆芯下栅板2的孔内,固定凸台6与栅板导槽3的配合,将燃料组件1固定在堆芯下栅板2上。Wherein, the core fuel assembly 1 is welded together with the fuel assembly pin 4; the fixing sleeve 5 is axially fixed on the outer side of the fuel assembly pin 4 through threads, and can rotate around the central axis of the fuel assembly pin 4; The platform 6 is welded on the surface of the fixing sleeve 5, the grid guide groove 3 is located in the hole of the grid plate 2 under the core, and the fixing boss 6 cooperates with the grid guide groove 3 to fix the fuel assembly 1 under the core grid 2.

如图1所示,由堆芯燃料组件1、堆芯下栅板2、栅板导槽3、燃料组件管脚4、固定套筒5和固定凸台6的相对位置可知,燃料组件1的下部插入堆芯下栅板2,通过轴向固定在组件管脚4上的凸台6与栅板导槽3的配合,来完成燃料组件在堆芯内的轴向定位。在换料过程中,换料机抓取燃料组件1的头部,通过简单的上下运动即可完成燃料组件4在堆芯内的固定和解锁。As shown in Figure 1, from the relative positions of the core fuel assembly 1, the lower core grid 2, the grid guide groove 3, the fuel assembly pin 4, the fixing sleeve 5 and the fixing boss 6, it can be known that the fuel assembly 1 The lower part is inserted into the lower grid plate 2 of the core, and the axial positioning of the fuel assembly in the core is completed through the cooperation of the boss 6 axially fixed on the assembly pin 4 and the guide groove 3 of the grid plate. During the refueling process, the refueling machine grabs the head of the fuel assembly 1, and the fixing and unlocking of the fuel assembly 4 in the core can be completed through a simple up and down movement.

例如本实施例中的堆芯燃料组件1可以为六边形柱体;本实施例中的反应堆中的堆芯燃料组件1采用六边形柱体;这和反应堆内栅元排布有关系。六边形的组件才能相互拼接在一起,像蜂窝一样组成反应堆堆芯。燃料组件管脚4为圆柱型;理论上燃料组件管脚4也可以采用其他形状,但是由于圆形具有良好的对中等性能,及加工的便利性,所以快中子反应堆的设计中,采用圆柱形的燃料组件管脚4效果更好,但不排斥采用其他形状的,如方柱体形状的。栅板导槽3为内锯齿形槽。For example, the core fuel assembly 1 in this embodiment can be a hexagonal cylinder; the core fuel assembly 1 in the reactor in this embodiment adopts a hexagonal cylinder; this is related to the arrangement of cells in the reactor. The hexagonal components can be spliced together to form the reactor core like a honeycomb. The pin 4 of the fuel assembly is cylindrical; in theory, the pin 4 of the fuel assembly can also adopt other shapes, but because the circular shape has good alignment performance and the convenience of processing, the design of the fast neutron reactor uses a cylindrical The effect of the shaped fuel assembly pin 4 is better, but it does not exclude the use of other shapes, such as the shape of a square cylinder. The grid guide groove 3 is an inner zigzag groove.

可选地,本实施例中的固定凸台6的数目与栅板导槽3的内锯齿形槽的数目相同。Optionally, the number of fixing bosses 6 in this embodiment is the same as the number of inner zigzag grooves of grid guide groove 3 .

本实施例的液态重金属反应堆的燃料组件锁紧装置,通过栅板和燃料组件的配合,既为燃料组件提供了足够的轴向约束,又不影响燃料组件向上取出换料。本实施例的液态重金属反应堆的燃料组件锁紧装置,结构简单,使用非常方便,且能够多次使用,能够有效地降低换料成本。且使用时位于中子辐照较弱的位置,安全性高;还可以有效防止燃料元件在液态重金属堆中的窜动,并能够实现反应堆的在线换料。此外,此种锁紧装置能较好的克服组件受热轴向变形引起的热应力。The fuel assembly locking device of the liquid heavy metal reactor in this embodiment, through the cooperation of the grid plate and the fuel assembly, not only provides sufficient axial restraint for the fuel assembly, but also does not affect the upward removal of the fuel assembly for refueling. The fuel assembly locking device of the liquid heavy metal reactor in this embodiment has a simple structure, is very convenient to use, can be used many times, and can effectively reduce the cost of refueling. And when used, it is located at a position where neutron irradiation is relatively weak, and has high safety; it can also effectively prevent the movement of fuel elements in the liquid heavy metal pile, and can realize online refueling of the reactor. In addition, this locking device can better overcome the thermal stress caused by thermal axial deformation of the components.

图2为本发明实施例提供的液态重金属反应堆的燃料组件锁紧装置中局部的轴向剖面图。如图2所示,由轴向剖面图可知,燃料组件管脚4包括燃料组件管脚4的上部41和燃料组件管脚4的下部42两部分,固定套筒5套入燃料组件管脚4的上部41,燃料组件管脚4的下部42通过螺纹与燃料组件管脚4的上部41连接,将固定套筒5轴向固定在燃料组件管脚4上。例如燃料组件管脚4与固定套筒5之间为圆锥与圆弧的线接触,可以有效的降低两接触面间由于金属扩散产生自焊的影响。Fig. 2 is a partial axial sectional view of the fuel assembly locking device of the liquid heavy metal reactor provided by the embodiment of the present invention. As shown in Figure 2, it can be seen from the axial section view that the fuel assembly pin 4 includes two parts, the upper part 41 of the fuel assembly pin 4 and the lower part 42 of the fuel assembly pin 4, and the fixing sleeve 5 is inserted into the fuel assembly pin 4 The upper part 41 of the fuel assembly pin 4 is connected with the upper part 41 of the fuel assembly pin 4 through threads, and the fixing sleeve 5 is axially fixed on the fuel assembly pin 4 . For example, the line contact between the pin 4 of the fuel assembly and the fixed sleeve 5 is a cone and an arc, which can effectively reduce the influence of self-welding between the two contact surfaces due to metal diffusion.

图3为本发明实施例提供的液态重金属反应堆的燃料组件锁紧装置中局部的纵向剖面图。如图3所示,本实施例中以固定凸台6的数目与栅板导槽3的内锯齿形槽的数目均为三个为例来说明的技术方案。如图3所示,由纵向剖面图可知,栅板导槽3位于堆芯下栅板2的安装孔中,固定套筒5与燃料组件管脚4同心安装。每根燃料组件1的固定凸台6共有三个,位于固定套筒5上。固定凸台6插入栅板导槽3对应的位置中。Fig. 3 is a partial longitudinal sectional view of the fuel assembly locking device of the liquid heavy metal reactor provided by the embodiment of the present invention. As shown in FIG. 3 , in this embodiment, the number of fixed bosses 6 and the number of inner zigzag grooves of grid plate guide groove 3 are both three to illustrate the technical solution. As shown in FIG. 3 , it can be seen from the longitudinal sectional view that the grid guide groove 3 is located in the installation hole of the grid plate 2 under the core, and the fixing sleeve 5 is installed concentrically with the fuel assembly pin 4 . There are three fixing bosses 6 for each fuel assembly 1 , which are located on the fixing sleeve 5 . The fixing boss 6 is inserted into the position corresponding to the grid guide groove 3 .

图4为本发明实施例提供的液态重金属反应堆的燃料组件锁紧装置中局部的轴向展开图。如图4所示,栅板导槽3沿轴向展开,固定凸台6在栅板导槽3内沿锯齿状边缘运动。当进行装料时,换料机构将燃料组件管脚4插入堆芯下栅板2中的安装孔,固定套筒5带动固定凸台6滑入栅板导槽3,位于图中①的位置;固定凸台6沿着栅板导槽3下平面旋转向下至最底部,位于图中②的位置;换料机构向上提升,固定凸台6沿着栅板导槽3上平面旋转至最顶部,位于图中③的位置,并在此位置通过球与面的接触固定。当进行换料时,换料机构将堆芯燃料组件1再次下压,固定凸台6沿着栅板导槽3下平面旋转直至最底部后,即图中④的位置,换料机构向上提升,固定凸台6移至图中⑤的位置,堆芯燃料组件1脱离堆芯下栅板2,实现换料的过程。Fig. 4 is a partial axial expansion view of the fuel assembly locking device of the liquid heavy metal reactor provided by the embodiment of the present invention. As shown in FIG. 4 , the grid plate guide groove 3 expands in the axial direction, and the fixing boss 6 moves along the serrated edge in the grid plate guide groove 3 . When charging, the refueling mechanism inserts the fuel assembly pin 4 into the installation hole in the lower grid plate 2 of the core, and the fixed sleeve 5 drives the fixed boss 6 to slide into the grid plate guide groove 3, which is located at the position ① in the figure ; The fixed boss 6 rotates along the lower plane of the grid guide groove 3 and goes down to the bottom, which is located at the position ② in the figure; The top is located at the position ③ in the figure, and is fixed at this position by the contact between the ball and the surface. When refueling, the refueling mechanism presses down the core fuel assembly 1 again, and the fixed boss 6 rotates along the lower plane of the grid guide groove 3 to the bottom, which is the position ④ in the figure, and the refueling mechanism lifts up , the fixed boss 6 moves to the position ⑤ in the figure, and the core fuel assembly 1 is detached from the core lower grid plate 2 to realize the process of refueling.

上述实施例的液态重金属反应堆的燃料组件锁紧装置的工作原理:将燃料组件管脚4插入堆芯下栅板2中的安装孔,固定套筒5连同固定凸台6滑入栅板导槽3,并使得固定凸台6沿着栅板导槽3下平面旋转直至最底部;当向上提升堆芯燃料组件1,底部的固定凸台6跟随堆芯燃料组件1运动,使得固定凸台6沿着栅板导槽3上平面旋转至最顶部,并在此位置通过球与面的接触固定,此种接触,有利于防止长时间静止在堆芯中,结构钢材之间自焊效应;进行换料时,将堆芯燃料组件1再次下压,固定凸台6沿着栅板导槽3下平面旋转直至最底部后,换料机构向上提升,堆芯燃料组件1脱离堆芯下栅板2,实现换料。The working principle of the fuel assembly locking device of the liquid heavy metal reactor in the above embodiment: insert the fuel assembly pin 4 into the mounting hole in the lower grid plate 2 of the core, and slide the fixing sleeve 5 together with the fixing boss 6 into the guide groove of the grid plate 3, and make the fixed boss 6 rotate along the lower plane of the grid guide groove 3 to the bottom; when the core fuel assembly 1 is lifted up, the fixed boss 6 at the bottom follows the movement of the core fuel assembly 1, so that the fixed boss 6 Rotate along the upper plane of the grid guide groove 3 to the top, and fix at this position through the contact between the ball and the surface. This contact is beneficial to prevent the self-welding effect between the structural steels when they are still in the core for a long time; When refueling, the core fuel assembly 1 is pressed down again, and the fixed boss 6 is rotated along the lower plane of the grid guide groove 3 to the bottom, and the refueling mechanism is lifted upwards, and the core fuel assembly 1 is separated from the lower grid 2. Realize refueling.

上述实施例的液态重金属反应堆的燃料组件锁紧装置,通过栅板和燃料组件的配合,既为燃料组件提供了足够的轴向约束,又不影响燃料组件向上取出换料。本实施例的液态重金属反应堆的燃料组件锁紧装置,结构简单,使用非常方便,且能够多次使用,能够有效地降低换料成本。且使用时位于中子辐照较弱的位置,安全性高;还可以有效防止燃料元件在液态重金属堆中的窜动,并能够实现反应堆的在线换料。此外,此种锁紧装置能较好的克服组件受热轴向变形引起的热应力。The fuel assembly locking device of the liquid heavy metal reactor in the above embodiment, through the cooperation of the grid plate and the fuel assembly, not only provides sufficient axial restraint for the fuel assembly, but also does not affect the upward removal of the fuel assembly for refueling. The fuel assembly locking device of the liquid heavy metal reactor in this embodiment has a simple structure, is very convenient to use, can be used many times, and can effectively reduce the cost of refueling. And when used, it is located at a position where neutron irradiation is relatively weak, and has high safety; it can also effectively prevent the movement of fuel elements in the liquid heavy metal pile, and can realize online refueling of the reactor. In addition, this locking device can better overcome the thermal stress caused by thermal axial deformation of the components.

图5为本发明实施例提供的使用如上实施例的液态重金属反应堆的燃料组件锁紧装置进行燃料组件换料的方法流程图。其中,液态重金属反应堆的燃料组件锁紧装置详见上述实施例的记载,在此不再赘述。使用过程中,换料机构与堆芯燃料组件1的头部连接,换料机构通过控制堆芯燃料组件1来实现控制液态重金属反应堆的燃料组件锁紧装置,实现换料。本实施例的使用如上实施例的液态重金属反应堆的燃料组件锁紧装置进行燃料组件换料的方法,具体可以包括如下步骤:Fig. 5 is a flowchart of a method for refueling a fuel assembly using the fuel assembly locking device of the liquid heavy metal reactor in the above embodiment provided by an embodiment of the present invention. Wherein, the details of the fuel assembly locking device of the liquid heavy metal reactor can be found in the descriptions of the above-mentioned embodiments, and will not be repeated here. During use, the refueling mechanism is connected to the head of the core fuel assembly 1, and the refueling mechanism controls the fuel assembly locking device of the liquid heavy metal reactor by controlling the core fuel assembly 1 to realize refueling. The method for fuel assembly refueling using the fuel assembly locking device of the liquid heavy metal reactor of the above embodiment in this embodiment may specifically include the following steps:

100、当进行装料时,换料机构通过控制堆芯燃料组件1将燃料组件管脚4插入堆芯下栅板2中的安装孔,将固定套筒5连同固定凸台6滑入栅板导槽3,使得固定凸台6沿着栅板导槽3下平面旋转直至最底部;100. When charging, the refueling mechanism controls the core fuel assembly 1 to insert the fuel assembly pin 4 into the installation hole in the lower grid plate 2 of the core, and slide the fixing sleeve 5 together with the fixing boss 6 into the grid plate The guide groove 3 makes the fixed boss 6 rotate along the lower plane of the grid plate guide groove 3 to the bottom;

固定凸台6沿着栅板导槽3下平面旋转直至最底部的时候,堆芯燃料组件1向上运动的时候,比较容易和上面的导槽配合。101、换料机构拉动堆芯燃料组件1向上提升,使得固定凸台6沿着栅板导槽3上平面旋转至最顶部,并在此位置通过球与面的接触固定;When the fixed boss 6 rotates along the lower plane of the grid guide groove 3 to the bottom, when the core fuel assembly 1 moves upward, it is easier to cooperate with the upper guide groove. 101. The refueling mechanism pulls the core fuel assembly 1 upwards, so that the fixed boss 6 rotates along the upper plane of the grid guide groove 3 to the top, and fixes it at this position through the contact between the ball and the surface;

换料机构拉动堆芯燃料组件1向上提升,底部的固定凸台6跟随堆芯燃料组件1运动,从而可以使得固定凸台6沿着栅板导槽3上平面旋转至最顶部,并在此位置通过球与面的接触固定,该种接触,有利于防止长时间静止在堆芯中,结构钢材之间自焊效应。The refueling mechanism pulls the core fuel assembly 1 to lift upward, and the fixed boss 6 at the bottom follows the movement of the core fuel assembly 1, so that the fixed boss 6 can rotate to the top along the upper plane of the grid guide groove 3, and here The position is fixed by the contact between the ball and the surface. This kind of contact is beneficial to prevent the self-welding effect between the structural steels when standing still in the core for a long time.

102、当进行换料时,换料机构将堆芯燃料组件1再次下压,固定凸台6沿着栅板导槽3下平面旋转直至最底部后,换料机构向上提升,堆芯燃料组件1脱离堆芯下栅板2,实现换料。102. When refueling, the refueling mechanism presses down the core fuel assembly 1 again, and the fixed boss 6 rotates along the lower plane of the grid guide groove 3 to the bottom, then the refueling mechanism lifts up, and the core fuel assembly 1 is separated from the lower grid plate 2 of the core to realize refueling.

通过采用本实施例的换料方法,使非常方便,且液态重金属反应堆的燃料组件锁紧装置,能够多次使用,能够有效地降低换料成本。且液态重金属反应堆的燃料组件锁紧装置位于中子辐照较弱的位置,安全性高;还可以有效防止燃料元件在液态重金属堆中的窜动,并能够实现反应堆的在线换料。By adopting the refueling method of this embodiment, it is very convenient, and the fuel assembly locking device of the liquid heavy metal reactor can be used many times, which can effectively reduce the cost of refueling. Moreover, the fuel assembly locking device of the liquid heavy metal reactor is located at a position where the neutron irradiation is relatively weak, so the safety is high; it can also effectively prevent the fuel elements from moving in the liquid heavy metal reactor, and can realize online refueling of the reactor.

最后应说明的是:以上实施例仅用以说明本发明的技术方案,而非对其限制;尽管参照前述实施例对本发明进行了详细的说明,本领域的普通技术人员应当理解:其依然可以对前述各实施例所记载的技术方案进行修改,或者对其中部分技术特征进行等同替换;而这些修改或者替换,并不使相应技术方案的本质脱离本发明各实施例技术方案的精神和范围。Finally, it should be noted that: the above embodiments are only used to illustrate the technical solutions of the present invention, rather than to limit them; although the present invention has been described in detail with reference to the foregoing embodiments, those of ordinary skill in the art should understand that: it can still be Modifications are made to the technical solutions described in the foregoing embodiments, or equivalent replacements are made to some of the technical features; and these modifications or replacements do not make the essence of the corresponding technical solutions deviate from the spirit and scope of the technical solutions of the various embodiments of the present invention.

Claims (9)

1. the fuel assembly locking device of a liquid heavy metal reactor, it is characterized in that, described device comprises: reactor fuel assembly (1), reactor core lower grid plate (2), screen guide groove (3), fuel assembly pin (4), fixed muffle (5) and fixing lug boss (6);
Wherein, described reactor fuel assembly (1) is welded as a whole with described fuel assembly pin (4); Described fixed muffle (5) is axially fixed in the outside of described fuel assembly pin (4) by screw thread, and can rotate around the central shaft of described fuel assembly pin (4); Described fixing lug boss (6) is welded on the surface of described fixed muffle (5), described screen guide groove (3) is for being positioned at the hole of described reactor core lower grid plate (2), described fixing lug boss (6) coordinates with described screen guide groove (3), and described fuel assembly (1) is fixed on described reactor core lower grid plate (2).
2. device according to claim 1, is characterized in that, described reactor fuel assembly (1) is hexagon cylinder.
3. device according to claim 1, is characterized in that, described fuel assembly pin (4) is column type.
4. device according to claim 1, is characterized in that, described screen guide groove (3) is interior zigzag slot.
5. device according to claim 4, is characterized in that, the number of described fixing lug boss (6) is identical with the number of the interior zigzag slot of described screen guide groove (3).
6. device according to claim 5, is characterized in that, the number of the interior zigzag slot of the number of described fixing lug boss (6) and described screen guide groove (3) is three.
7. device according to claim 1, it is characterized in that, described fuel assembly pin (4) comprises the top (41) of described fuel assembly pin (4) and bottom (42) two parts of described fuel assembly pin (4), described fixed muffle (5) is inserted in the described top (41) of described fuel assembly pin (4), the described bottom (42) of described fuel assembly pin (4) is connected with the described top (41) of described fuel assembly pin (4) by screw thread, and described fixed muffle (5) is axially fixed on described fuel assembly pin (4).
8. device according to claim 7, is characterized in that, between described fuel assembly pin (4) and described fixed muffle (5), for circular cone, contacts with the line of circular arc.
9. use the as above fuel assembly locking device of the arbitrary described liquid heavy metal reactor of claim 1-9 to carry out the method that fuel assembly reloads, it is characterized in that, comprise the steps:
When carrying out when filling with substance, refueling agency inserts the mounting hole in described reactor core lower grid plate (2) by controlling described reactor fuel assembly (1) by described fuel assembly pin (4), described fixed muffle (5) is slipped into described screen guide groove (3) together with described fixing lug boss (6), make described fixing lug boss (6) along the rotation of described screen guide groove (3) lower plane until bottommost;
Refueling agency pulls described reactor fuel assembly (1) upwards to promote, and makes described fixing lug boss (6) along the upper Plane Rotation of described screen guide groove (3) to top, and fixes with contacting of face by ball in this position;
When reloading, refueling agency presses down described reactor fuel assembly (1) again, described fixing lug boss (6) is along the rotation of screen guide groove (3) lower plane until after bottommost, refueling agency upwards promotes, described reactor fuel assembly (1) departs from described reactor core lower grid plate (2), and realization is reloaded.
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CN106531233A (en) * 2016-12-29 2017-03-22 中国科学院合肥物质科学研究院 Reactor fuel assembly
CN106782682A (en) * 2016-12-30 2017-05-31 清华大学天津高端装备研究院 A kind of fuel assembly for lead bismuth heap
CN107767967A (en) * 2017-09-29 2018-03-06 中广核研究院有限公司 Fuel assembly lower locking mechanism and locking, unlocking method
CN108053905A (en) * 2017-12-18 2018-05-18 岭澳核电有限公司 Fuel assembly lower locking mechanism and locking, unlocking method
CN109767851A (en) * 2018-12-21 2019-05-17 中广核研究院有限公司 Fuel assembly lower locking mechanism and its locking, unlocking method
CN109767850A (en) * 2018-12-21 2019-05-17 中广核研究院有限公司 Fuel assembly lower locking mechanism and its application method
CN109841287A (en) * 2019-04-11 2019-06-04 哈尔滨工程大学 A kind of liquid fuel nuclear reactor for realizing work by inertia force
CN110600144A (en) * 2019-10-10 2019-12-20 中国科学院近代物理研究所 Lower pipe seat buoyancy locking mechanism of lead-based reactor fuel assembly
CN110600145A (en) * 2019-10-10 2019-12-20 中国科学院近代物理研究所 Locking, unlocking and grabbing lifting device for lead-based reactor fuel assembly
CN111477364A (en) * 2020-02-27 2020-07-31 中国原子能科学研究院 nuclear reactor components
CN111667928A (en) * 2020-06-19 2020-09-15 中国科学院近代物理研究所 A lead-based reactor fuel assembly locking structure
CN112837832A (en) * 2020-12-30 2021-05-25 中国原子能科学研究院 A special structure for rotary refueling for replacing the outer sleeve of the control rod assembly
CN112863715A (en) * 2020-12-30 2021-05-28 中国原子能科学研究院 Rotary type material changing special structure for replacing control rod assembly moving body
CN113436755A (en) * 2021-06-04 2021-09-24 中国原子能科学研究院 Pin throttling device and small grid plate header assembly
CN113871042A (en) * 2021-09-26 2021-12-31 中国原子能科学研究院 Replacing device for control rod assembly moving body
CN114147362A (en) * 2021-12-08 2022-03-08 西北有色金属研究院 Method for improving corrosion resistance of stainless steel pipe plate joint weld of space nuclear reactor container
WO2023077468A1 (en) * 2021-11-05 2023-05-11 中广核研究院有限公司 Fuel assembly locking device

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4684498A (en) * 1985-03-29 1987-08-04 Westinghouse Electric Corp. Guide thimble captured locking tube in a reconstitutable fuel assembly
EP0362005A1 (en) * 1988-09-19 1990-04-04 Framatome Method and device to extract locking sleeves from guide tubes of reconstituable nuclear reactor fuel assemblies
US5844958A (en) * 1993-12-30 1998-12-01 Framatome Dismountable fuel assembly of a nuclear reactor cooled by light water
CN101727993A (en) * 2008-10-24 2010-06-09 中国核动力研究设计院 Quick detachable joint of nuclear fuel assembly
CN103077756A (en) * 2013-01-13 2013-05-01 中国科学院合肥物质科学研究院 Clamp device of refueling machine for liquid heavy metal cooling pile
WO2013165496A2 (en) * 2012-04-16 2013-11-07 Babcock & Wilcox Nuclear Energy, Inc. Lower end fitting locknut for nuclear fuel assembly

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4684498A (en) * 1985-03-29 1987-08-04 Westinghouse Electric Corp. Guide thimble captured locking tube in a reconstitutable fuel assembly
EP0362005A1 (en) * 1988-09-19 1990-04-04 Framatome Method and device to extract locking sleeves from guide tubes of reconstituable nuclear reactor fuel assemblies
US5844958A (en) * 1993-12-30 1998-12-01 Framatome Dismountable fuel assembly of a nuclear reactor cooled by light water
CN101727993A (en) * 2008-10-24 2010-06-09 中国核动力研究设计院 Quick detachable joint of nuclear fuel assembly
WO2013165496A2 (en) * 2012-04-16 2013-11-07 Babcock & Wilcox Nuclear Energy, Inc. Lower end fitting locknut for nuclear fuel assembly
CN103077756A (en) * 2013-01-13 2013-05-01 中国科学院合肥物质科学研究院 Clamp device of refueling machine for liquid heavy metal cooling pile

Cited By (24)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106531233A (en) * 2016-12-29 2017-03-22 中国科学院合肥物质科学研究院 Reactor fuel assembly
CN106782682A (en) * 2016-12-30 2017-05-31 清华大学天津高端装备研究院 A kind of fuel assembly for lead bismuth heap
CN107767967A (en) * 2017-09-29 2018-03-06 中广核研究院有限公司 Fuel assembly lower locking mechanism and locking, unlocking method
CN107767967B (en) * 2017-09-29 2019-10-08 中广核研究院有限公司 Fuel assembly lower locking mechanism and locking, unlocking method
CN108053905A (en) * 2017-12-18 2018-05-18 岭澳核电有限公司 Fuel assembly lower locking mechanism and locking, unlocking method
CN109767851A (en) * 2018-12-21 2019-05-17 中广核研究院有限公司 Fuel assembly lower locking mechanism and its locking, unlocking method
CN109767850A (en) * 2018-12-21 2019-05-17 中广核研究院有限公司 Fuel assembly lower locking mechanism and its application method
CN109767851B (en) * 2018-12-21 2023-08-25 中广核研究院有限公司 Lower locking device of fuel assembly and locking and unlocking method thereof
CN109767850B (en) * 2018-12-21 2023-08-25 中广核研究院有限公司 Lower locking device of fuel assembly and using method thereof
CN109841287A (en) * 2019-04-11 2019-06-04 哈尔滨工程大学 A kind of liquid fuel nuclear reactor for realizing work by inertia force
CN110600145B (en) * 2019-10-10 2020-07-14 中国科学院近代物理研究所 A locking, unlocking and grabbing lifting device for lead-based reactor fuel assembly
CN110600145A (en) * 2019-10-10 2019-12-20 中国科学院近代物理研究所 Locking, unlocking and grabbing lifting device for lead-based reactor fuel assembly
CN110600144A (en) * 2019-10-10 2019-12-20 中国科学院近代物理研究所 Lower pipe seat buoyancy locking mechanism of lead-based reactor fuel assembly
CN111477364A (en) * 2020-02-27 2020-07-31 中国原子能科学研究院 nuclear reactor components
CN111667928A (en) * 2020-06-19 2020-09-15 中国科学院近代物理研究所 A lead-based reactor fuel assembly locking structure
CN112863715B (en) * 2020-12-30 2023-03-21 中国原子能科学研究院 Rotary type material changing special structure for replacing control rod assembly moving body
CN112863715A (en) * 2020-12-30 2021-05-28 中国原子能科学研究院 Rotary type material changing special structure for replacing control rod assembly moving body
CN112837832A (en) * 2020-12-30 2021-05-25 中国原子能科学研究院 A special structure for rotary refueling for replacing the outer sleeve of the control rod assembly
CN113436755A (en) * 2021-06-04 2021-09-24 中国原子能科学研究院 Pin throttling device and small grid plate header assembly
CN113436755B (en) * 2021-06-04 2024-02-20 中国原子能科学研究院 Pin throttling device and small grid plate header assembly
CN113871042A (en) * 2021-09-26 2021-12-31 中国原子能科学研究院 Replacing device for control rod assembly moving body
CN113871042B (en) * 2021-09-26 2023-12-12 中国原子能科学研究院 Material changing device for control rod assembly moving body
WO2023077468A1 (en) * 2021-11-05 2023-05-11 中广核研究院有限公司 Fuel assembly locking device
CN114147362A (en) * 2021-12-08 2022-03-08 西北有色金属研究院 Method for improving corrosion resistance of stainless steel pipe plate joint weld of space nuclear reactor container

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