竖直圆管内欠热和含汽流动沸腾临界热流密度实验研究

正在直径为8.2mm、加热长度为2.4m的均匀加热圆管上对欠热和含汽强迫流动沸腾工况下的临界热流密度(CHF)进行了实验,覆盖的参数范围为:压力为3～21MPa,质量流速为963～3 883kg/(m~2·s),出口含汽率为-0.87～0.78。系统参数研究表明:CHF随进口欠热度和质量流速的增加而呈线性增加,随进口含汽率的增加而迅速减小。在次临界压力区域,CHF随压力的增加而减小,欠热度对CHF的影响减弱。不同含汽量的工况下,CHF     

垂直圆管内超临界R134a对流传热实验研究

为研究超临界压力下的对流传热特性,对超临界压力氟利昂R134a在内径25 mm垂直圆管中的受热上升流动传热进行了实验研究,获得压力4.5 MPa和4.7 MPa、质量流速G=400~700 kg/(m2·s)、热流密度q=30~60 k W/m2的实验数据,对换热强化和传热恶化的规律和特性以及其影响因素进行了分析。结果发现,在拟临界区附近,超临界压力R134a出现明显的强化换热现象。在低质量流速或高热流密度下发生传热恶化,其恶化边界为q/G0.06 k J/kg。在特定的工况下观察到两次传热恶化:第一次发生在临近入口区域,在不同流体入口温度下均观测到恶化;第二次发生在远离入口区域,仅在一定流体焓值范围内存在。实验参数敏感性分析表明,传热强化随质量流速的增加、热流密度的减小、压力的降低而增加,而传热恶化则相反。     

竖直圆管内向上流动的干涸实验研究

在直径为8.2 mm的竖直向上均匀加热圆管上进行了干涸型临界热流密度实验研究，加热长度2.4 m，压力3.2～19.7 MPa，质量流速963～2 707 kg/（m²•s），进口欠热度34～213 ℃，出口含汽率0.11～0.78。研究发现：临界热流密度随进口欠热度、质量流速的增加而线性增加，随出口含汽率的增加而迅速减小。通过对临界气液两相参数的分析发现，本实验参数范围内，蒸汽速度是导致干涸的主要原因。当达到临界蒸汽速度时，近壁面液体消失触发临界。随压力的增加，表面张力逐渐减小，液膜更易被撕裂，因而临界蒸汽速度随压力的增加而减小。从高压实验数据出发得到临界蒸汽速度U_cr，参考Steen和Wallis推荐的夹带开始速度U₀，建立了预测临界蒸汽速度的模型：U_cr=25U₀+4。利用低压实验数据对预测模型进行了验证，符合较好。     

环形通道内钠流动起始沸腾壁面过热度实验研究

对环形通道内金属钠起始沸腾壁面过热度进行实验研究。实验段长800 mm,环形通道外径10 mm,内径6 mm。电加热元件最高热流密度为846 kW/m²,进口过冷度为63.1～287.8 ℃,质量流量为7.2～122.0 kg/h,系统压力为0.85～28.79 kPa。实验结果表明,起始沸腾壁面过热度随热流密度和进口过冷度的增加而升高,随质量流量和系统压力的增加而降低。拟合得到了关于起始沸腾壁面过热度的半经验关系式,关系式计算结果与实验数据符合良好。     

窄缝通道内过冷沸腾区域汽泡脱离频率研究

采用高速摄像仪对矩形窄缝通道内垂直上升流过冷流动沸腾区域汽泡脱离频率进行可视化实验研究。结果表明,汽泡脱离频率随质量流速的增大而减小,随入口过冷度的增大而减小,随热流密度的增大而增大。将实验数据与文献中汽泡脱离频率计算模型进行比较,发现基于池式沸腾和饱和流动沸腾开发的计算模型不能准确预测过冷沸腾区域汽泡脱离频率。本文以无量纲参数的形式,分别用液相雷诺数、过冷雅各布数和核态沸腾热流密度表示质量流速、主流过冷度和热流密度对汽泡脱离频率的影响,获得矩形窄缝通道内过冷沸腾区域汽泡脱离频率预测关系式,关系式的平均预测误差为±17.1%。     

环形窄缝双面加热通道内欠热沸腾传热实验研究

在压力0.84～6.09 MPa、质量流速41.9～300.2 kg/(m2·s)、热流密度2.61～114.41 kw/m2范围内,以去离子水为工质,对间隙为1.5 mm环形窄通道实验段竖直向上流动的欠热沸腾传热特性进行了实验研究,得出了适用环形窄缝通道的欠热沸腾传热经验关系式。     

稳态和瞬态流动条件下低压欠热沸腾水的临界热流密度实验研究

稳定流动和流量衰减条件下,在内径15.9mm的圆管上进行欠热沸腾水的临界热流密度实验,覆盖的参数范围为:压力p=0.2～1.7MPa,速度v=2.1～13.5m/s,出口欠热度ΔTs=0～110K,临界热流密度qCHF=(3.2～13.5)×106W/m2。结果表明,对于稳定流动条件,在较高压力下,临界热流密度随ΔTs的减少基本上呈单调下降趋势。然而,对于p≤0.3MPa,在ΔTs降低到30K以下的一定值时(此值随流速变化而有所不同,且较大值对应较高流速),临界热流密度达到最低值,此后,随ΔTs进一步降低临界热流密度转而升高,并伴随摩擦压降陡峭增大。对于流量衰减的流动工况,在较高…     

竖直圆管下降流过渡沸腾传热实验研究

采用热块骤冷实验技术、非稳态一维数值分析方法和多元回归分析技术对竖直圆形元件管内下降流过渡沸腾传热特性进行了研究，建立了一组以ＣＨＦ点和最小膜态沸腾点（ＭＩＮ）为基础的过渡沸腾传热特性两点模型，和可以反映压力、流量和入口过冷度对过渡沸腾曲线影响的多变量数据分析模型。采用一维非稳态数值分析方法建立热块及试验管的精细温场分布，推导管内壁温度和热流密度，采用本文的模型和多元回归分析技术整理实验数据，得到一组过渡沸腾传热特性的半经验关系式，其适用于：Ｇ＝７０－２２５６ｋｇ／ｍ２·ｓ；Ｐ＝０．３－１６ＭＰａ；ΔＴｓｕｂ＝６℃－７５℃；预测结果与实验数据吻合较好。对主要流动参数对过渡沸腾传热特性的影响作了趋势分析和机理浅析。     

简单通道内超临界水传热特性实验研究

针对各国超临界水冷堆燃料组件设计方案,选取圆管、圆环形通道、方环形通道3种具有热工水力代表性的简单通道,开展超临界条件下水工质的传热特性实验研究。实验结果表明,热流密度、质量流速和压力3种热工参数对不同简单通道传热特性的影响趋势基本一致;在相同质量流速和压力下,换热系数在靠近拟临界温度处存在峰值,且随热流密度的增大而减小;在相同热流密度和压力下,相同主流体焓处对应的换热系数随着质量流速增加而增加;压力对超临界水传热特性影响较弱,仅在拟临界区域内换热系数峰值稍有不同;实验中出现了拟临界区域的传热恶化现象,传热恶化发生时壁温出现局部峰值。     

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。     

Applications of Artificial Neural Network for the Prediction of Flow Boiling Curves

An artificial neural network (ANN) was applied successfully to predict flow boiling curves. The databases used in the analysis are from the 1960's, including 1,305 data points which cover these parameter ranges: pressure P=100–1,000 kPa, mass flow rate G=40–500 kg/m²-s, inlet subcooling ΔT_sub =0–35°C, wall superheat ΔT_w = 10–300°C and heat flux Q=20–8,000kW/m². The proposed methodology allows us to achieve accurate results, thus it is suitable for the processing of the boiling curve data. The effects of the main parameters on flow boiling curves were analyzed using the ANN. The heat flux increases with increasing inlet subcooling for all heat transfer modes. Mass flow rate has no significant effects on nucleate boiling curves. The transition boiling and film boiling heat fluxes will increase with an increase in the mass flow rate. Pressure plays a predominant role and improves heat transfer in all boiling regions except the film boiling region. There are slight differences between the steady and the transient boiling curves in all boiling regions except the nucleate region. The transient boiling curve lies below the corresponding steady boiling curve.     

An investigation of transition boiling mechanisms of subcooled water under forced convective conditions

A mechanistic model for forced convective transition boiling has been developed to investigate transition boiling mechanisms and to predict transition boiling heat flux realistically. This model is based on a postulated multi-stage boiling process occurring during the passage time of the elongated vapor blanket specified at a critical heat flux (CHF) condition. Between the departure from nucleate boiling (DNB) and the departure from film boiling (DFB) points, the boiling heat transfer is established through three boiling stages, namely, the macrolayer evaporation and dryout governed by nucleate boiling in a thin liquid film and the unstable film boiling characterized by the frequent touches of the interface and the heated wall. The total heat transfer rates after the DNB is weighted by the time fractions of each stage, which are defined as the ratio of each stage duration to the vapor blanket passage time. The model predictions are compared with some available experimental transition boiling data. The parametric effects of pressure, mass flux, inlet subcooling on the transition boiling heat transfer are also investigated. From these comparisons, it can be seen that this model can identify the crucial mechanisms of forced convective transition boiling, and that the transition boiling heat fluxes including the maximum heat flux and the minimum film boiling heat flux are well predicted at low qualities/high pressures near 10 bar. In future, this model will be improved in the unstable film boiling stage and generalized for high quality and low pressure situations.     

针对REPEC加热实验的RELAP5程序模拟与分析

为研究压力容器外部流道的冷却能力及流动传热过程,在反应堆压力容器外部冷却(REPEC, Reactor Pressure vessel External Cooling)实验台架前期加热实验的基础上,采用RELAP5程序对实验工况进行模拟和对比。模拟结果与实验数据一致性较好。随加热热流、进出口面积的增加,系统内自然循环流量也增加;入口欠热度对自然循环流量的影响不是很明显;近饱和沸腾条件下,系统出现明显的两相不稳定流动。     

Application of an Artificial Neural Network in Reactor Thermohydraulic Problem: Prediction of Critical Heat Flux

A new method for predicting Critical Heat Flux (CHF) with the Artificial Neural Network (ANN) method is presented in this paper. The ANNs were trained based on three conditions: type I (inlet or upstream conditions), II (local or CHF point conditions) and III (outlet or downstream conditions). The best condition for predicting CHF is type II, providing an accuracy of ±10%. The effects of main parameters such as pressure, mass flow rate, equilibrium quality and inlet subcooling on CHF were analyzed using the ANN. Critical heat flux under oscillation flow conditions was also predicted.     

竖直矩形窄缝通道内过冷沸腾传热特性的实验研究

以去离子水为工质,在进口压力为0.1~0.3 MPa、质量流速为200~1400 kg?m-2?s-1、热流密度为20~320 kW?m-2的参数范围内,对截面参数为50 mm×2 mm的竖直矩形窄缝通道展开了传热实验研究。实验获得通道内部工质由单相状态到过冷沸腾状态的传热过程曲线,将过冷沸腾段实验值与8个经验公式提供的预测值进行了对比与分析,采用相似原理以及回归分析法,建立了适用于竖直矩形窄缝通道的过冷沸腾准则关系式。研究结果表明,在竖直矩形窄缝通道内,热流密度对过冷沸腾传热具有主导作用;对于本实验的窄缝通道,Bertsch传热公式对于过冷沸腾段的预测效果相较于其他公式更好,本研究所建立的准则关系式与实验数据符合良好。因此,本研究建立的公式能够用于竖直矩形窄缝通道过冷沸腾传热系数的预测。      

临界热流密度的人工神经网络预测法

本文成功地训练了3种用于预测临界热流密度(CHF)的人工神经网络,其输入参数分别是系统压力、质量流速、平衡含汽量;其输出参数是CHF.通过人工神经网络,分析了压力、流量、热平衡含汽量和进口过冷度对CHF的影响,且成功地将人工神经网络应用于CHF的预测中,预测结果与实验值符合很好.分析结果表明:人工神经网络训练的3种类型中,类型Ⅱ的预测精度最高,可达±10%.     

Density Wave Instability of Sodium Boiling Two-phase Flow in a Vertical Annulus at Low Pressure

Experiments of density wave instability in a sodium boiling two-phase flow in an annulus were carried out with the parameters of heat flux from 80 to 976kW/m², inlet subcooling from 25.6 to 226.8°C, mass flow rate from 7.92 to 68.9 kg/h, and system pressure from 2,600 Pa to 0.06 MPa. It was found that the density wave instability occurred in the case of low exit quality, and the oscillation of flow rate was so large that the flow would be reversal. The lower inlet temperature, the higher system pressure and the larger mass flow rate could result in a more stable boiling two-phase flow. The oscillation period of the instability increased with the system pressure and the inlet subcooling, but it decreased with the mass flow rate. A correlation for the onset condition of the density wave instability was obtained from the experimental data.     

A study of the sensitivity of loca heat transfer analysis for a water-cooled reactor system

Results are given of computer calculations, using the reactor thermal analysis code THETA1-B, to determine the significance and relative importance of various heat transfer regimes in predicting maximum fuel cladding temperature for the blowdown phase of a postulated loss-of-coolant accident (LOCA) in a pressurized water reactor system. The factors considered include the choice of heat transfer correlation for a particular heat transfer regime, the method of delineating the boundaries between regimes, and core inlet coolant flow conditions.For a hot-leg rupture, the maximum surface temperature is sensitive to a number of factors, including choices of critical heat flux correlation, flow boiling transition heat transfer correlation, and in particular, stable film flow boiling correlation. However, for a LOCA resulting from a double-ended rupture of an inlet feeder, these factors have only marginal effects on maximum cladding temperature. In this case the importance of heat transfer to dry steam coolant at low net flow rate conditions is demonstrated, indicating a need for further information.     

环形通道内液态金属钠沸腾两相传热特性实验研究

对环形通道内液态金属钠沸腾两相流动特性进行了实验研究。实验中,系统压力为3.6~110.0kPa,热流密度为11~600kW·m~(-2),流速为0.02~0.45m·s~(-1)。实验结果表明,液态金属钠沸腾传热系数与壁面热流密度和系统压力有强烈关系,而与入口过冷度和质量流速无关。在本文实验数据基础上,拟合得到了计算液态金属钠沸腾两相传热系数的关系式,通过与各组实验数据间的比较,证明本文关系式适用于计算环形通道内液态金属钠沸腾两相传热系数。     

R134a卧式螺旋管内沸腾两相流型与传热特性实验研究

在蒸发温度为5～15 ℃、热流密度范围为5～20 kW·m^-2、工质质量流速变化范围为50～500 kg·m^-2·s^-1和干度范围为0.01～0.9的条件下,对R134a在卧式螺旋管内的沸腾两相流型及传热特性进行了实验研究。利用可视化技术对流型进行了观察分析,发现在相同工况条件下,卧式螺旋管上升段和下降段的流型有所不同,特别是形成环状流之前存在明显不同的过渡流型,分别为波环状流型和超大气弹流型,因此,对上升段和下降段分别建立了流型图。获得了传热系数随工质的干度、质量流速和热流密度等参数的变化关系,发展了R134a在卧式螺旋管内流动沸腾传热系数的计算关联式。