竖直管内淹没及流向反转的实验研究

本文对竖直管中气体由下向上流动,液体由上向下流动过程的淹没及流向反转问题进行了实验研究。给出了计算淹没及流向反转的关系式。通过实验发现,在一定的液体流量下,增加气体流量与减少气体流量时淹没点有所差别;管壁的干燥条件对流向反转有很大影响。     

管径和气体入口条件对淹没过程的影响

通过实验研究了管径和气体入口条件对竖直管内淹没和流向反转的影响。实验结果表明,当气体入口阻力减小时,在一定的条件下,淹没开始点所对应的气体流量会大大提高。气体入口为直角时,管径不同对淹没开始点无影响。气体入口为喇叭口形时,管径对淹没开始点有影响。气体入口条件对全部携带点无影响,但管径对全部携带点有影响,管径越小全部携带点所对应的J_8值越大。管径及气体入口条件对流向反转点均无影响。气体入口条件对减少气流量的淹没消失点无影响,但管径不同对淹没消失点有影响。     

竖管内淹没及其消失滞后问题的研究

本文通过试验研究了竖管内淹没、流向反转以及淹没消失的滞后问题,研究了管径不同对这些过程的影响.采用无因次量J_g~*和J_L~*表达后,通过研究发现淹没开始点和流向反转点与管径无关;全部携带点与管径有关,而与注水量无关.根据试验结果给出了淹没过程中试验段内压差和流量的变化.当逐渐减少气体流量时,淹没点的消失会出现滞后,根据试验段的压差和流量变化分析了淹没消失滞后的原因和影响因素.根据试验数据整理出了相应的经验关系式.     

反应堆失水事故条件下热管段内的两相流逆向流动研究

对反应堆失水事故条件下热管段内的两相流逆向流动过程进行了实验研究和理论分析。实验回路由竖直管、倾斜管和水平管三段组成 ,研究发现在这种回路中水平管的长度对逆向流动的溢流开始点影响较大。对逆向流动的溢流开始点进行了实验研究和理论分析 ,对现有的国外计算模型进行了分析和比较 ,推荐了热管段内溢流开始点的计算关系式。     

矩形窄通道再淹没现象实验和数值研究

在反应堆发生大破口事故时,再淹没阶段可以有效地降低燃料元件温度,防止堆芯熔毁。为了预测再淹没过程中板状燃料元件的换热特性,进行了竖直矩形窄缝通道底部再淹没过程的实验研究。针对实验工况,基于商用软件CFX,通过耦合分析加热板和流体的方法研究竖直矩形窄缝通道底部再淹没过程。通过将数值模拟结果与实验结果进行对比,评价了相关模型的适用性,并验证了计算流体动力学(Computational Fluid Dynamics,CFD)方法在预测再淹没过程的有效性。基于验证后计算模型,对壁面初始温度、入口流速对再淹没过程的影响进行了分析,获得了相关初始条件对壁面温度变化的影响规律。     

扁管传热与阻力特性的实验研究

以水为工质,对3种不同几何尺寸的扁管进行了传热与流阻的实验研究.相同换热条件下3根扁管的传热系数和管内传热系数均高于圆管,管内传热系数最大可提高到圆管的2.43倍.说明扁管具有很好的强化传热效果,但压降也高于圆管.同时对扁管在套管内水平和竖直2种放置方式的换热情况进行了对比,实验结果表明竖直放置的传热效果优于水平放置.     

竖直向下大、小支管气相夹带起始可视化研究

已有气相夹带起始模型均是基于竖直向下的小支管夹带所得到的,用于分析大支管气相夹带时并不适用。本文基于可视化实验,对竖直向下的大、小尺寸T型管的气相夹带起始点进行对比研究。选择与主管道直径比为0.625和0.1的大、小支管,并采用有机玻璃作为实验管道材料,空气和水为实验工质。其实验现象表明：大、小支管夹带起始均有漩涡,且漩涡现象大致相同,但在大支管条件下会出现气室,夹带气体进入支管后也会在气室下翻腾,且在相同液相折算速度下,大支管夹带起始液位会高于小支管。     

竖直向下大、小支管气相夹带起始可视化研究

已有气相夹带起始模型均是基于竖直向下的小支管夹带所得到的,用于分析大支管气相夹带时并不适用。本文基于可视化实验,对竖直向下的大、小尺寸T型管的气相夹带起始点进行对比研究。选择与主管道直径比为0.625和0.1的大、小支管,并采用有机玻璃作为实验管道材料,空气和水为实验工质。其实验现象表明:大、小支管夹带起始均有漩涡,且漩涡现象大致相同,但在大支管条件下会出现气室,夹带气体进入支管后也会在气室下翻腾,且在相同液相折算速度下,大支管夹带起始液位会高于小支管。     

窄缝环形通道内流动阻力特性的实验研究

分别在换热和冷态条件下,对水平、竖直向上和竖直向下3个流动方向的窄缝环形通道进行了流动摩擦阻力实验研究.实验发现窄缝通道内流态转变点比普通流道有所提前.将实验结果与传统的阻力计算公式进行对比,分析了换热温差及流动方向对摩擦阻力的影响,对窄缝环形通道内阻力特性进行了探讨.     

竖直管内两相流逆向流动特性研究

实验发现在竖直管内两相流逆向流动过程中,由于气体的入口条件不同、淹没开始点可能出现在气相的入口处,也可能出现在出口处。由于出现的位置不同,淹没开始点所对应的气、水之间的关系式也不一样。这一实验结果对进一步研究淹没开始的机理有重要意义。根据两相流的流动特性,分析了出现这种现象的原因,提出应采用不同的关系式计算这 两种不同的淹没开始点。     

Experimental study on the air/water counter-current flow limitation in a model of the hot leg of a pressurized water reactor

An experimental investigation on the air/water counter-current two-phase flow in a horizontal rectangular channel connected to an inclined riser has been conducted. This test-section representing a model of the hot leg of a pressurized water reactor is mounted between two separators in a pressurized experimental vessel. The cross-section and length of the horizontal part of the test-section are (0.25 m × 0.05 m) and 2.59 m, respectively, whereas the inclination angle of the riser is 50°. The flow was captured by a high-speed camera in the bended region of the hot leg, delivering a detailed view of the stratified interface as well as of dispersed structures like bubbles and droplets. Countercurrent flow limitation (CCFL), or the onset of flooding, was found by analyzing the water levels measured in the separators. The counter-current flow limitation is defined as the maximum air mass flow rate at which the discharged water mass flow rate is equal to the inlet water mass flow rate.From the high-speed observations it was found that the initiation of flooding coincides with the formation of slug flow. Furthermore, a hysteresis was noticed between flooding and deflooding. The CCFL data was compared with similar experiments and empirical correlations available in the literature. Therefore, the Wallis-parameter was calculated for the rectangular cross-sections by using the channel height as length, instead of the diameter. The agreement of the CCFL curve is good, but the zero liquid penetration was found at lower values of the Wallis parameter than in most of the previous work. This deviation can be attributed to the special rectangular geometry of the hot leg model of FZD, since the other investigations were done for pipes.     

Erratum to “Experimental study on the air/water counter-current flow limitation in a model of the hot leg of a pressurized water reactor”

This paper replaces the paper published in the journal by Deendarlianto et al. (2008). Because of an error in the implementation of the air flow meter some of the data given by Deendarlianto et al. (2008) are wrong. They are corrected within the present paper. The general results and conclusions remain unchanged.An experimental investigation on the air/water counter-current two-phase flow in a horizontal rectangular channel connected to an inclined riser has been conducted. This test-section representing a model of the hot leg of a pressurized water reactor is mounted between two separators in a pressurized experimental vessel. The cross-section and length of the horizontal part of the test-section are (0.25 m × 0.05 m) and 2.59 m, respectively, whereas the inclination angle of the riser is 50°. The flow was captured by a high speed camera in the bended region of the hot leg, delivering a detailed view of the stratified interface as well as of dispersed structures like bubbles and droplets. Counter-current flow limitation (CCFL), or the onset of flooding, was found by analyzing the water levels measured in the separators. The counter-current flow limitation is defined as the maximum air mass flow rate at which the discharged water mass flow rate is equal to the inlet water mass flow rate.From the high-speed observations it was found that the initiation of flooding coincides with the formation of slug flow. Furthermore, a slight hysteresis was noticed between flooding and deflooding. The CCFL data was compared with similar experiments and empirical correlations available in the literature. Therefore, the Wallis-parameter was calculated for the rectangular cross-sections by using the channel height as length, instead of the diameter. The agreement of the CCFL curve is good, but the zero liquid penetration was found at lower values of the Wallis parameter than in most of the previous work. This deviation can be attributed to the special rectangular geometry of the hot leg model of HZDR, since the other investigations were done for pipes.     

Assessment of flooding in a best estimate thermal hydraulic code ( COBRA/TRAC)

The performance of COBRA/TRAC code in predicting the flooding, the counter-current flow limit, is evaluated in three geometries important to nuclear reactor loss-of-coolant accident evaluation; a vertical pipe, a perforated plate, and a downcomer annulus. These flow limits are computationally evaluated through transient conditions. The flooding in the vertical pipe is compared with the classical Wallis flooding limit. The flooding on the perforated plate is compared with the Northwestern flooding data correlation. The downcomer flooding in 1/15th and 1/5th scale model is compared with the Creare data. Finally, full scale downcomer flooding is compared with the UPTF test data. The prediction capability of the code for the flooding is found to be very good.     

Wall pressure measurements of flooding in vertical countercurrent annular air-water flow

An experimental study of flooding in countercurrent air-water annular flow in a large diameter vertical tube using wall pressure measurements is described in this paper. Axial pressure profiles along the length of the test section were measured up to and after flooding using fast response pressure transducers for three representative liquid flow rates representing a wide range of liquid Reynolds numbers (Re_L = 4Γ/μ; Γ is the liquid mass flow rate per unit perimeter; μ is the dynamic viscosity) from 3341 to 19,048. The results show that flooding in large diameter tubes cannot be initiated near the air outlet and is only initiated near the air inlet. Fourier analysis of the wall pressure measurements shows that up to the point of flooding, there is no dominant wave frequency but rather a band of frequencies encompassing both the low frequency and the broad band that are responsible for flooding. The data indicates that flooding in large diameter vertical tubes may be caused by the constructive superposition of a plurality of waves rather than the action of a single large-amplitude wave.     

垂直管内蒸汽冷凝回流阻液分析模型的研究

在汽液两相分离流动模型的基础上，建立了垂直管内蒸汽冷凝回流阻液分析模型。采用该模型对单根Ｕ型管内蒸汽冷凝回流实验参数下的阻液起始点进行计算，计算结果与实验结果符合较好。分析模型还与现有分析模型和经验关系式进行了比较，结果表明，本模型与ＤｕｋｌｅｒＳｍｉｔｈ关系式符合较好，而与Ｋｕｔａｔｅｌａｄｅｚ类型关系式和其它分析模型的偏差相对较大。     

Flooding limited CHF in a vertical 3 × 3 rod bundle with non-uniform axial heat flux

KAERI has performed an experimental study on the critical heat flux (CHF) under zero flow conditions with a non-uniformly heated 3 × 3 rod bundle. Experimental conditions are in the range of a system pressure from 0.50 to 14.96 MPa and inlet water subcooling enthalpies from 68 to 352 kJ/kg. The test section used in the present experiments consisted of a vertical flow channel, upper and lower plenums, and a non-uniformly heated 3 × 3 rod bundle. The experimental results show that the CHFs in low-pressure conditions are somewhat scattered within a narrow range. As the system pressure increases, however, the CHFs show a good parametric trend. The CHFs occur in the upper region of the heated section, but the locations of the detected CHFs move gradually in a downward direction with the increase of the system pressure. Even though the effects of the inlet water subcooling enthalpies and system pressure of the flooding CHF are relatively smaller than those of the flow boiling CHF, the CHF increases by increasing the inlet water subcooling enthalpies. Several existing correlations for the countercurrent flooding CHF based on Wallis's flooding correlation and Kutateladze's criterion for the onset of flooding are compared with the CHF data obtained in the present experiments to examine the applicability of the correlations.     

Steam-water interactions in a vertical tube

When subcooled water is introduced into a vertical tube in which steam is flowing upward the phenomena of flooding are strongly influenced by the condensation effects. An experimental investigation is reported which has delineated the flow regimes that occur. Flow regime transitions have been identified through analysis and/or dimensionless empirical correlations. A method of analysis has been developed to predict the oscillatory motion of a liquid plug that occurs in certain regions.     

Two-phase countercurrent flow in a model of a pressurized water reactor hot leg

The onset of flooding or countercurrent flow limitation (CCFL) determines the maximum rate at which one phase can flow countercurrently to another phase. In the present study, the experimental data of the CCFL for gas and liquid in a horizontal pipe with a bend are investigated. The different mechanisms that lead to flooding and that are dependent on the liquid flow rate are observed. For low and intermediate liquid flow rates, the onset of flooding appears simultaneously with the slugging of unstable waves that are formed at the crest of the hydraulic jump. At low liquid flow rates, slugging appears close to the bend; at higher liquid flow rates, it appears far away from the bend, in the horizontal section. For high liquid flow rates, no hydraulic jump is observed, and flooding occurs as a result of slug formation at the end of the horizontal pipe. The effects of the inclination angle of the bends, the liquid inlet conditions and the length of the horizontal pipes are of significance for the onset of flooding. A mathematical model of Ardron and Banerjee is modified to predict the onset of flooding. Flooding curves calculated by this model are compared with present experimental data and those of other researchers. The predictions of the onset of flooding as a function of the length-to-diameter ratio are in reasonable agreement with the experimental data.