低压高过冷度下自然循环流动不稳定性实验研究

对具有长直上升段的自然循环系统,开展了流动不稳定性实验研究。同时,详细分析了低压、高入口过冷度条件下典型的流动不稳定现象。实验表明：自然循环系统的结构、流体的热边界条件会影响自然循环的运行特性及流动不稳定性类型。较高入口过冷度下,高热流密度导致系统脱离稳态后,很难重新回到稳定的两相自然循环流动状态。随着热流密度的提高,系统会经历间歇沸腾、复合动态流动不稳定性等状态。依据实验结果得到了高入口过冷度下的不稳定性边界图。在两相振荡期间,自然循环驱动压头和回路阻力的主要影响因素集中在长直上升段和加热段。加热段出口积聚的大量气泡对上、下游流体的强烈挤压作用是流量大幅振荡及逆流的主要原因。     

低压流动稳定性实验研究(英文)

在5MW核供热反应堆模拟热工水力学实验回路HRTL-5上研究了在低压(P=0.1,0.24MPa)自然循环各种进口过欠热度条件下,单相及两相流流动特性。研究了不同种类的流动不稳定性,如,欠热沸腾不稳定性,欠热沸腾引起的闪蒸不稳定性,纯闪蒸不稳定性,密度波-闪蒸耦合不稳定性及高频流动振荡。研究结果表明:低压自然循环系统在绝大部分进口欠热度条件下,其两相流流动是不稳定的,仅在小进口欠热度条件下可获得稳定的两相流流动;在高进口欠热度条件下,加热段中的欠热沸腾控制流动不稳定,在中进口欠热度条件下,加热段中的欠热沸腾及上升段中的空泡闪蒸控制流动不稳定。     

两相自然循环系统压降震荡流动不稳定性起始点研究

对两相自然循环系统的压降震荡流动不稳定起始点进行研究。实验研究发现当实验本体流体出现充分发展的过冷泡核沸腾后,由于汽泡大量产生,以及稳压器上部在可压缩气体的作用下,自然循环回路与稳压器之间出现波动流量,自然循环系统出现压降震荡型流动不稳定。Bowring模型和Saha-Zuber模型预测实验本体出口发生充分发展欠热泡核沸腾的功率值与与自然循环系统的压降震荡流动不稳定起始点功率实验数据的偏差在8%以内。因此,充分发展的过冷泡核沸腾起始点可认为是自然循环系统的压降震荡流动不稳定起始点。     

欠热沸腾诱发自然循环不稳定性的研究

以最佳估算程序RELAP5为基本分析工具,对自然循环系统进行数值分析,得出了不同条件下系统的不稳定性边界。研究发现自然循环对过冷沸腾有一定的承受能力,不稳定性一般发生在低欠热沸腾区,气泡脱离壁面和凝结时的扰动可能是自然循环系统不稳定性的诱因,系统驱动力、阻力和流量之间的相位差使振荡得以维持和发展。     

自然循环流动不稳定条件下的传热特性实验研究

为探究流动不稳定性机理,在低压自然循环系统中开展了一系列相关实验,分析了不同流量振荡模式下自然循环的沸腾传热机制及局部传热特性。实验表明：中、低热流密度下出现的较规则的周期性振荡由加热段内流动沸腾诱发,壁面过热度不会随流量振荡而大幅度变化;高热流密度下自然循环系统出现的周期性不规则振荡现象中,流动沸腾类型间的相互转变不是流量波动的唯一原因。大幅度的流量脉动可能在高热流密度下导致沸腾临界的发生,出口壁面出现间歇性干涸,局部传热系数下降的同时伴随壁温的短暂飞跃。随着热流密度的提高,自然循环系统可能出现持续性干涸。     

低压自然循环复合流量脉动实验研究

在低压流动沸腾不稳定性实验中,研究了自然循环流动在不同入口过冷度下的演化过程。对实验中的流动沸腾不稳定性入口流量信号进行快速傅里叶变换,基于振幅和频率特性区分了3种流动脉动模式：小幅流量脉动、复合流量脉动和逆流。分析了加热功率和入口过冷度对自然循环不稳定性的影响。根据加热段出口水温变化得到了出口的流型变化,当流量波动振幅较小时加热段出口流体始终是饱和状态,而当流量波动振幅较大时,加热段出口为单相液体和两相混合物交替通过。给出了这3种流量脉动的边界图,分析了热流密度和入口过冷度对流量脉动模式的影响。结果表明：出口含气率大于0时发生流动不稳定性,热流密度达到间歇干涸型临界热流密度时发生逆流。     

低压自然循环复合流量脉动实验研究

在低压流动沸腾不稳定性实验中,研究了自然循环流动在不同入口过冷度下的演化过程。对实验中的流动沸腾不稳定性入口流量信号进行快速傅里叶变换,基于振幅和频率特性区分了3种流动脉动模式:小幅流量脉动、复合流量脉动和逆流。分析了加热功率和入口过冷度对自然循环不稳定性的影响。根据加热段出口水温变化得到了出口的流型变化,当流量波动振幅较小时加热段出口流体始终是饱和状态,而当流量波动振幅较大时,加热段出口为单相液体和两相混合物交替通过。给出了这3种流量脉动的边界图,分析了热流密度和入口过冷度对流量脉动模式的影响。结果表明:出口含气率大于0时发生流动不稳定性,热流密度达到间歇干涸型临界热流密度时发生逆流。     

低压流动稳定性实验研究

在5MW核供热反应堆模拟热工水力学实验回路HRTL-5上研究了在低压(p=0.1,0.24MPa)自然循环各种进口过欠热度条件下,单相及两相流流动特性。研究了不同种类的流动不稳定性,如,欠热沸腾不稳定性,欠热沸腾引起的闪蒸不稳定性,纯闪蒸不稳定性,密度波-闪蒸耦合不稳定性及高频流动振荡。研究结果表明:低压自然循环系统在绝大部分进口欠热度条件下,其两相流流动是不稳定的,仅在小进口欠热度条件下可获得稳定     

开式自然循环系统不稳定性实验研究

核电站非能动安全系统依靠自然循环将热量导出,然而系统中的驱动压头、流动阻力、流量等相互影响,容易引发流动不稳定性,导致流动沸腾临界热流密度大幅降低,带来安全问题。因此,流动稳定性是自然循环热力系统的重要研究对象。本文以开式竖直加热圆管为实验本体,通过实验和物理建模的方法,研究了自然循环条件下管内间歇沸腾现象和流动不稳定特性。研究结果表明：随着热流密度的升高,系统将经历初始状态、低频脉动、高频脉动和稳定的自然循环四个阶段。基于实验数据,建立了不稳定边界的预测模型,预测值和实验值符合良好,误差在±10%内。     

基于RELAP5的单通道自然循环流动不稳定性分析

针对某一自然循环实验,利用RELAP5程序对其建模,并进行数值分析,得出了该系统的流动不稳定性边界。对不同压力和不同上升段结构尺寸下的流动不稳定性边界及流量振动曲线进行了比较,分析了原因。最后,讨论了欠热沸腾对自然循环流动不稳定性的影响。研究结果可为自然循环系统的工程设计提供一定的借鉴。     

低干度自然循环流量漂移的特征曲线图谱分析

在5MW低温核供热堆全模拟试验回路(HRTL-5)上,实验观察到了低干度自然循环条件下的流量漂移现象.通过一个考虑了加热段欠热沸腾、上升段冷凝、闪蒸等物理过程的两相流动数学模型,编制了相应的计算程序,获得了自然循环特征曲线图谱及其运行曲线,确定了自然循环分岔图和静态不稳定边界图,进而提出了通过自然循环特征曲线图谱研究流量漂移的分析方法.分析表明:特征曲线图谱方法是研究自然循环静态不稳定的有效手段.增大系统压力、减小热流密度、增加入口单相阻力、减小出口两相阻力有利于避免自然循环流量漂移的发生.     

中国先进研究堆自然循环两相流动不稳定性分析

应用均相流模型对中国先进研究堆自然循环两相流动不稳定性进行数值分析计算，获得了自然循环不稳定性边界，分析了流量、压降、壁温、流体温度以及沸腾边界等参数在不稳定工况下的变化。研究结果为中国先进研究堆的安全运行和事故分析提供了重要参考。     

Two-phase instability analysis in natural circulation loops of China advanced research reactor

In this paper, two-phase flow instability in natural circulation loops of China Advanced Research Reactor (CARR) has been investigated. CARR is a low pressure and low power density research reactor. A natural circulation instability analysis model is developed for the natural circulation loop of CARR. The homogeneous flow model is used to establish the system control equations. The non-uniform heating and subcooled boiling heat transfer is included. The accumulation heat of the wall is also included. Numerical method of Gear is employed to solve the system equations documented in terms of ordinary differential equations. According to the calculation results, stability maps of the natural circulation loop, which confirm the presence of an instability region under the conditions of low equilibrium quality in the outlet and low pressure, are obtained. It is a special kind of density wave oscillation (DWO) that occurs in very low equilibrium quality region with the characteristics of geysering and ‘Type-I’ DWO at the same time. The calculation results show such oscillation course clearly. The variations of the mass flow rate, the pressure drop and the boiling boundary are analyzed separately. Especially, the phase-space trajectory of the boiling boundary and the mass flow rate is discussed. Finally the oscillation frequency is discussed. The calculated results have important significance for the safety operation and accidental analysis of CARR.     

Flow excursion phenomenon and its mechanism in natural circulation

An experiment was performed on the test loop (HRTL-5), which simulates the geometry and system design of a 5-MW nuclear heating reactor. In a wide range of inlet subcoolings, different flow modes, such as single-phase stable flow, subcooled boiling stable flow, subcooled boiling static flow excursion, density-wave oscillation and stable two-phase flow in the natural circulation system have been described. The phenomenon and mechanism of the static flow-excursion, which has never been studied well on this field, is especially interpreted. The experimental results show that, in the process of flow excursion, the mass flow rate and the inlet temperature decreases, while the exit temperature increases smoothly. As the process of the excursion continues for about 1 h, short period dynamic flow oscillation occurs, which can only be seen in the process of this static flow excursion, and has also never been studied well. These static and dynamic flow instabilities combine together and continue for about 2 h, then a point is reached, at which the static flow excursion disappears, but the dynamic flow oscillation continues. The mechanism of the static flow excursion is interpreted through two sets of curves for flow resistance pressure drop and driven head in natural circulation, and one curve for the natural circulation operation under special thermohydraulic condition. The study of the flow excursion and its concerned dynamic flow oscillation is of great significance for the development of the nuclear heating reactor under natural circulation.     

Experimental investigations on steady state natural circulation behavior of multiple parallel boiling channel system

In some industrial applications, including nuclear power plants, natural circulation flow is often employed as a reliable heat transport method. A common characteristic of many industrial two-phase natural circulation systems is the presence of a large number of parallel boiling channels. Sensitivity of the steady state behavior of such a two-phase natural circulation system to different system parameters has many implications vis-à-vis performance of the system as per the design intent under various operating conditions. This article reports the results of experimental studies carried out on the characteristics of a low pressure two-phase natural circulation system with parallel boiling channels having their individual heat sources. The work covers the study of dependence of system behavior on operational history, down-comer resistance and channel power. In view of its particular significance in nuclear industry, a special system condition with zero power in one of the parallel channels was also studied. An experimental setup consisting of 10 transparent parallel channels was designed and constructed for conducting these experimental investigations.     

Experimental observation of flow instability in a semi-closed two-phase natural circulation loop

In this experimental study, the flow instabilities within a semi-closed two-phase natural circulation loop were examined, with an emphasis placed on the role of the expansion-tank-line resistance. Six different modes of loopwise natural circulation were identified: the single-phase natural circulation, periodic two-phase natural circulation with a nonboiling period between the cycles, two-phase continuous circulation (stable circulation), and three other modes of the two-phase natural circulation characterized by different ranges of the cyclic period. The results were also shown in the instability map in the plane of the heat flux and the heater-inlet subcooling. When the frictional resistance at the expansion-tank line becomes larger, the circulation becomes stable, especially at the high heat-flux and high inlet-subcooling conditions, and, as a whole, the stable operation region becomes larger in the instability map. Similarly, the longer expansion-tank line stabilizes the system. However, unlike the analytical prediction, the excursive instability was not identified with the semi-closed loop due to the flow restriction at the expansion-tank line.     

竖直管道内间歇式两相流动沸腾特性分析

自然循环或重力注水过程的热功率、冷却剂流量等操作条件较小,易出现各种流动不稳定现象,影响核反应堆事故的发展进程,间歇式流动沸腾现象就属于其中的一种。以去离子水为工质,采用2×2加热棒束,对内径为32 mm竖直通道内的间歇式流动沸腾现象进行了实验研究,分析了不同热流密度下间歇式流动沸腾不稳定现象的变化规律,讨论了热流密度对间歇式沸腾周期的影响。结果表明,在一定的热流密度条件下,当加热通道内流体达到饱和并过热时,会发生周期性地剧烈喷涌及冷液回流现象,期间伴随泡状流、弹状流、搅混流及环状流等多种流动形态;间歇喷涌周期取决于沸腾停滞时间,随热流密度的不断增大,沸腾停滞时间缩短,间歇喷涌周期也缩短。当热流密度增大到一定程度时,间歇式流动沸腾现象消失,从而转变为另一种两相流动不稳定现象。     

Advances on the research on nonlinear phenomena in boiling natural circulation loop

The state-of-the-art of theoretical investigations on the flow oscillations that occur in a boiling natural circulation loop has been presented here. Motivation behind the work is to develop a high-fidelity model that is capable of predicting nature of flow instabilities more accurately. At the low pressures and low heat fluxes conditions, the major four types of instabilities may occur in boiling natural circulation loop depending on operating conditions: Flow excursion, Geysering instability, Flashing-induced instability and Type I density-wave oscillations. The characteristics of different instabilities as well as the effects of different operating and geometric parameters on them have been reviewed. The objective of this review is to gather the research findings on the nonlinear stability phenomena in various boiling flow channel systems over a period of several years. This review indicates that most of the theoretical predictions of amplitudes and periods of the sustained oscillations are carried out using two models, namely, homogeneous equilibrium model (HEM) (still debatable) and drift-flux model (DFM) (more realistic) and are validated by experimental findings. This review work on theoretical investigations presented in this paper indicates that there are enough scopes for improving mathematical formulations of the natural circulation boiling loop (NCBL) for thermohydraulic instabilities.