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1.
提出了中国先进研究堆冷中子源氢系统的概念设计方案,并进行了可行性试验。针对概念设计中采用的两相虹吸氢回路系统,使用氟里昂113进行了1:1的模化试验研究,确定了中子慢化室含气率、热虹吸系统循环能力及各部件的初步结构形式和尺寸。还进行了气泡在不同液体中上升速度的试验研究,以决定密度、粘度及表面张力等物性对气泡上升速度、含气率、系统循环能力的影响,分析得到模化关系,以便将氟里昂模化试验的结果应用于中国先进研究堆(CARR)堆冷中子源氢系统的设计。  相似文献   

2.
以氟利昂R113为工质对中国先进研究堆(CARR)冷中子源(CNS)两相氢热虹吸循环回路进行了全尺寸模拟试验。以气液密度比、体积蒸发率相等为相似准则,试验研究了循环特性、冷包液位、截面含气率与热负荷的关系。实验观测到,各工况下的模拟回路均能建立稳定的循环,在冷包内形成了内筒含气、环形空间充满一定含气率的气液两相混合物的慢化剂结构。随热负荷变化,模拟系统冷包液位具有自调节性。  相似文献   

3.
应用蒙特卡罗方法研究了中国先进研究堆冷中子源尺寸对58Ni和超镜冷中子导管出口处中子注量率的影响,使用2个不同软件获得了一致的模拟结果。对于58Ni导管,需要18cm×30cm的冷中子源尺寸才可使积分中子注量率和直到2nm波长的中子注量率达到饱和,对于m=2的超镜导管对应的尺寸为22cm×36cm。  相似文献   

4.
以氟利昂12为冷却介质,对4种加热比条件下的矩形窄缝通道双面不对称加热工况下的临界热流密度(CHF)进行实验分析,获得各种工况下CHF与冷却剂质量流速、入口过冷度、出口含汽率的关系。实验结果表明:低含汽率下,CHF随加热比的增加而增加,随着含汽率的增加,不同加热比的实验通道内CHF差异减小;高含汽率下,CHF随加热比变化趋势与低含汽率的相反。  相似文献   

5.
为了测量核蒸汽发生器模拟体的汽液两相流空泡率和流型,采用国产两相流空泡率光纤探头于小型氟利昂两相流台架。光纤探头信  相似文献   

6.
以氟利昂113为工质,对矩形窄腔内的截面含汽率进行了研究,得出了不同压力、加热功率情况下的截面含汽率变化规律以及含汽率沿高度方向的计算式。结果表明,当容积产气量一定时,整个空间内的平均截面含汽率随压力增大而升高,而当加热功率一定时,截面含汽率随压力增大而降低。因此当热负荷不变时适当升高工作压力,可以降低截面含汽率。  相似文献   

7.
介绍了超冷中子的获取方法及其中的关键技术,对固氘超冷中子源和超流氦超冷中子源的工作原理、结构和部分技术参数进行了阐述分析,并对我国超冷中子源的研究前景进行了展望。上述工作为我国未来超冷中子源的设计和建设提供了参考。  相似文献   

8.
为了测量核蒸汽发生器模拟体的汽液两相流空泡率和流型,采用国产两相流空泡率光纤探头于小型氟利昂两相流台架。光纤探头信号被动态采集并转换为数字形式。同时对信号的电平时序,电平概率密度函数和傅里叶谱函数进行了分析。汽液过渡的阈值由冷态压降试验确定。空泡率由单阈值方法确定,并与传热数值计算结果进行了比较。流型由上述时序和函数的特征图形确定,并经过目视观察记录证实。试验表明,光纤技术可以应用于两相流的流型和空泡份额测量。  相似文献   

9.
正中国先进研究堆(CARR)冷中子源装置采用单相液氘作为冷中子慢化剂,液氘慢化剂通过堆内装置热交换器热虹吸回路封闭式自然循环和氦气夹层内低温氦气(约19K)的冷却维持在液态。CARR冷中子源系统充氘调试主要目的为:1)实现首次氘装载、冷中子源冷态运行考验及带核综合试验,验证冷中子源系统满足合同规定的技术要求,能够安全稳定地运行;2)测量冷中子源热负荷、冷中子源运行模式运行参数验证以及冷中子  相似文献   

10.
正中国先进研究堆(CARR)冷中子源堆内部分由真空容器及堆内组件组成,包括热虹吸系统、主法兰和与冷中子源堆外系统的连接管线部分,称为冷源堆内装置。CARR冷中子源堆内装置安装在重水箱内,冷包及热虹吸回路装置安装在真空容器内,氘系统管线、氦制冷系统管线、真空管线在堆水池内需要安装固定并与冷包及热虹吸回路装置连接。冷包处在堆芯活性区中心标高位置。CARR冷中子源堆内安装具体流程如图1所示。冷中子源堆内安装具有难度大、精度高、技术  相似文献   

11.
To keep the void fraction of two-phase hydrogen in the moderator cell of the cold neutron source (CNS) of China Advanced Research Reactor (CARR) to a specified range, an annular vessel with the same size as the actual moderator cell was used as test section. Deionized water and alcohol, sucrose, and sodium chloride solutions with different concentrations were used as working fluid to find out influences of physical properties, such as density, viscosity and surface tension, of the two-phase mixture on void fraction. The tests proved that the ratio of surface tension to density of liquid phase has great influence on void fraction: the larger the ratio, the smaller the void fraction. Since the ratio of surface tension to density of Freon 113 is lower than that of liquid hydrogen, Freon 113 can be used as a working fluid to study the void fraction in the two-phase hydrogen thermosiphon loop in the CNS of CARR and the results will be conservative.  相似文献   

12.
The cold neutron source (CNS) is a facility to increase cold neutrons by scattering thermal neutrons in liquid hydrogen or deuterium around 20 K. For extracting a stable cold neutron flux from the CNS, the liquid quantity in the moderator cell should be maintained stably against disturbance of nuclear heating. The China Institute of Atomic Energy (CIAE) is now constructing the China Advanced Research Reactor (CARR: 60 MW). and designing the CARR-CNS with a two-phase thermo-siphon loop consisting of a condenser, two moderator transfer tubes and an annular cylindrical moderator cell. The mock-up tests were carried out using a full-scale loop with Freon-113,for validating the self-regulating characteristics of the loop, the void fraction less than 20% in the liquid hydrogen of the moderator cell, and the requirements for establishing the condition under which the inner shell has only vapor. The density ratio of liquid to vapor and the volumetric evaporation rate due to heat load are kept the same as those innormal operation of the CARR-CNS. The results show that the loop has the self-regulating characteristics and the inner shell contains only vapor, while the outer shell liquid. The local void fraction in the liquid increases with increasing of the loop pressure.  相似文献   

13.
In certain natural-circulation reactor systems proposed recently, vapor generation takes place by flashing in an adiabatic riser above the core. A step-by-step facility design procedure was used to define suitable scaling criteria for a refrigerant-113 (R-113) experiment simulating the dynamics and stability of such a loop. The fact that vapor generation does not normally take place in the core allows additional flexibility in designing the model; almost perfect simulation can be achieved, mainly by reducing the height of the facility according to the liquid density ratio and scaling for similar void fraction distributions in the prototype and the model.  相似文献   

14.
Experiments have been performed using sodium, water, white spirit and Freon 113 in a simple small-scale system, to determine the conditions necessary for gas entrainment inception at a vortex with an unstable gas core. The results demonstrate that surface tension effects play a major role and hence they must not be ignored when developing an entrainment-free system.  相似文献   

15.
The three-dimensional moving particle semi-implicit (MPS) method is employed to simulate the deposition process of single droplet on the liquid film. The model accounts for the presence of inertial, gravitation, viscous and surface tension and is validated by comparison with experimental results. The parameters of liquid droplets and film are calculated by a one-dimensional mixture model in which correlations and methods on void fraction, entrainment fraction and droplet velocity and size distribution are employed. The simulation results are analyzed to study the effect of splash on the deposition and re-entrainment processes in annular-mist flow. It is found that splash plays an important role in the deposition and re-entrainment processes in high quality conditions of BWR.  相似文献   

16.
The purpose of the study is to develop a method for predicting steam carryunder which is one of the important characteristics of a steam separator. Bubbles returning to the liquid surface and trapped by the re-circulating flow are calculated by tracking the behavior of bubbles moving in liquid bulk where velocity and temperature distributions have been calculated beforehand in conjunction with the Monte-Carlo method. Regarding the statistics of bubbles, a survey of references and visual tests have been conducted. To validate this method, several tests to measure bubble behavior under air/water conditions at atmospheric pressure and high temperature and pressure ranging 3~7 MPa have been conducted with a full-scale steam separator.

As a result, the developed method predicted with good precision the carryunder ratio obtained by the full-scale tests under the condition that carried-under void fraction was less than 20%, but underestimated carryunder ratio in the ATR “Fugen” reactor in which steam drum water level was shallow and average void fraction in water bulk was high. This method has a characteristic that carryunder ratio is underestimated in the case that void fraction is more than 20%.  相似文献   

17.
Little work on the void fraction behaviors along structural materials with poor-wettability for liquid metals has been performed. In the present study, void fraction behaviors around a single cylinder with non-wetting surface condition were quantitatively discussed by using a gas jet–cylinder system where the impinging jet flow, the boundary layer flow, the separation flow, and the wake flow appear. One cylinder with a non-wetting surface and two cylinders with a wetting surface were used to vary the wettability for liquid sodium, and void fraction distributions were measured around the cylinders. In the case of wetting condition, void fraction distributions around the cylinder decrease clearly in the backward region of the cylinder, and liquid-rich region is formed due to bubble separation from the cylinder surface. On the other hand, under non-wetting condition, because of two-phase flow without bubble separation on the cylinder surface, void fraction distributions show almost steady values around the cylinder compared to those with wetting surface. The void behaviors on a non-wetting surface were also confirmed by a visualization experiment conducted in water. The observed differences can be basically attributed to the work of adhesion required for liquid–solid interfacial separation.  相似文献   

18.
The local void fraction, bubble size and interfacial area concentration for co-current air-water bubbly flow through a horizontal pipe of 50.3 mm internal diameter were investigated experimentally using the double-sensor resistivity probe method. The local and area-averaged void fractions and interfacial area concentrations were analyzed as a function of liquid and gas flow rates. These parameters were found to increase systematically with decreasing liquid flow and increasing gas flow. However, variations with the liquid flow were not as significant as with the gas flow. A consistent variation of the gas phase drift velocity and distribution parameter with the liquid flow rate was observed. It was demonstrated that presentation of the average void fraction in terms of flowing volumetric concentration was more appropriate for horizontal bubbly flow. Several bubble break-up mechanisms were discussed. It was concluded that average pressure fluctuations generated by the turbulent liquid fluctuations acting across a bubble diameter are the only mechanism which causes distortion of a bubble. Based on this force and the competing surface tension force, a theoretical model was developed for mean bubble size and interfacial area concentration. The theoretically predicted mean bubble size and interfacial area concentration were found to agree reasonably well with those measured by the double-sensor resistivity method.  相似文献   

19.
Visualization was performed for the vapor bubbles in water subcooled flow boiling in a vertical heated tube to measure simultaneously the void fraction and the four fundamental bubble parameters: nucleation site density, bubble release frequency, bubble lifetime and bubble size. Using the mass flowrate and liquid subcooling as the experimental parameters, the changes of void fraction and bubble parameters with the wall heat flux were measured. The results of image analysis showed that the vapor void fraction could be approximated by the function of nucleation site density and bubble lift-off diameter; the bubble lift-off diameter was more influential than the nucleation site density. It was hence concluded that the bubble lift-off diameter could be regarded as the key parameter to determine the vapor void fraction under the present experimental conditions. The strong relation of bubble lift-off diameter to superheated liquid layer thickness was indicated for the future model development studies of bubble lift-off diameter.  相似文献   

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