CN201066596Y - Down pipe base for nucleus fuel component - Google Patents
Down pipe base for nucleus fuel component Download PDFInfo
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- CN201066596Y CN201066596Y CNU2007201755659U CN200720175565U CN201066596Y CN 201066596 Y CN201066596 Y CN 201066596Y CN U2007201755659 U CNU2007201755659 U CN U2007201755659U CN 200720175565 U CN200720175565 U CN 200720175565U CN 201066596 Y CN201066596 Y CN 201066596Y
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- lower tube
- tube support
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- 239000000446 fuel Substances 0.000 title claims description 3
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 16
- 238000002474 experimental method Methods 0.000 abstract description 5
- 238000001514 detection method Methods 0.000 abstract description 3
- 238000004088 simulation Methods 0.000 description 10
- 239000012530 fluid Substances 0.000 description 4
- 238000005259 measurement Methods 0.000 description 2
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
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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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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
技术领域 technical field
本实用新型涉及核燃料组件下管座,具体涉及一种用于模拟实验的核燃料组件下管座。The utility model relates to a lower pipe seat of a nuclear fuel assembly, in particular to a lower pipe seat of a nuclear fuel assembly used for simulation experiments.
背景技术 Background technique
反应堆整体水力模拟实验用于验证反应堆的设计,特别是堆芯结构是否满足热工水力要求,其中堆芯入口流量分配因子的取得,对提高水力设计的可靠性,进而改善反应堆热工水力特性,有非常重要的意义。The overall hydraulic simulation experiment of the reactor is used to verify the design of the reactor, especially whether the core structure meets the thermal-hydraulic requirements. The acquisition of the core inlet flow distribution factor can improve the reliability of the hydraulic design and further improve the thermal-hydraulic characteristics of the reactor. has a very important meaning.
核燃料组件主要由下管座、棒束、上管座等部分组成。在进行整体水力模拟实验时,需要对复杂的组件进行合理简化,使得模型组件与原型组件具有相同的阻力特性。模拟组件由下管座(即涡轮流量计段)、下管板、棒束、上管座连接板和阻力调整段组成,要求各段阻力与原型组件相同,因此模型组件下管座要和原型组件下管座的阻力一致。如果采用内嵌式涡轮流量计,在下管座区段流动的总阻力将包括下管座空腔的阻力和涡轮流量计的阻力两部分,由于涡轮流量计内嵌,流量计的有效流通面积受制于下管座外形尺寸的限制,其设计值较小,形成了较大的流动阻力,从而使得内嵌式涡轮流量计与下管座的空腔阻力总和大于原型下管座的阻力,无法实现阻力相等的模拟。基于上述具体的技术要求,需要对下管座和涡轮流量计进行改进,减小其阻力,从而满足反应堆整体水力模拟的实验要求。The nuclear fuel assembly is mainly composed of lower nozzles, rod bundles, upper nozzles and other parts. When conducting the overall hydraulic simulation experiment, it is necessary to rationally simplify the complex components so that the model components have the same resistance characteristics as the prototype components. The simulation component consists of the lower tube base (that is, the turbine flowmeter section), the lower tube plate, the rod bundle, the upper tube base connecting plate and the resistance adjustment section. The resistance of each segment is required to be the same as that of the prototype component, so the lower tube base of the model component must be the same as the prototype The resistance of the tube socket under the assembly is consistent. If an embedded turbine flowmeter is used, the total resistance of the flow in the lower tube base section will include two parts: the resistance of the lower tube base cavity and the resistance of the turbine flowmeter. Since the turbine flowmeter is embedded, the effective flow area of the flowmeter is limited Due to the limitation of the outer dimension of the lower pipe seat, its design value is small, forming a large flow resistance, so that the sum of the cavity resistance of the embedded turbine flowmeter and the lower pipe seat is greater than the resistance of the prototype lower pipe seat, which cannot be realized Simulation of equal resistance. Based on the above specific technical requirements, it is necessary to improve the lower nozzle and turbine flowmeter to reduce their resistance, so as to meet the experimental requirements of the overall hydraulic simulation of the reactor.
发明内容 Contents of the invention
本实用新型的目的在于提供一种满足模拟实验要求,同时具有流量测量功能的核燃料组件下管座。The purpose of the utility model is to provide a nuclear fuel assembly lower nozzle which satisfies the requirements of the simulation experiment and has the function of flow measurement.
实现本实用新型目的的技术方案:一种核燃料组件下管座,包括外截面为正方形,内截面为圆形的外壳,下管座的内腔装有涡轮叶片、机芯和信号检测组件,下管座的下端设有突起的下支撑脚,下管座的上端出口处设有连接孔。The technical solution for realizing the purpose of the utility model: a lower tube base of a nuclear fuel assembly, including a shell with a square outer section and a circular inner section. The lower end of the tube base is provided with protruding lower supporting feet, and the outlet of the upper end of the lower tube base is provided with a connecting hole.
如上所述的核燃料组件下管座,下支撑脚为五边形,共四个,与下管座外壳为一个整体。As mentioned above, the lower nozzle base of the nuclear fuel assembly has four lower support legs in the shape of a pentagon, which are integrated with the lower nozzle housing.
本实用新型的效果在于:在核燃料组件模型设计时,在下管座的内腔安装涡轮叶片、机芯和信号检测组件,实现了下管座与涡轮流量计的组合设计,放大了流量计的流通面积,具有较小的流动压降,满足了加装涡轮后的下管座与原型组件下管座的阻力特性相同的要求,并从结构上保证了模型组件下管座外形和原型组件下管座相似,能够在整体水力模拟实验中代替原型组件测量流量分配因子,满足实验的要求。The effect of the utility model is that: when designing the model of the nuclear fuel assembly, the turbine blades, the core and the signal detection assembly are installed in the inner cavity of the lower pipe seat, so that the combined design of the lower pipe seat and the turbine flowmeter is realized, and the circulation of the flowmeter is enlarged. Area, with a small flow pressure drop, to meet the requirements of the same resistance characteristics of the lower pipe seat after the turbine is installed and the lower pipe seat of the prototype assembly, and structurally ensure the shape of the lower pipe seat of the model assembly and the lower pipe of the prototype assembly Similar to the seat, it can replace the prototype component in the overall hydraulic simulation experiment to measure the flow distribution factor and meet the requirements of the experiment.
附图说明 Description of drawings
图1为本实用新型核燃料组件下管座的主视图;Fig. 1 is the front view of the lower socket of the nuclear fuel assembly of the present invention;
图2为本实用新型核燃料组件下管座的俯视图;Fig. 2 is a top view of the lower socket of the nuclear fuel assembly of the present invention;
图3为本实用新型核燃料组件下管座的仰视图;Fig. 3 is a bottom view of the lower nozzle of the nuclear fuel assembly of the present invention;
图中:1.外壳;2.涡轮叶片;3.机芯;4.信号检测组件;5.下支撑脚;6.连接孔。In the figure: 1. Shell; 2. Turbine blade; 3. Movement; 4. Signal detection component; 5. Lower support leg; 6. Connection hole.
具体实施方式 Detailed ways
下面结合附图对本实用新型所述适用于模拟实验的核燃料组件下管座作进一步描述。The lower socket of the nuclear fuel assembly suitable for the simulation experiment described in the utility model will be further described below in conjunction with the accompanying drawings.
如图1、图2、图3所示,下管座的外壳1的外截面为正方形,内截面为圆形,下管座的内腔装有涡轮叶片2、机芯3和信号检测组件4,下管座的下端设有四个突起的下支撑脚5,该下支撑脚5为五边形,与下管座的外壳1为一个整体。下管座的上端出口处设有连接孔6。下管座的下管板通过间隙配合放入下管座的连接孔6内。整个下管座的外形与实验需要模拟的下管座原型相似。As shown in Fig. 1, Fig. 2 and Fig. 3, the outer cross-section of the
根据反应堆水力特性模拟的要求,设计压力为1.5MPa,设计温度80℃,当流体经过下管座内腔时,流体推动涡轮叶片旋转,然后通过涡轮叶片与信号检测器之间的磁耦合,将流体的流速转化成电脉冲信号输出,通过放大器放大整形,并传输给显示仪表,达到对流体的体积流量或总量进行测量的目的。According to the requirements of reactor hydraulic characteristics simulation, the design pressure is 1.5MPa, and the design temperature is 80°C. When the fluid passes through the inner cavity of the lower tube base, the fluid pushes the turbine blades to rotate, and then through the magnetic coupling between the turbine blades and the signal detector, the The flow rate of the fluid is converted into an electrical pulse signal output, amplified and shaped by the amplifier, and transmitted to the display instrument to achieve the purpose of measuring the volume flow or total amount of the fluid.
本实用新型从结构上将下管座与涡轮流量计合并,设计了一种具有流量测量功能的一体化式燃料组件下管座,使得加装涡轮后的下管座与原型下管座的阻力特性相同,并从结构上保证了与原型下管座相似,满足了实验要求。The utility model combines the lower nozzle and the turbine flowmeter structurally, and designs an integrated fuel assembly lower nozzle with flow measurement function, so that the resistance between the lower nozzle after the turbine is installed and the prototype lower nozzle is designed. The characteristics are the same, and the structure is guaranteed to be similar to the prototype lower tube seat, which meets the experimental requirements.
Claims (2)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNU2007201755659U CN201066596Y (en) | 2007-08-31 | 2007-08-31 | Down pipe base for nucleus fuel component |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNU2007201755659U CN201066596Y (en) | 2007-08-31 | 2007-08-31 | Down pipe base for nucleus fuel component |
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| CN201066596Y true CN201066596Y (en) | 2008-05-28 |
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| Application Number | Title | Priority Date | Filing Date |
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| CNU2007201755659U Expired - Lifetime CN201066596Y (en) | 2007-08-31 | 2007-08-31 | Down pipe base for nucleus fuel component |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105719707A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Differential pressure measuring point layout structure in pressurized water reactor integral hydraulic simulation test |
| CN105938074A (en) * | 2016-05-17 | 2016-09-14 | 西安交通大学 | Nuclear reactor fuel assembly bottom nozzle hydraulic scouring test system and test method thereof |
| CN106248152A (en) * | 2016-10-09 | 2016-12-21 | 中国核动力研究设计院 | A kind of novel enclosed passage small amount of flow measuring device and assembly method thereof |
| CN106803432A (en) * | 2017-02-28 | 2017-06-06 | 中国核动力研究设计院 | A kind of ex-reactor experiment structure of fuel assembly |
| CN107180659A (en) * | 2017-05-09 | 2017-09-19 | 中广核研究院有限公司 | Become resistance type pipe flow speed limits device |
-
2007
- 2007-08-31 CN CNU2007201755659U patent/CN201066596Y/en not_active Expired - Lifetime
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105719707A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Differential pressure measuring point layout structure in pressurized water reactor integral hydraulic simulation test |
| CN105938074A (en) * | 2016-05-17 | 2016-09-14 | 西安交通大学 | Nuclear reactor fuel assembly bottom nozzle hydraulic scouring test system and test method thereof |
| CN105938074B (en) * | 2016-05-17 | 2018-07-03 | 西安交通大学 | Fuel assembly for nuclear reactor bottom nozzle waterpower scour simulation system and its test method |
| CN106248152A (en) * | 2016-10-09 | 2016-12-21 | 中国核动力研究设计院 | A kind of novel enclosed passage small amount of flow measuring device and assembly method thereof |
| CN106803432A (en) * | 2017-02-28 | 2017-06-06 | 中国核动力研究设计院 | A kind of ex-reactor experiment structure of fuel assembly |
| CN106803432B (en) * | 2017-02-28 | 2018-05-25 | 中国核动力研究设计院 | A kind of ex-reactor experiment structure of fuel assembly |
| CN107180659A (en) * | 2017-05-09 | 2017-09-19 | 中广核研究院有限公司 | Become resistance type pipe flow speed limits device |
| CN107180659B (en) * | 2017-05-09 | 2023-12-15 | 中广核研究院有限公司 | Variable resistance type pipeline flow speed limiting device |
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| Date | Code | Title | Description |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term | ||
| CX01 | Expiry of patent term |
Granted publication date: 20080528 |