CN105575447B - Experimental device for assessing nuclear fuel cladding pipe performance under simulated LOCA working condition - Google Patents
Experimental device for assessing nuclear fuel cladding pipe performance under simulated LOCA working condition Download PDFInfo
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- 238000005253 cladding Methods 0.000 title claims abstract description 68
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 57
- 238000010438 heat treatment Methods 0.000 claims abstract description 38
- 229910052751 metal Inorganic materials 0.000 claims abstract description 29
- 239000002184 metal Substances 0.000 claims abstract description 29
- 238000010791 quenching Methods 0.000 claims abstract description 29
- 230000000171 quenching effect Effects 0.000 claims abstract description 29
- 238000007789 sealing Methods 0.000 claims abstract description 14
- 238000011156 evaluation Methods 0.000 claims abstract 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 14
- 239000000463 material Substances 0.000 claims description 11
- 230000008602 contraction Effects 0.000 claims description 10
- 239000007788 liquid Substances 0.000 claims description 9
- 238000002955 isolation Methods 0.000 claims description 8
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 3
- 239000000919 ceramic Substances 0.000 claims description 3
- 229910002804 graphite Inorganic materials 0.000 claims description 3
- 239000010439 graphite Substances 0.000 claims description 3
- 239000010453 quartz Substances 0.000 claims description 3
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N silicon dioxide Inorganic materials O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims description 3
- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 claims description 3
- 229910052721 tungsten Inorganic materials 0.000 claims description 3
- 239000010937 tungsten Substances 0.000 claims description 3
- 229910052580 B4C Inorganic materials 0.000 claims description 2
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims description 2
- 230000001681 protective effect Effects 0.000 claims description 2
- 238000004804 winding Methods 0.000 claims 1
- 239000000446 fuel Substances 0.000 abstract description 9
- 238000005452 bending Methods 0.000 abstract description 7
- 239000007789 gas Substances 0.000 description 9
- 238000000034 method Methods 0.000 description 5
- 239000002826 coolant Substances 0.000 description 4
- 238000012360 testing method Methods 0.000 description 4
- 238000009529 body temperature measurement Methods 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- 230000004992 fission Effects 0.000 description 3
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 2
- 238000005260 corrosion Methods 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 230000003628 erosive effect Effects 0.000 description 2
- 239000001257 hydrogen Substances 0.000 description 2
- 229910052739 hydrogen Inorganic materials 0.000 description 2
- 239000010410 layer Substances 0.000 description 2
- 230000003647 oxidation Effects 0.000 description 2
- 238000007254 oxidation reaction Methods 0.000 description 2
- 239000008188 pellet Substances 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 229910001093 Zr alloy Inorganic materials 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 238000011109 contamination Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000011241 protective layer Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 238000004088 simulation Methods 0.000 description 1
- 230000008961 swelling Effects 0.000 description 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
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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)
Abstract
本发明涉及一种模拟LOCA工况下对核燃料包壳管性能评价的实验装置，其包括：型腔，其包括通过密封件分隔形成的真空腔和淬火腔，在密封件上设有通孔，核燃料包壳管密封设置在通孔中，且两端位于真空腔、中间位于淬火腔内，淬火腔包括腔体、腔体一体设置的金属波纹管，淬火腔能够随着金属波纹管的自由伸缩而伸缩；平衡装置，其包括滑轮组件、配重砝码；加热装置，其包括伸入核燃料包壳管内的加热棒、套设在加热棒外周的隔离管。本发明能够使得燃料包壳管在管受热过程中可以自由膨胀和伸缩，同时由金属波纹管的自由伸缩设置，还能够防止核燃料包壳管在加热过程中膨胀变弯的问题，从而能够准确的评价核燃料包壳管性能。
The invention relates to an experimental device for evaluating the performance of nuclear fuel cladding tubes under simulating LOCA working conditions, which includes: a mold cavity, which includes a vacuum chamber and a quenching chamber separated by a sealing member, and a through hole is arranged on the sealing member. The nuclear fuel cladding tube is sealed and arranged in the through hole, and the two ends are located in the vacuum chamber, and the middle is located in the quenching chamber. The quenching chamber includes a cavity and a metal bellows integrated with the cavity. The quenching cavity can expand and contract freely with the metal bellows And telescopic; Balance device, it comprises pulley assembly, counterweight weight; Heating device, it comprises the heating rod that stretches into the nuclear fuel cladding tube, the isolating tube that is sheathed in the outer periphery of heating rod. The invention can make the fuel cladding tube freely expand and contract during the heating process of the tube, and at the same time, the free telescopic setting of the metal bellows can also prevent the expansion and bending of the nuclear fuel cladding tube during the heating process, thereby enabling accurate Evaluation of nuclear fuel cladding tube performance.
Description
技术领域technical field
本发明涉及一种模拟LOCA工况下对核燃料包壳管性能评价的实验装置，特别涉及一种模拟LOCA工况发生时在高温水蒸气氧化及淬火中用于评价核燃料包壳性能的实验装置。The invention relates to an experimental device for evaluating the performance of nuclear fuel cladding tubes under simulating LOCA working conditions, in particular to an experimental device for evaluating the performance of nuclear fuel cladding tubes in high-temperature water vapor oxidation and quenching when simulating LOCA working conditions.
背景技术Background technique
核燃料包壳管为核燃料芯块外面的一层保护层，它保护燃料芯块不受冷却剂的侵蚀，避免燃料中裂变产物外泄，使冷却剂免受污染，同时还能保持燃料元件的几何形状并使之有足够的刚度和机械强度。包壳是反应堆中工况最苛刻的重要部件。其工况条件为其包容核燃料，承受高温高压和强烈的中子辐射，受裂变气体压力、腐蚀、燃料肿胀、吸氢致脆等危害，受冷却剂压力、冲刷、振动和腐蚀以及氢脆等威胁。因此核燃料包壳管的性能十分重要，关系到核电站的安全。The nuclear fuel cladding tube is a protective layer outside the nuclear fuel pellet, which protects the fuel pellet from the erosion of the coolant, prevents the leakage of fission products in the fuel, keeps the coolant from contamination, and maintains the geometry of the fuel element Shape and make it have sufficient rigidity and mechanical strength. The cladding is an important part of the most severe working conditions in the reactor. Its working condition is that it contains nuclear fuel, withstands high temperature and pressure and strong neutron radiation, is subject to fission gas pressure, corrosion, fuel swelling, hydrogen absorption and embrittlement, etc., and is subject to coolant pressure, erosion, vibration and corrosion, and hydrogen embrittlement, etc. threaten. Therefore, the performance of the nuclear fuel cladding tube is very important, which is related to the safety of the nuclear power plant.
LOCA为反应堆运行过程中非常严重的事故，该事故发生主要由以下原因引起的：一回路一根管道或辅助系统的管道破裂；一回路或辅助系统管道的阀门意外打开或不能关闭；输送一回路介质的泵的轴封或阀杆泄露。LOCA事故发生时反应堆失去一回路冷却剂，堆芯冷却不良导致包壳温度快速升高，使其氧化速率加快，造成包壳材料氧化膜厚度快速增加。在LOCA的后期，大量的水注入反应堆活性区，使包壳材料温度快速下降，可以认为该过程是对包壳材料的淬火，如果包壳材料没有足够的抗冲击能力便会发生破裂，导致放射性裂变产物释放，对反应堆的安全构成威胁。LOCA is a very serious accident during the operation of the reactor. The accident is mainly caused by the following reasons: the rupture of a pipeline in the primary circuit or the pipeline of the auxiliary system; the accidental opening or failure of the valve of the pipeline in the primary circuit or the auxiliary system; Medium pump shaft seal or stem leaks. When the LOCA accident occurred, the reactor lost the primary circuit coolant, and the poor cooling of the core led to a rapid rise in the temperature of the cladding, which accelerated the oxidation rate, resulting in a rapid increase in the thickness of the cladding material oxide film. In the later stage of LOCA, a large amount of water is injected into the reactor active area, causing the temperature of the cladding material to drop rapidly. This process can be considered as a quenching of the cladding material. If the cladding material does not have sufficient impact resistance, it will rupture, resulting in radioactivity. The release of fission products poses a threat to the safety of the reactor.
如果用堆内实验获得燃料包壳材料在LOCA工况下的行为，不仅技术复杂，而且耗费较大。因此，基本上采用反应堆外模拟技术及装置来评价燃料核燃料包壳管的性能。目前，进行模拟LOCA工况下包壳行为的装置较少，大部分为了利于控温采取外部加热的方式，该方式与LOCA真实工况不相符合，不能够更加真实的反应工况下材料的性能。同时，一部分实验装置在加热过程中核燃料包壳管不能自由膨胀，因此燃料核燃料包壳管在整个试验过程中承受了一定的外力，这将对试验结果产生一定的影响，不能准确的反应材料的真实性能，还有一部分实验装置在加热过程中核燃料包壳管能够自由膨胀，但其存在了膨胀后变弯的问题，无法使得包壳管能够自由伸缩，更准确的测试材料的性能。If the behavior of fuel cladding material under LOCA conditions is obtained by in-core experiments, it is not only technically complicated, but also expensive. Therefore, the performance of nuclear fuel cladding tubes is basically evaluated using external reactor simulation techniques and devices. At present, there are few devices for simulating cladding behavior under LOCA working conditions, and most of them use external heating to facilitate temperature control. This method does not conform to the real working conditions of LOCA, and cannot respond more realistically to the behavior of materials under working conditions. performance. At the same time, the nuclear fuel cladding tube of some experimental devices cannot expand freely during the heating process, so the fuel nuclear fuel cladding tube bears a certain external force during the entire test process, which will have a certain impact on the test results and cannot accurately reflect the material. In terms of real performance, there is also a part of the experimental device where the nuclear fuel cladding tube can expand freely during the heating process, but it has the problem of bending after expansion, which cannot make the cladding tube free to expand and contract, and more accurately test the performance of the material.
发明内容Contents of the invention
本发明所要解决的技术问题是克服现有技术的不足，提供一种模拟LOCA工况下对核燃料包壳管性能评价的实验装置。The technical problem to be solved by the invention is to overcome the deficiencies of the prior art and provide an experimental device for evaluating the performance of nuclear fuel cladding tubes under simulated LOCA working conditions.
为解决上述技术问题，本发明采取如下技术方案：In order to solve the problems of the technologies described above, the present invention takes the following technical solutions:
一种模拟LOCA工况下对核燃料包壳管性能评价的实验装置，其包括：An experimental device for evaluating the performance of nuclear fuel cladding tubes under simulated LOCA working conditions, comprising:
用于容纳核燃料包壳管的型腔，该型腔包括通过密封件分隔形成的位于上下两端的真空腔和位于中部的淬火腔，在密封件上设有通孔，核燃料包壳管密封设置在通孔中，且两端位于真空腔、中间位于淬火腔内，淬火腔包括与核燃料包壳管延伸方向一致的腔体、以及与沿着腔体方向与腔体一体设置的金属波纹管，其中淬火腔能够随着金属波纹管的自由伸缩而伸缩，腔体上具有水蒸气的入口和出口、以及淬火液的入口和出口；A cavity for accommodating nuclear fuel cladding tubes. The cavity includes vacuum chambers at the upper and lower ends and a quenching cavity in the middle separated by seals. There are through holes on the seals, and the nuclear fuel cladding tubes are sealed in The two ends are located in the vacuum chamber, and the middle is located in the quenching chamber. The quenching chamber includes a cavity that is consistent with the extension direction of the nuclear fuel cladding tube, and a metal bellows that is integrated with the cavity along the direction of the cavity. The quenching chamber can expand and contract with the free expansion and contraction of the metal bellows, and the chamber has inlets and outlets for water vapor, and inlets and outlets for quenching liquid;
平衡装置，其用于平衡对金属波纹管施加的应力，使得金属波纹管处于自由伸缩状态，其包括位于上端部真空腔的上方的滑轮组件、以及配重砝码；A balance device, which is used to balance the stress applied to the metal bellows, so that the metal bellows is in a state of free expansion and contraction, which includes a pulley assembly located above the vacuum chamber at the upper end, and a counterweight;
加热装置，其包括伸入核燃料包壳管内的加热棒、套设在加热棒的外周用于将加热棒与核燃料包壳管的内壁绝缘隔开的隔离管，该隔离管的材质为石英、碳化硼或陶瓷。The heating device includes a heating rod extending into the nuclear fuel cladding tube, and an isolation tube sleeved on the outer periphery of the heating rod to insulate the heating rod from the inner wall of the nuclear fuel cladding tube. The material of the isolating tube is quartz, carbonized boron or ceramic.
优选地，金属波纹管位于腔体的上方，且金属波纹管的上端部与密封件密封连接。尽可能的减小对金属波纹管所产生的应力，便于平衡装置的设计。Preferably, the metal bellows is located above the cavity, and the upper end of the metal bellows is in sealing connection with the sealing member. Minimize the stress on the metal bellows to facilitate the design of the balance device.
进一步的，平衡装置有两组，且分别位于上端部真空腔顶部的左右两侧。使得真空腔的受力相对均匀，确保金属波纹管的自由伸缩，进一步有效地防止了核燃料包壳管的弯曲。Further, there are two sets of balancing devices, which are respectively located on the left and right sides of the top of the vacuum chamber at the upper end. The force of the vacuum chamber is relatively uniform, the free expansion and contraction of the metal bellows is ensured, and the bending of the nuclear fuel cladding tube is further effectively prevented.
根据本发明的一个具体实施和优选方面，滑轮组件包括位于上端部真空腔上方的定滑轮、缠绕在定滑轮上的牵引绳，其中牵引绳一端部与位于上端部真空腔相连接、另一端部与配重砝码相连接。结构简单，且便于实施。According to a specific implementation and preferred aspect of the present invention, the pulley assembly includes a fixed pulley located above the upper end vacuum chamber, and a traction rope wound on the fixed pulley, wherein one end of the traction rope is connected with the vacuum chamber located at the upper end, and the other end is Connect with counterweight weights. The structure is simple and easy to implement.
根据本发明的另一具体实施和优选方面，加热棒两端部分别伸出所述核燃料包壳管，加热装置还包括分别设置在加热棒两端部的电极。According to another specific implementation and preferred aspect of the present invention, the two ends of the heating rod protrude from the nuclear fuel cladding tube respectively, and the heating device further includes electrodes respectively arranged at the two ends of the heating rod.
优选地，电极为钨电极。Preferably, the electrodes are tungsten electrodes.
优选地，加热装置还包括分别设置在真空腔内、用于将电极与所述真空腔相绝缘的绝缘层。Preferably, the heating device further includes insulating layers respectively disposed in the vacuum chamber and used to insulate the electrodes from the vacuum chamber.
优选地，腔体上还设有测温窗口。便于实际操控。Preferably, a temperature measurement window is also provided on the cavity. It is convenient for practical manipulation.
此外，实验装置还包括气体保护装置，该气体保护装置包括保护气体存储器、分别向真空腔内通入保护气体的管道、以及控制阀。In addition, the experimental device also includes a gas protection device, which includes a protection gas storage, a pipeline for introducing the protection gas into the vacuum chamber, and a control valve.
优选地，密封件为水冷密封件，核燃料包壳管与通孔由石墨密封圈进行密封。Preferably, the seal is a water-cooled seal, and the nuclear fuel cladding tube and the through hole are sealed by a graphite sealing ring.
由于以上技术方案的实施，本发明与现有技术相比具有如下优点：Due to the implementation of the above technical solutions, the present invention has the following advantages compared with the prior art:
本发明的装置设计巧妙，合理，使得燃料包壳管在管受热过程中可以自由膨胀和伸缩，同时由金属波纹管的自由伸缩设置，还能够解决核燃料包壳管在加热过程中膨胀变弯的问题，从而能够准确的评价核燃料包壳管性能，结构简单，操作方便，且成本低。The design of the device of the present invention is ingenious and reasonable, so that the fuel cladding tube can freely expand and contract during the heating process of the tube, and at the same time, the free expansion and contraction of the metal bellows can also solve the problem of expansion and bending of the nuclear fuel cladding tube during the heating process problem, so that the performance of the nuclear fuel cladding tube can be accurately evaluated, the structure is simple, the operation is convenient, and the cost is low.
附图说明Description of drawings
下面结合附图和具体的实施例对本发明做进一步详细的说明。The present invention will be described in further detail below in conjunction with the accompanying drawings and specific embodiments.
图1为根据本发明的实验装置的结构示意图；Fig. 1 is the structural representation according to experimental device of the present invention;
其中：1、核燃料包壳管（锆合金包壳管）；2、型腔；3、密封件（水冷密封件）；4、真空腔；5、淬火腔；50、腔体； 51、金属波纹管；6、平衡装置；60、滑轮组件；600、定滑轮；601、牵引绳；61、配重砝码；7、加热装置；70、加热棒；71、隔离管；72、电极；8、气体保护装置；80、保护气体的管道；a、水蒸气的入口；b、水蒸气的出口；c、淬火液的入口；d、淬火液的出口；e、测温窗口。Among them: 1. Nuclear fuel cladding tube (zirconium alloy cladding tube); 2. Cavity; 3. Seal (water-cooled seal); 4. Vacuum cavity; 5. Quenching cavity; 50. Cavity; 51. Metal corrugation 6, balance device; 60, pulley assembly; 600, fixed pulley; 601, traction rope; 61, counterweight weight; 7, heating device; 70, heating rod; 71, isolation tube; 72, electrode; 8, Gas protection device; 80, pipeline of protective gas; a, inlet of water vapor; b, outlet of water vapor; c, inlet of quenching liquid; d, outlet of quenching liquid; e, temperature measuring window.
具体实施方式detailed description
如图1所示，本实施例提供模拟LOCA工况下对核燃料包壳管性能评价的实验装置，其主要包括：用于容纳核燃料包壳管1的型腔2，该型腔2包括通过密封件3分隔形成的位于上下两端的真空腔4和位于中部的淬火腔5，在密封件3上设有通孔，核燃料包壳管1密封设置在通孔中，且两端位于真空腔4、中间位于淬火腔5内，淬火腔5包括与核燃料包壳管1延伸方向一致的腔体50、以及与沿着腔体50方向与腔体50一体设置的金属波纹管51，其中淬火腔5能够随着金属波纹管51的自由伸缩而伸缩，腔体50上具有水蒸气的入口a和出口b、以及淬火液的入口c和出口d；As shown in Figure 1, this embodiment provides an experimental device for evaluating the performance of nuclear fuel cladding tubes under simulated LOCA operating conditions, which mainly includes: a cavity 2 for accommodating nuclear fuel cladding tubes 1, the cavity 2 includes a sealing The vacuum chamber 4 located at the upper and lower ends and the quenching chamber 5 located in the middle are separated and formed by the member 3. A through hole is provided on the sealing member 3, and the nuclear fuel cladding tube 1 is sealed in the through hole, and the two ends are located in the vacuum chamber 4, The middle is located in the quenching chamber 5, and the quenching chamber 5 includes a cavity 50 consistent with the extension direction of the nuclear fuel cladding tube 1, and a metal bellows 51 integrally arranged with the cavity 50 along the direction of the cavity 50, wherein the quenching cavity 5 can As the metal bellows 51 expands and contracts freely, the cavity 50 has an inlet a and an outlet b of water vapor, and an inlet c and outlet d of the quenching liquid;
平衡装置6，其用于平衡对金属波纹管51施加的应力，使得金属波纹管51处于自由伸缩状态，其包括位于上端部真空腔4的上方的滑轮组件60、以及配重砝码61；A balance device 6, which is used to balance the stress applied to the metal bellows 51, so that the metal bellows 51 is in a state of free expansion and contraction, which includes a pulley assembly 60 located above the upper end vacuum chamber 4, and a counterweight 61;
加热装置7，其包括伸入核燃料包壳管1内的加热棒70、套设在加热棒70的外周用于将加热棒70与核燃料包壳管1的内壁绝缘隔开的隔离管71，该隔离管71的材质为石英、碳化硼或陶瓷。The heating device 7 includes a heating rod 70 protruding into the nuclear fuel cladding tube 1, and an isolation tube 71 sleeved on the outer periphery of the heating rod 70 for insulating the heating rod 70 from the inner wall of the nuclear fuel cladding tube 1. The isolation tube 71 is made of quartz, boron carbide or ceramics.
具体的，密封件3为水冷密封件，核燃料包壳管1与密封件3上的通孔由石墨密封圈进行密封。Specifically, the sealing member 3 is a water-cooled sealing member, and the through holes on the nuclear fuel cladding tube 1 and the sealing member 3 are sealed by a graphite sealing ring.
金属波纹管51位于腔体50的上方，且金属波纹管51的上端部与密封件3密封连接。尽可能的减小对金属波纹管51所产生的应力，便于平衡装置6的设计。The metal bellows 51 is located above the cavity 50 , and the upper end of the metal bellows 51 is in sealing connection with the sealing member 3 . Reducing the stress on the metal bellows 51 as much as possible facilitates the design of the balancing device 6 .
水蒸气的入口a和出口b分别位于腔体50的两侧，且水蒸气的出口b位于水蒸气的入口a的上方；淬火液的入口c和出口d分别位于所述腔体50的同侧，且淬火液的出口d位于淬火液的入口c的上方。The inlet a and the outlet b of the water vapor are located on both sides of the chamber 50 respectively, and the outlet b of the water vapor is located above the inlet a of the water vapor; the inlet c and the outlet d of the quenching liquid are respectively located on the same side of the chamber 50 , and the outlet d of the quenching liquid is located above the inlet c of the quenching liquid.
进一步的，淬火液的出口d与水蒸气的出口b位于同侧，且水蒸气的出口b位于水蒸气的出口b的上方。Further, the outlet d of the quenching liquid is located on the same side as the outlet b of the water vapor, and the outlet b of the water vapor is located above the outlet b of the water vapor.
进一步的，腔体50上还设有测温窗口e。便于实际操控。该测温窗口e位于水蒸气的入口a的同侧，且位于腔体50的中上部。Further, the cavity 50 is also provided with a temperature measurement window e. It is convenient for practical manipulation. The temperature measurement window e is located on the same side as the water vapor inlet a, and is located in the middle and upper part of the cavity 50 .
本例中，平衡装置6有两组，且分别位于上端部真空腔4顶部的左右两侧。使得真空腔4的受力相对均匀，确保金属波纹管51的自由伸缩，进一步有效地防止了核燃料包壳管1的弯曲。In this example, there are two groups of balancing devices 6 , which are respectively located on the left and right sides of the top of the upper end vacuum chamber 4 . The force of the vacuum chamber 4 is relatively uniform, the free expansion and contraction of the metal bellows 51 is ensured, and the bending of the nuclear fuel cladding tube 1 is further effectively prevented.
进一步的，滑轮组件60包括位于上端部真空腔4上方的定滑轮600、缠绕在定滑轮600上的牵引绳601，其中牵引绳601一端部与位于上端部真空腔4相连接、另一端部与配重砝码61相连接。结构简单，且便于实施。Further, the pulley assembly 60 includes a fixed pulley 600 located above the upper vacuum chamber 4, and a traction rope 601 wound on the fixed pulley 600, wherein one end of the traction rope 601 is connected to the vacuum chamber 4 at the upper end, and the other end is connected to the vacuum chamber 4 at the upper end. Counterweight weights 61 are connected. The structure is simple and easy to implement.
本例中，加热棒70两端部分别伸出核燃料包壳管1，加热装置7包括分别设置在加热70两端部的电极72；分别设置在真空腔3内、用于将电极72与真空腔4相绝缘的绝缘层（图中未显示）。In this example, the two ends of the heating rod 70 extend out of the nuclear fuel cladding tube 1 respectively, and the heating device 7 includes electrodes 72 respectively arranged at the two ends of the heating rod 70; The cavity is insulated with 4 phases by an insulating layer (not shown in the figure).
进一步的，电极为钨电极。延长自身的使用寿命。Further, the electrodes are tungsten electrodes. Extend its own lifespan.
同时，本例中，隔离管71的两端部也冒出核燃料包壳管1的两端部，由隔离管71和加热棒70的设置，留有余量，从而便于核燃料包壳管1伸缩，也进一步的防止核燃料包壳管1的变形或弯曲。At the same time, in this example, the two ends of the isolation tube 71 also protrude from the two ends of the nuclear fuel cladding tube 1, and the arrangement of the isolation tube 71 and the heating rod 70 leaves a margin, thereby facilitating the expansion and contraction of the nuclear fuel cladding tube 1 , and further prevent deformation or bending of the nuclear fuel cladding tube 1 .
此外，实验装置还包括气体保护装置8，该气体保护装置8包括保护气体存储器（图中未显示）、分别向真空腔4内通入保护气体的管道80、以及控制阀（图中未显示）。In addition, the experimental device also includes a gas protection device 8, which includes a protection gas storage (not shown in the figure), a pipeline 80 for feeding the protection gas into the vacuum chamber 4, and a control valve (not shown in the figure) .
本例中，淬火腔的总长度为330mm，其中腔体的长度为300mm，金属波纹管的长度为30mm。In this example, the total length of the quenching chamber is 330mm, wherein the length of the chamber is 300mm, and the length of the metal bellows is 30mm.
综上所述，本发明的燃料包壳管在管受热过程中可以自由膨胀和伸缩，同时由金属波纹管的自由伸缩设置，防止核燃料包壳管在加热过程中膨胀变弯的现象发生，从而更准确的测试材料的性能，对提高核安全水平具有重要意义。In summary, the fuel cladding tube of the present invention can freely expand and contract during the heating process of the tube, and at the same time, the free expansion and contraction of the metal bellows prevents the expansion and bending of the nuclear fuel cladding tube during the heating process, thereby More accurate testing of the performance of materials is of great significance to improving nuclear safety.
以上对本发明做了详尽的描述，其目的在于让熟悉此领域技术的人士能够了解本发明的内容并加以实施，并不能以此限制本发明的保护范围，凡根据本发明的精神实质所作的等效变化或修饰，都应涵盖在本发明的保护范围内。The present invention has been described in detail above, and its purpose is to allow those familiar with this field to understand the content of the present invention and implement it, and can not limit the scope of protection of the present invention. Effect changes or modifications should be covered within the protection scope of the present invention.
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| CN110957053B (en) * | 2019-12-18 | 2021-10-08 | 苏州热工研究院有限公司 | A test system for simulating high fuel consumption conditions of fuel cladding |
| CN112378764A (en) * | 2020-09-29 | 2021-02-19 | 国家电投集团科学技术研究院有限公司 | Explosion testing device and method for nuclear fuel cladding pipe |
| CN112382421B (en) * | 2020-10-09 | 2022-06-21 | 国家电投集团科学技术研究院有限公司 | Test device for simulating nuclear reactor fuel rod |
| CN113421668B (en) * | 2021-05-19 | 2024-03-22 | 中国原子能科学研究院 | Experimental system for simulating water loss accident |
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