CN108447573A - A nuclear reactor fuel rod melting visualization experiment device and method - Google Patents
A nuclear reactor fuel rod melting visualization experiment device and method Download PDFInfo
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- CN108447573A CN108447573A CN201810338609.8A CN201810338609A CN108447573A CN 108447573 A CN108447573 A CN 108447573A CN 201810338609 A CN201810338609 A CN 201810338609A CN 108447573 A CN108447573 A CN 108447573A
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- 238000000034 method Methods 0.000 title claims abstract description 24
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 19
- 238000002844 melting Methods 0.000 title claims description 71
- 230000008018 melting Effects 0.000 title claims description 71
- 238000002474 experimental method Methods 0.000 title claims description 14
- 238000012800 visualization Methods 0.000 title description 11
- 239000000446 fuel Substances 0.000 claims abstract description 38
- 239000000498 cooling water Substances 0.000 claims abstract description 27
- 238000001816 cooling Methods 0.000 claims abstract description 21
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 claims abstract description 18
- 229910052802 copper Inorganic materials 0.000 claims abstract description 18
- 239000010949 copper Substances 0.000 claims abstract description 18
- NZPGFUCQQUDSQG-UHFFFAOYSA-N [Mo].[Re] Chemical compound [Mo].[Re] NZPGFUCQQUDSQG-UHFFFAOYSA-N 0.000 claims abstract description 16
- 230000000007 visual effect Effects 0.000 claims abstract description 12
- 238000010438 heat treatment Methods 0.000 claims abstract description 11
- 238000003723 Smelting Methods 0.000 claims abstract 10
- 230000004927 fusion Effects 0.000 claims abstract 9
- 238000009738 saturating Methods 0.000 claims abstract 9
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 98
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims description 19
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 claims description 12
- 239000000155 melt Substances 0.000 claims description 12
- 238000012360 testing method Methods 0.000 claims description 9
- 229910052786 argon Inorganic materials 0.000 claims description 6
- 239000007789 gas Substances 0.000 claims description 5
- 239000000956 alloy Substances 0.000 claims description 4
- 229910045601 alloy Inorganic materials 0.000 claims description 4
- 239000011521 glass Substances 0.000 claims 3
- 229910052702 rhenium Inorganic materials 0.000 claims 2
- WUAPFZMCVAUBPE-UHFFFAOYSA-N rhenium atom Chemical compound [Re] WUAPFZMCVAUBPE-UHFFFAOYSA-N 0.000 claims 2
- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 claims 2
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims 1
- 238000002485 combustion reaction Methods 0.000 claims 1
- 239000010453 quartz Substances 0.000 claims 1
- 229910052726 zirconium Inorganic materials 0.000 claims 1
- 238000004088 simulation Methods 0.000 abstract description 5
- 238000012795 verification Methods 0.000 abstract description 5
- 238000004458 analytical method Methods 0.000 abstract description 4
- 230000036760 body temperature Effects 0.000 abstract 1
- DECCZIUVGMLHKQ-UHFFFAOYSA-N rhenium tungsten Chemical compound [W].[Re] DECCZIUVGMLHKQ-UHFFFAOYSA-N 0.000 description 13
- 239000011162 core material Substances 0.000 description 12
- 238000013508 migration Methods 0.000 description 8
- 230000005012 migration Effects 0.000 description 8
- 238000010309 melting process Methods 0.000 description 7
- 238000007789 sealing Methods 0.000 description 5
- 230000005855 radiation Effects 0.000 description 4
- 238000012546 transfer Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 239000012768 molten material Substances 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 230000005496 eutectics Effects 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 238000011160 research Methods 0.000 description 2
- 230000001052 transient effect Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 239000007769 metal material Substances 0.000 description 1
- 230000000116 mitigating effect Effects 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 238000007794 visualization technique Methods 0.000 description 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/08—Structural combination of reactor core or moderator structure with viewing means, e.g. with television camera, periscope, window
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- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Manufacture And Refinement Of Metals (AREA)
Abstract
Description
技术领域technical field
本发明涉及严重事故条件下可视化实验装置及方法,具体涉及一种核反应堆燃料棒熔化可视化实验装置及方法,属于实验测量可视化方法领域。The invention relates to a visualization experiment device and method under severe accident conditions, in particular to a nuclear reactor fuel rod melting visualization experiment device and method, and belongs to the field of experiment measurement visualization methods.
背景技术Background technique
反应堆的堆内材料会在到达自身熔点的情况下,会熔化成液态。而不同材料的共晶效应,则会进一步降低这一熔化温度。这些堆芯材料熔融物会通过向下流动,进入反应堆堆芯水平位置较低的位置,并有一定的概率会引起反应堆冷却剂流道的面积减小。而伴随着严重事故进一步的发展,堆芯熔化物持续在冷却剂流道内堆积,会导致部分燃料组件间的流道内出现堵塞现象,它会使堆芯冷却能力进一步下降,使反应堆严重事故继续恶化。如果得不到缓解的话,极有可能在反应堆内部出现局部熔穿,并导致整个上部的反应堆结构坍塌,进一步扩大堆芯的熔化区域。因此,严重事故条件下燃料棒熔化及熔融物迁徙行过程中发生的金属材料共晶现象,包壳氧化、破裂行为,熔融物壅塞等现象为严重事故序列中的重要环节,为后续堆内外反应堆严重事故进程提供源项。因此若能在燃料棒熔化期间采取及时的事故缓解措施将极大程度的削弱严重事故的危害,减少公众的生命财产安全。但是反应堆堆芯熔化是高温高压条件下一种非线性非连贯的复杂物理化学现象。这使得现象的研究与分析十分困难,传统的严重事故分析程序模拟在这一方面面临巨大挑战。因为现有的装置中无法观察到反应堆内部的燃料棒熔化的具体过程和现象,导致现有严重事故分析程序仅能对宏观集总参数进行模拟分析,无法准确描述严重事故进程及机理。The material in the reactor will melt into a liquid state when it reaches its own melting point. The eutectic effect of different materials will further reduce this melting temperature. These core material melts will flow downward and enter the lower horizontal position of the reactor core, and there is a certain probability that the area of the reactor coolant flow channel will be reduced. With the further development of severe accidents, core melts continue to accumulate in the coolant flow channels, which will lead to blockages in the flow channels between some fuel assemblies, which will further reduce the cooling capacity of the core and make the serious accident of the reactor continue to worsen. . If it is not relieved, it is very likely that a local meltthrough will occur inside the reactor and cause the entire upper reactor structure to collapse, further expanding the melted area of the core. Therefore, under severe accident conditions, the eutectic phenomenon of metal materials, cladding oxidation, cracking behavior, and melt clogging that occur during fuel rod melting and molten material migration are important links in the severe accident sequence, and they are important for subsequent internal and external reactors. The Severe Incident process provides source terms. Therefore, if timely accident mitigation measures can be taken during the melting of fuel rods, the harm of serious accidents will be greatly weakened and the safety of public life and property will be reduced. But reactor core melting is a nonlinear and incoherent complex physical and chemical phenomenon under the condition of high temperature and high pressure. This makes the research and analysis of the phenomenon very difficult, and the traditional severe accident analysis program simulation faces great challenges in this respect. Because the specific process and phenomenon of fuel rod melting inside the reactor cannot be observed in the existing device, the existing severe accident analysis program can only simulate and analyze the macroscopic lumped parameters, and cannot accurately describe the process and mechanism of the severe accident.
发明内容Contents of the invention
为解决上述问题,本发明的目的是提供一种核反应堆燃料棒熔化可视化实验装置及方法。In order to solve the above problems, the object of the present invention is to provide a nuclear reactor fuel rod melting visualization experimental device and method.
为实现上述目的,本发明采用如下的技术方案:To achieve the above object, the present invention adopts the following technical solutions:
一种核反应堆燃料棒熔化可视化实验装置,包括带有若干个透窗的高温熔融炉,高温熔融炉内竖直设置有试验件,试验件的上端和下端分别设置有铼钼电极,铼钼电极将试验件,铼钼电极与穿过高温熔融炉侧壁的铜电极相连,试验件包括燃料棒,燃料棒内设置有钨铼加热棒,高温熔融炉外侧设置有用于对高温熔融炉进行冷却的冷却水循环系统。A nuclear reactor fuel rod melting visualization experiment device includes a high-temperature melting furnace with several windows, a test piece is vertically arranged in the high-temperature melting furnace, rhenium-molybdenum electrodes are respectively arranged at the upper end and the lower end of the test piece, and the rhenium-molybdenum electrodes connect The test piece, the rhenium-molybdenum electrode is connected with the copper electrode passing through the side wall of the high-temperature melting furnace, the test piece includes a fuel rod, and a tungsten-rhenium heating rod is arranged inside the fuel rod, and a cooling device for cooling the high-temperature melting furnace is arranged outside the high-temperature melting furnace water circulatory system.
本发明进一步的改进在于,高温熔融炉的顶部设置有上炉盖,底部设置有下炉盖,上炉盖与液压机相连,下炉盖与叉车相连,上炉盖由液压机控制升降,下炉盖由叉车控制升降。The further improvement of the present invention is that the top of the high-temperature melting furnace is provided with an upper furnace cover, and the bottom is provided with a lower furnace cover, the upper furnace cover is connected with a hydraulic press, the lower furnace cover is connected with a forklift, the upper furnace cover is controlled by a hydraulic Lifting is controlled by a forklift.
本发明进一步的改进在于,燃料棒下方设置有坩埚,坩埚设置在下炉盖上;穿过高温熔融炉侧壁,在不同高度设置有6个钨铼热电偶,用于测量燃料棒的温度。The further improvement of the present invention is that a crucible is arranged under the fuel rod, and the crucible is arranged on the lower furnace cover; through the side wall of the high-temperature melting furnace, six tungsten-rhenium thermocouples are arranged at different heights for measuring the temperature of the fuel rod.
本发明进一步的改进在于,高温熔融炉的炉体侧壁上开设有6个透窗,6个透窗沿炉体侧壁螺旋式上升排布,在周向上均匀分布。The further improvement of the present invention lies in that the side wall of the furnace body of the high-temperature melting furnace is provided with 6 through windows, and the 6 through windows are spirally arranged along the side wall of the furnace body and evenly distributed in the circumferential direction.
本发明进一步的改进在于,相邻两个透窗在竖直方向的距离为0.16m;透窗呈圆台型,透窗的顶面开口处的直径为25mm,底面开口处的直径为74mm。The further improvement of the present invention is that the vertical distance between two adjacent through windows is 0.16m; the through windows are in the shape of a truncated cone, the diameter of the top opening of the through window is 25mm, and the diameter of the bottom opening is 74mm.
本发明进一步的改进在于,透窗处的高温熔融炉侧壁上设置有圆形盖板,圆形盖板与高温熔融炉侧壁上之间设置有石英玻璃,圆形盖板上开设有圆孔。The further improvement of the present invention is that a circular cover plate is provided on the side wall of the high-temperature melting furnace at the window, quartz glass is provided between the circular cover plate and the side wall of the high-temperature melting furnace, and a circular cover plate is provided on the circular cover plate. hole.
本发明进一步的改进在于,圆形盖板通过螺钉固定在高温熔融炉的侧壁上,石英玻璃为圆柱状,圆形盖板和石英玻璃9之间设置有O型密封圈,石英玻璃的侧壁上设置有矩形密封圈。The further improvement of the present invention is that the circular cover plate is fixed on the side wall of the high-temperature melting furnace by screws, the quartz glass is cylindrical, an O-shaped sealing ring is arranged between the circular cover plate and the quartz glass 9, and the side wall of the quartz glass A rectangular sealing ring is arranged on the wall.
本发明进一步的改进在于,石英玻璃的直径为40mm。A further improvement of the present invention is that the diameter of the quartz glass is 40 mm.
本发明进一步的改进在于,冷却水循环系统包括水箱,上炉盖上设置有管道,高温熔融炉体侧壁上设置有管道,下炉盖上设置有管道,铜电极上设置有管道;水箱出口与水泵入口相连,水泵出口与五路分水器相连,五路分水器的出口分别与上炉盖上的管道入口、高温熔融炉体侧壁上的管道入口、下炉盖上的管道入口、铜电极上的管道入口以及罗茨泵入口相连,上炉盖上的管道出口、高温熔融炉体侧壁上的管道出口、下炉盖上的管道出口、铜电极上的管道出口以及罗茨泵出口均与集水器入口相连,集水器出口与水箱入口相连;水箱内设置有水位计,水箱上方设置有冷却塔,水箱内设置有提升泵,提升泵出口与冷却塔相连。The further improvement of the present invention is that the cooling water circulation system includes a water tank, pipes are provided on the upper furnace cover, pipes are provided on the side wall of the high-temperature melting furnace body, pipes are provided on the lower furnace cover, and pipes are provided on the copper electrodes; the outlet of the water tank is connected to the The inlet of the water pump is connected, and the outlet of the water pump is connected with the five-way water separator. The pipeline inlet on the copper electrode is connected to the Roots pump inlet, the pipeline outlet on the upper furnace cover, the pipeline outlet on the side wall of the high-temperature melting furnace body, the pipeline outlet on the lower furnace cover, the pipeline outlet on the copper electrode and the Roots pump The outlets are all connected to the inlet of the water collector, and the outlet of the water collector is connected to the inlet of the water tank; a water level gauge is installed in the water tank, a cooling tower is installed above the water tank, a lifting pump is installed in the water tank, and the outlet of the lifting pump is connected to the cooling tower.
一种实验方法,开启给水泵和提升泵,给水泵位于水箱外部并与五路分水器相连,将水箱中的冷却水送至五路分水器后分别流向对应的实验设备,冷却水冷却对应实验设备后汇聚至集水器中,集水器与水箱相连,冷却水最终流回水箱;提升泵位于水箱底部,将水箱中的水提升至高处的冷却塔,冷却水经过空气冷却后流回至水箱中;随后对高温熔融炉内抽真空,当高温熔融炉内真空度达到设定值后通入氩气,氩气从炉底通入至高温熔融炉内直至高温熔融炉内压力达到1.2MPa,交流电通过水冷铜电极和铼钼电极,流入钨铼加热棒对燃料棒进行电加热;高速摄像仪透过炉壁透窗实时拍摄炉内燃料棒熔化及迁徙动态过程并保存,钨铼热电偶测量燃料棒外表面锆-4合金的温度并保存。An experimental method. Turn on the feedwater pump and the lifting pump. The feedwater pump is located outside the water tank and connected to the five-way water distributor. The cooling water in the water tank is sent to the five-way water distributor and then flows to the corresponding experimental equipment respectively. The cooling water is cooled. Corresponding to the experimental equipment, it is collected into the water collector, and the water collector is connected with the water tank, and the cooling water finally flows back to the water tank; the lifting pump is located at the bottom of the water tank, and lifts the water in the water tank to the high cooling tower, and the cooling water flows after being cooled by air. Return to the water tank; then vacuumize the high-temperature melting furnace, and when the vacuum degree in the high-temperature melting furnace reaches the set value, argon gas is introduced, and the argon gas is passed into the high-temperature melting furnace from the bottom of the furnace until the pressure in the high-temperature melting furnace reaches 1.2MPa, the alternating current passes through the water-cooled copper electrode and rhenium-molybdenum electrode, and flows into the tungsten-rhenium heating rod to electrically heat the fuel rod; the high-speed camera captures the melting and migration dynamic process of the fuel rod in the furnace through the window of the furnace wall and saves it in real time, and the tungsten-rhenium A thermocouple measures the temperature of the zirconium-4 alloy on the outer surface of the fuel rod and saves it.
与现有技术相比,本发明具有以下有益效果:Compared with the prior art, the present invention has the following beneficial effects:
本发明的实验装置通过在高温熔融炉上开设透窗,可以在透窗外设置高速摄像仪,通过高速摄像仪观察高温熔融炉内实验情况,克服了现有装置中无法观察燃料棒熔化的具体过程的问题,由于炉外有高速摄像仪存在,因此需要对整个实验装置进行冷却。因此本发明中增设了冷却水循环系统,本发明的实验装置结构简单,能够实现,并能可视化地揭示堆芯材料熔化及熔融物的迁徙瞬态行为特性,获得可视化图像数据可为传统数值模拟方法提供验证。本发明有助于掌握关键现象机理,降低堆芯熔化进程的不确定性。The experimental device of the present invention provides a transparent window on the high-temperature melting furnace, and a high-speed camera can be arranged outside the transparent window to observe the experimental situation in the high-temperature melting furnace through the high-speed camera, which overcomes the inability to observe the specific process of fuel rod melting in the existing device Due to the presence of a high-speed camera outside the furnace, the entire experimental device needs to be cooled. Therefore, a cooling water circulation system is added in the present invention. The experimental device of the present invention is simple in structure, can be realized, and can visually reveal the melting of the core material and the transient behavior characteristics of the migration of the melt, and obtaining visual image data can be a traditional numerical simulation method. Provide verification. The invention helps to grasp the mechanism of key phenomena and reduces the uncertainty of the core melting process.
进一步的,由液压机控制上炉盖的升降,由叉车控制下炉盖的升降,利于控制。Further, the lifting of the upper furnace cover is controlled by a hydraulic machine, and the lifting of the lower furnace cover is controlled by a forklift, which is convenient for control.
进一步的,6个透窗沿炉体侧壁螺旋式上升排布,在周向上均匀分布,利于观察不同角度的燃料棒的熔化情况。Furthermore, the six through windows are spirally arranged along the side wall of the furnace body, and are evenly distributed in the circumferential direction, which is beneficial to observe the melting conditions of the fuel rods at different angles.
进一步的,由于反应堆燃料棒将在2000℃以上的高温条件下熔化,因此透窗表面会受到较大的辐射传热量。透窗面积过大将导致其表面温度过高而遭到损坏。另一方面,透窗面积过小将导致观测视角很小,无法记录整个燃料棒的熔化过程。综合考虑,可视化实验装置采用了圆台型透窗,设置透窗的顶面开口处的直径为25mm,底面开口处的直径为74mm。通过本发明的圆台型透窗可以实现燃料棒熔化迁徙的动态记录。Furthermore, since the reactor fuel rods will be melted under high temperature conditions above 2000° C., the surface of the window will be subjected to a large amount of heat transfer by radiation. Excessive window area will cause its surface temperature to be too high and be damaged. On the other hand, if the area of the window is too small, the viewing angle will be too small to record the melting process of the entire fuel rod. Considering comprehensively, the visualization experiment device adopts a circular frustum-shaped transparent window. The diameter of the top opening of the transparent window is 25mm, and the diameter of the bottom opening is 74mm. The dynamic recording of fuel rod melting and migration can be realized through the frustum-shaped window of the invention.
进一步的,石英玻璃尺寸较小以减少辐射传热量,降低石英玻璃的表面温度,所以,本发明中石英玻璃的直径为40mm。炉体上开设有圆台型透窗以增大观测视角。高温熔融炉外的高速摄像仪透过炉壁的圆台型透窗可现实时记录燃料棒熔化进程。Further, the size of the quartz glass is small to reduce the radiation heat transfer and reduce the surface temperature of the quartz glass, so the diameter of the quartz glass in the present invention is 40mm. The furnace body is equipped with a circular platform-shaped transparent window to increase the viewing angle. The high-speed camera outside the high-temperature melting furnace can record the melting process of fuel rods in real time through the circular frustum-shaped window on the furnace wall.
通过高温熔融炉冷却水循环系统保证炉体外侧温度保持在安全限制以内,外部的高速摄像仪可以正常工作,本方法能够真实模拟反应堆严重事故条件下堆芯熔化进程。本发明中的实验温度高达2000℃以上,本发明获得的实验数据可为传统数值模拟方法提供验证,降低现有严重事故分析程序的不确定性。由于公开文献中获得的实验数据无法满足我国对反应堆严重事故程序自主化需求,采用本发明的实验方法,进行堆芯材料熔化及熔融材料迁移特性研究,对于我国的核能科学与工程专业的发展,对反应堆严重事故进程及机理研究,具体极其重要的意义。The cooling water circulation system of the high-temperature melting furnace ensures that the temperature outside the furnace body is kept within the safety limit, and the external high-speed camera can work normally. This method can truly simulate the core melting process under severe reactor accident conditions. The experimental temperature in the present invention is as high as above 2000°C, and the experimental data obtained in the present invention can provide verification for traditional numerical simulation methods and reduce the uncertainty of existing severe accident analysis procedures. Since the experimental data obtained in the open literature cannot meet my country's demand for autonomy in severe accident procedures for reactors, the experimental method of the present invention is used to conduct research on the melting of core materials and the migration characteristics of molten materials. For the development of nuclear energy science and engineering in my country, It is extremely important to study the process and mechanism of severe reactor accidents.
附图说明Description of drawings
图1为高温熔融炉实验装置三维简图。Figure 1 is a three-dimensional schematic diagram of the experimental device of the high-temperature melting furnace.
图2为圆台型透窗示意图。Figure 2 is a schematic diagram of a frustum-shaped through window.
图3为本发明的核反应堆燃料棒熔化可视化实验装置的结构示意图。Fig. 3 is a structural schematic diagram of the nuclear reactor fuel rod melting visualization experimental device of the present invention.
图中,1为控制柜,2为罗茨泵,3为滑阀泵,4为阶梯,5为支撑架,6为高温熔融炉,7为叉车,8为液压机,9为石英玻璃,10为矩形密封圈,11为螺钉,12为O型密封圈,13为真空管,14为真空阀,15为真空规管,16为上炉盖,17为下炉盖,18为炉体侧壁,19为透窗,20为钨铼热电偶,21为铜电极,22为铼钼电极,23为坩埚,24为钨铼加热棒,25为燃料棒,26为给水泵,27为提升泵,28为冷却塔,29为水位计,30为水箱,31为分水器,32为集水器,33为水源,34为补水阀。In the figure, 1 is the control cabinet, 2 is the Roots pump, 3 is the sliding valve pump, 4 is the ladder, 5 is the support frame, 6 is the high temperature melting furnace, 7 is the forklift, 8 is the hydraulic machine, 9 is the quartz glass, 10 is the Rectangular sealing ring, 11 is a screw, 12 is an O-ring, 13 is a vacuum tube, 14 is a vacuum valve, 15 is a vacuum gauge, 16 is an upper furnace cover, 17 is a lower furnace cover, 18 is a furnace side wall, 19 20 is a tungsten-rhenium thermocouple, 21 is a copper electrode, 22 is a rhenium-molybdenum electrode, 23 is a crucible, 24 is a tungsten-rhenium heating rod, 25 is a fuel rod, 26 is a water supply pump, 27 is a lift pump, and 28 is a Cooling tower, 29 is a water level gauge, 30 is a water tank, 31 is a water distributor, 32 is a water collector, 33 is a water source, and 34 is a replenishment valve.
具体实施方式Detailed ways
下面通过附图对本发明进行详细描述。The present invention will be described in detail below by means of the accompanying drawings.
参见图1、图2和图3,本发明的可视化实验方法主要通过六个梯形水冷透窗和高温熔融炉冷却水循环系统实现。本发明的实验方法能可视化地揭示堆芯材料熔化及熔融物的迁徙瞬态行为特性,获得可视化图像数据可为传统数值模拟方法提供验证。本发明有助于掌握关键现象机理,降低堆芯熔化进程的不确定性。Referring to Fig. 1, Fig. 2 and Fig. 3, the visualization experiment method of the present invention is mainly realized through six trapezoidal water-cooling windows and the cooling water circulation system of the high-temperature melting furnace. The experimental method of the invention can visually reveal the melting of the core material and the migration transient behavior characteristics of the molten material, and the obtained visual image data can provide verification for the traditional numerical simulation method. The invention helps to grasp the mechanism of key phenomena and reduces the uncertainty of the core melting process.
本发明的核反应堆燃料棒熔化可视化实验装置如图1所示。核反应堆燃料棒熔化可视化实验装置包括带有若干个透窗的高温熔融6,高温熔融炉6内竖直设置有试验件,试验件的上端和下端分别设置有铼钼电极22,铼钼电极22用于夹持试验件并导电,铼钼电极22与穿过高温熔融炉侧壁的铜电极21相连,试验件包括设置在中心的钨铼加热棒24,钨铼加热棒24的外侧设置有燃料棒25,燃料棒25将钨铼加热棒24包裹,即钨铼加热棒24位于燃料棒25的中心,燃料棒外表面为锆-4合金。高温熔融炉的顶部设置有上炉盖16,底部设置有下炉盖17,上炉盖16与液压机8相连,下炉盖17与叉车7相连,上炉盖16由液压机8控制升降,下炉盖17由叉车7控制升降。The nuclear reactor fuel rod melting visualization experimental device of the present invention is shown in FIG. 1 . The nuclear reactor fuel rod melting visualization experimental device includes a high-temperature melting furnace 6 with several windows. A test piece is vertically arranged in the high-temperature melting furnace 6. The upper and lower ends of the test piece are respectively provided with rhenium-molybdenum electrodes 22. The rhenium-molybdenum electrodes 22 are used To clamp the test piece and conduct electricity, the rhenium-molybdenum electrode 22 is connected to the copper electrode 21 passing through the side wall of the high-temperature melting furnace. The test piece includes a tungsten-rhenium heating rod 24 arranged in the center, and a fuel rod is arranged on the outside of the tungsten-rhenium heating rod 24 25. The fuel rod 25 wraps the tungsten-rhenium heating rod 24, that is, the tungsten-rhenium heating rod 24 is located at the center of the fuel rod 25, and the outer surface of the fuel rod is zirconium-4 alloy. The top of the high-temperature melting furnace is provided with an upper furnace cover 16, and the bottom is provided with a lower furnace cover 17. The upper furnace cover 16 is connected with the hydraulic press 8, and the lower furnace cover 17 is connected with the forklift 7. The upper furnace cover 16 is controlled by the hydraulic press 8. Cover 17 is lifted and lowered by forklift 7 control.
燃料棒25下方设置有坩埚23,坩埚23设置在下炉盖17上。穿过高温熔融炉侧壁在不同高度设置有6个钨铼热电偶20,用于测量燃料棒25的温度。A crucible 23 is arranged below the fuel rod 25 , and the crucible 23 is arranged on the lower furnace cover 17 . Six tungsten-rhenium thermocouples 20 are arranged at different heights through the side wall of the high-temperature melting furnace for measuring the temperature of the fuel rod 25 .
高温熔融炉6的炉体侧壁18上开设有6个透窗21,6个透窗沿炉体侧壁螺旋式上升排布,在周向上均匀分布,相邻两个透窗在竖直方向的距离为0.16m。由于反应堆燃料棒将在2000℃以上的高温条件下熔化,因此透窗表面会受到较大的辐射传热量。透窗面积过大将导致其表面温度过高而遭到损坏。另一方面,透窗面积过小将导致观测视角很小,无法记录整个燃料棒的熔化过程。综合考虑,可视化实验装置采用了圆台型透窗,设置透窗的顶面开口处的直径为25mm,底面开口处的直径为74mm。The furnace side wall 18 of the high-temperature melting furnace 6 is provided with 6 through windows 21, and the 6 through windows are spirally arranged along the side wall of the furnace body, and are evenly distributed in the circumferential direction. The distance is 0.16m. Because the reactor fuel rods will be melted under high temperature conditions above 2000°C, the surface of the window will be subjected to a large amount of radiation heat transfer. Excessive window area will cause its surface temperature to be too high and be damaged. On the other hand, if the area of the window is too small, the viewing angle will be too small to record the melting process of the entire fuel rod. Considering comprehensively, the visualization experiment device adopts a circular frustum-shaped transparent window. The diameter of the top opening of the transparent window is 25mm, and the diameter of the bottom opening is 74mm.
圆台型透窗如图2所示。透窗入口处设置在高温熔融炉6侧壁上的开设有圆孔的圆形盖板,圆形盖板上沿周向均匀分布着6个螺钉11,将圆形盖板与高温熔融炉侧壁通过螺钉相连。圆形盖板和高温熔融炉6侧壁之间设置有圆柱状的石英玻璃9,并且圆形盖板和石英玻璃9之间设置有O型密封圈12,石英玻璃9的侧壁上设置有矩形密封圈10,同时保证装置的密闭性。石英玻璃的直径为40mm,尺寸较小以减少辐射传热量,降低石英玻璃的表面温度,石英玻璃内的炉体开设有圆台型透窗以增大观测视角。高温熔融炉外的高速摄像仪透过炉壁的圆台型透窗可现实时记录燃料棒熔化进程。由于炉外有高速摄像仪存在,因此需要对整个实验装置进行冷却。The frustum-shaped window is shown in Figure 2. The window entrance is provided with a circular cover plate with a round hole on the side wall of the high-temperature melting furnace 6, and 6 screws 11 are evenly distributed along the circumference on the circular cover plate, and the circular cover plate is connected to the side wall of the high-temperature melting furnace. The walls are connected by screws. A cylindrical quartz glass 9 is arranged between the circular cover plate and the side wall of the high-temperature melting furnace 6, and an O-shaped sealing ring 12 is arranged between the circular cover plate and the quartz glass 9, and the side wall of the quartz glass 9 is provided with The rectangular sealing ring 10 ensures the airtightness of the device at the same time. The diameter of the quartz glass is 40mm, and the size is small to reduce the heat transfer of radiation and reduce the surface temperature of the quartz glass. The furnace body inside the quartz glass is provided with a circular frustum-shaped window to increase the viewing angle. The high-speed camera outside the high-temperature melting furnace can record the melting process of fuel rods in real time through the circular frustum-shaped window on the furnace wall. Since there is a high-speed camera outside the furnace, the entire experimental device needs to be cooled.
高温熔融炉6的冷却水循环系统如图3所示。冷却水循环系统包括水箱30,上炉盖16上设置有管道,高温熔融炉体侧壁上设置有管道,下炉盖17上设置有管道,铜电极21上设置有管道;水箱30与水泵28入口相连,水泵28出口与五路分水器31相连,五路分水器31的出口分别与上炉盖上的管道入口、高温熔融炉体侧壁上的管道入口、下炉盖17上的管道入口、铜电极21上的管道入口以及罗茨泵2入口相连,上炉盖16上的管道出口、高温熔融炉体侧壁上的管道出口、下炉盖17上的管道出口、铜电极21上的管道出口以及罗茨泵2出口均与集水器32入口相连,集水器32出口与水箱30相连。The cooling water circulation system of the high-temperature melting furnace 6 is shown in FIG. 3 . The cooling water circulation system includes a water tank 30, a pipeline is provided on the upper furnace cover 16, a pipeline is provided on the side wall of the high-temperature melting furnace body, a pipeline is provided on the lower furnace cover 17, and a pipeline is provided on the copper electrode 21; the water tank 30 and the water pump 28 inlet The outlet of the water pump 28 is connected to the five-way water separator 31, and the outlet of the five-way water separator 31 is respectively connected to the pipeline inlet on the upper furnace cover, the pipeline inlet on the side wall of the high-temperature melting furnace body, and the pipeline on the lower furnace cover 17. The inlet, the pipeline inlet on the copper electrode 21 and the Roots pump 2 inlet are connected, the pipeline outlet on the upper furnace cover 16, the pipeline outlet on the side wall of the high-temperature melting furnace body, the pipeline outlet on the lower furnace cover 17, and the copper electrode 21. The outlet of the pipeline and the Roots pump 2 outlet are all connected to the inlet of the water collector 32, and the outlet of the water collector 32 is connected to the water tank 30.
水箱30内设置有水位计29,水箱30上方设置有冷却塔28,水箱30内设置有提升泵27,提升泵27出口与冷却塔28相连;水箱30中的循环冷却水由给水泵26驱动送至五路分水器31中,分别流向上炉盖16、炉体侧壁、罗茨泵2、铜电极21和下炉盖17。冷却水冷却对应实验设备后汇聚至集水器32中,最终流回水箱30。实验时,冷却水循环系统将实时输出进、出口水温和水箱水位,若进、出口水温超过限值或水箱的水位低于限值,都将启动补水阀34对水箱30补充水源33,水源33与水箱30之间设置有补水阀34。另一方面,水箱30中的水由提升泵27提升至高处的冷却塔28,冷却水经过空气冷却后流回至水箱30中。冷却水循环系统保证燃料棒在2000℃以上的高温条件下的实验设备的安全。通过本发明的圆台型透窗可以实现燃料棒熔化迁徙的动态记录,本发明获得的实验数据可为传统数值模拟方法提供验证,降低现有严重事故分析程序的不确定性。A water level gauge 29 is arranged in the water tank 30, a cooling tower 28 is arranged above the water tank 30, a lifting pump 27 is arranged in the water tank 30, and the outlet of the lifting pump 27 is connected with the cooling tower 28; Into the five-way water separator 31, it flows into the upper furnace cover 16, the side wall of the furnace body, the Roots pump 2, the copper electrode 21 and the lower furnace cover 17 respectively. The cooling water is collected into the water collector 32 after cooling the corresponding experimental equipment, and finally flows back to the water tank 30 . During the experiment, the cooling water circulation system will output the inlet and outlet water temperatures and the water level of the water tank in real time. If the inlet and outlet water temperatures exceed the limit value or the water level of the water tank is lower than the limit value, the replenishment valve 34 will be activated to replenish the water source 33 to the water tank 30. The water source 33 and A replenishment valve 34 is arranged between the water tanks 30 . On the other hand, the water in the water tank 30 is lifted to the high cooling tower 28 by the lift pump 27 , and the cooling water flows back into the water tank 30 after being air-cooled. The cooling water circulation system ensures the safety of experimental equipment for fuel rods under high temperature conditions above 2000°C. The frustum-shaped window of the invention can realize the dynamic recording of fuel rod melting and migration, and the experimental data obtained by the invention can provide verification for traditional numerical simulation methods and reduce the uncertainty of existing serious accident analysis procedures.
罗茨泵2一侧与控制柜1相连,罗茨泵2另一侧与滑阀泵3相连,罗茨泵2经与真空管13与高温熔融炉内部相连,真空管13上设置有真空阀14以及真空规管15。One side of the Roots pump 2 is connected to the control cabinet 1, and the other side of the Roots pump 2 is connected to the slide valve pump 3. The Roots pump 2 is connected to the interior of the high-temperature melting furnace through a vacuum tube 13. The vacuum tube 13 is provided with a vacuum valve 14 and Vacuum gauge15.
高温熔融炉外部设置有支撑架5,支撑架5一侧设置有阶梯4。A support frame 5 is provided outside the high-temperature melting furnace, and a step 4 is provided on one side of the support frame 5 .
实验时,启动冷却水循环系统的给水泵26和提升泵27,给水泵26位于水箱30外部并与五路分水器31相连,将水箱30中的冷却水送至五路分水器31后分别流向对应的实验设备,冷却水冷却对应实验设备后汇聚至五路集水器33中,五路集水器33与水箱30相连,冷却水最终流回水箱30。提升泵27位于水箱30底部,将水箱30中的水提升至高处的冷却塔28,冷却水经过空气冷却后流回至水箱30中。随后启动滑阀泵3和罗茨泵2,滑阀泵3和罗茨泵2通过真空管道15与高温熔融炉内腔相连,对高温熔融炉抽真空,当高温熔融炉内真空度达到设定值后氩气系统随之启动。恒定流量的氩气从炉底通入至高温熔融炉内直至炉内压力达到1.2MPa。随后交流电通过水冷铜电极21和铼钼电极34,流入钨铼加热棒24对燃料棒25进行电加热。高速摄像仪透过炉壁透窗实时拍摄炉内燃料棒熔化及迁徙动态过程并保存,钨铼热电偶20测量燃料棒外表面锆-4合金的温度并保存。During the experiment, start the feed water pump 26 and the lifting pump 27 of the cooling water circulation system, the feed water pump 26 is located outside the water tank 30 and is connected with the five-way water separator 31, and the cooling water in the water tank 30 is sent to the five-way water separator 31, respectively Flowing to the corresponding experimental equipment, the cooling water cools the corresponding experimental equipment and converges into the five-way water collector 33 , the five-way water collector 33 is connected to the water tank 30 , and the cooling water finally flows back to the water tank 30 . The lifting pump 27 is located at the bottom of the water tank 30 , and lifts the water in the water tank 30 to the cooling tower 28 at a high place, and the cooling water flows back into the water tank 30 after being air-cooled. Then start the slide valve pump 3 and the Roots pump 2, the slide valve pump 3 and the Roots pump 2 are connected to the inner cavity of the high-temperature melting furnace through the vacuum pipeline 15, and the high-temperature melting furnace is evacuated. When the vacuum degree in the high-temperature melting furnace reaches the set After the value is set, the argon system starts up. A constant flow of argon gas is passed into the high-temperature melting furnace from the bottom of the furnace until the pressure in the furnace reaches 1.2 MPa. Then the alternating current passes through the water-cooled copper electrode 21 and the rhenium-molybdenum electrode 34 , and flows into the tungsten-rhenium heating rod 24 to electrically heat the fuel rod 25 . The high-speed camera shoots and saves the melting and migration dynamic process of the fuel rods in the furnace in real time through the windows of the furnace wall, and the tungsten-rhenium thermocouple 20 measures and saves the temperature of the zirconium-4 alloy on the outer surface of the fuel rods.
以上内容是结合具体的优选实施方式对本发明所作的进一步详细说明,不能认定本发明的具体实施方式仅限于此,对于本发明所属技术领域的普通技术人员来说,在不脱离本发明构思的前提下,还可以做出若干简单的推演或替换,都应当视为属于本发明由所提交的权利要求书确定专利保护范围。The above content is a further detailed description of the present invention in conjunction with specific preferred embodiments. It cannot be determined that the specific embodiments of the present invention are limited thereto. Under the circumstances, some simple deduction or replacement can also be made, all of which should be regarded as belonging to the scope of patent protection determined by the submitted claims of the present invention.
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Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US9056263B2 (en) * | 2010-05-25 | 2015-06-16 | Northwestern University | Chalcogenide compounds for the remediation of nuclear and heavy metal wastes |
CN105911087A (en) * | 2016-06-01 | 2016-08-31 | 西安交通大学 | Large nuclear reactor molten pool natural-convection heat transfer test system and method |
CN106525895A (en) * | 2016-11-11 | 2017-03-22 | 西安交通大学 | Device and method for high temperature melt growth choking experiment |
CN107331425A (en) * | 2017-07-07 | 2017-11-07 | 西安交通大学 | A kind of fused mass and the pilot system and method for liquid metal repercussion study |
CN107393607A (en) * | 2017-07-07 | 2017-11-24 | 西安交通大学 | Reactor core fused mass and concrete reaction test system and method |
-
2018
- 2018-04-16 CN CN201810338609.8A patent/CN108447573B/en active Active
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US9056263B2 (en) * | 2010-05-25 | 2015-06-16 | Northwestern University | Chalcogenide compounds for the remediation of nuclear and heavy metal wastes |
CN105911087A (en) * | 2016-06-01 | 2016-08-31 | 西安交通大学 | Large nuclear reactor molten pool natural-convection heat transfer test system and method |
CN106525895A (en) * | 2016-11-11 | 2017-03-22 | 西安交通大学 | Device and method for high temperature melt growth choking experiment |
CN107331425A (en) * | 2017-07-07 | 2017-11-07 | 西安交通大学 | A kind of fused mass and the pilot system and method for liquid metal repercussion study |
CN107393607A (en) * | 2017-07-07 | 2017-11-24 | 西安交通大学 | Reactor core fused mass and concrete reaction test system and method |
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