竖直及倾斜环隙流道内自然对流沸腾临界热负荷

以水为工质 ,在常压下对垂直和倾斜环隙流道内的自然对流沸腾临界热负荷进行了实验研究和理论分析 ,得到了计及进出口局部阻力的计算公式 ,讨论了流道几何尺寸、几何形状、倾角、压力和进出口局部阻力等因素对临界热负荷的影响 ,最后提出了一个新的 ,可用于计算竖直环隙、圆管及长方形流道内自然对流沸腾临界热负荷的半经验公式 ,其计算精度和适用范围较现有的计算公式有显著提高 ,原则上不受H/De 值大小的限制。     

微细化沸腾传热实验研究

气泡微细化沸腾是沸腾到达某个临界热负荷后,加热面温度升高不大,与该临界热负荷相比,热流密度大幅提高的沸腾现象。本文在设计完成一可视化实验装置的基础上,通过高速摄影仪观察并结合采集的壁温数据,对常压下直径为10 mm铜加热面上的池式气泡微细化沸腾现象进行了研究,并讨论了液体过冷度对其的影响。实验发现,气泡微细化沸腾状态下,加热面上生成1层极其不稳定的气膜,气液交界面上不停地有大量微小气泡生成并以极高速度射入过冷液体中。随加热面热流密度的增大,气膜厚度波动周期缩短,气膜最大厚度减小,所生成微小气泡的直径也明显减小。实验中获得的最高热流密度达9 MW/m²。     

加热面朝下的池沸腾汽泡动态行为研究

基于Matlab软件开发了自动识别气液两相流界面程序,程序可获得气液界面变化、汽膜厚度、汽膜脱离周期和汽膜法向速度等特征。利用该程序对沟槽结构加热表面朝下布置时,在不同倾角、不同热流密度下的汽泡动态数据进行了处理和分析。结果表明：加热表面朝下发生核态沸腾时,汽膜厚度随热流密度的增大而增大,汽泡脱离周期随热流密度的增大先减小,而后维持在一稳定值;汽膜脱离周期随倾角的增大而减小,倾角为5°时的汽膜脱离周期稳定在0.27 s左右。当发生沸腾危机时,汽膜厚度迅速减小,这可作为动态监测加热表面沸腾状态的依据。     

Bubble Dynamic Behavior Study on Pool Boiling with Downward Facing Heated Surface

Based on the Matlab software, a program for automatic identification of vapor liquid two-phase flow interface was developed. The program can obtain such characteristics as vapor liquid interface change, vapor film thickness, vapor film departure period and normal velocity. The dynamic data of bubbles on the downward facing heated grooved surface with different inclination angles and heat fluxes were processed and analyzed by this program. The results show that when the downward facing heated surface under the nucleate boiling, the vapor film thickness increases with the heat flux, and the bubble departure period decreases with the increase of the heat flux firstly and then maintains a stable value. The vapor film departure period decreases with the increase of inclination angle, and is about 0.27 s when the inclination angle is 5°. When the boiling crisis occurs, the vapor film thickness decreases rapidly, which can be used as the basis for dynamically monitoring the boiling state of heated surface.     

下沉加热面上气泡微细化沸腾实验研究

为分析加热面相对位置对气泡微细化沸腾（MEB）的影响,对下沉加热面上的过冷沸腾进行了实验研究,并与齐平加热面实验结果进行了对比。25～50 K过冷度范围内,在下沉3 mm加热面上观察到了MEB现象。在50 K过冷度下,MEB时的热流密度可达5.55 MW/m²。可视化结果表明：在MEB区域,下沉加热面上形成的蒸汽气膜会频繁地膨胀收缩;随过冷度的升高,膨胀收缩的周期增加,而幅值变化较小。此外,相比于齐平加热面条件,下沉加热面周围的壁面可显著限制蒸汽气膜的横向膨胀。     

倾斜窄长套管内自然对流沸腾临界热流密度的实验研究

用实验方法对浸没在饱和液体中的倾斜窄长加热套管内的自然对流沸腾临界热流密度进行了实验研究,考察了套管间隙、管长、倾斜角和工质对临界热流密度的影响,并考虑了倾斜角对重力的影响,对用于预测垂直套管内自然对流沸腾临界热流密度的半理论半经验公式进行了修正。修正后的公式能较好地预测本实验和他人实验的结果。     

HFE-7100工质稳态临界沸腾传热实验研究

池沸腾临界热通量是沸腾相变传热的重要参数,决定了相变换热器件的推广应用。表面粗糙度和饱和压力对沸腾传热边界层分布、表面铺展润湿及工质动力学特性具有重要影响,进而对临界热通量作用显著。本文对HFE-7100工质在4种不同粗糙度的铜基表面（0.019、0.205、0.311和0.587 μm）条件及在不同饱和压力（0.07、0.10、0.15及0.20 MPa）工况下的池沸腾稳态临界状态下的传热及可视化实验进行了研究。对表面粗糙度及饱和压力对稳态临界沸腾的影响机制进行了分析,并考察了临界热通量预测模型对临界热通量的预测准确性。可视化研究表明,临界状态下的沸腾气液两相工质由小气泡、大气泡、气柱及蘑菇状气团组成,而在过渡状态下,沸腾表面会形成非平滑气膜,并不断分离出气泡。同时传热数据表明,表面粗糙度及饱和压力的增加能使表面临界热通量得到提升。相比而言,Bailey等建立的临界热通量预测模型能相对准确地预测HFE-7100工质沸腾临界热通量数据。为进一步提升预测准确度,建立了临界热通量无因次参数K预测经验关联式,其预测值与本实验及文献实验数据吻合较好。     

Critical heat flux during natural convective boiling in inclined tubes submerged in saturated liquids

An experimental study was carried out to improve and expand understanding of boiling phenomena and the critical heat flux (CHF) during natural convective boiling in uniformly heated inclined tubes submerged in a pool of saturated liquids under atmospheric pressure. The test conditions were as follows: inter diameters of the test tubes ranged from 0.9 to 8.0 mm; heated lengths ranged from 100 to 400 mm, and inclination angles varied from 30° to vertical position. The test fluids were water and R-11. The experimental results showed that the CHF decreases with the increasing ratio of the tube length to the tube diameter, and with the reducing of the inclination angle. A semi-theoretical correlation, which originally used for the CHF during natural convective boiling in vertical tubes, was modified to predict the CHF occurs in the inclined tubes. The modified correlation agreed reasonably well with the present experimental data and other CHF data for narrow inclined annular tubes.     

窄环隙流道内自然对流沸腾换热实验研究

以水为工质 ,在常压下对竖直和倾斜环隙流道进行了自然对流沸腾换热实验研究 ,给出并讨论了间隙大小、热负荷、倾角和表面张力对换热性能的影响 ,可视化观察加深了对窄小空间沸腾现象的认识。在实验的基础上 ,提出了一个新的、可以较方便使用的传热计算关联式。     

过冷度对蒸汽气泡破碎及微气泡喷射过程的影响

为研究过冷度对蒸汽气泡破碎及微气泡喷射过程的影响,利用高速摄像机记录不同过冷度下过冷池中蒸汽气泡凝结过程。实验结果表明:在低过冷度(ΔTsub=17K)下,蒸汽气泡界面波动发展缓慢,气泡不会破碎,而是逐渐分裂凝结;在高过冷度(40KΔTsub75K)下,蒸汽气泡表面上的波动剧烈发展,随后气泡会突然破碎,并形成大量微气泡;在ΔTsub=30K时,气泡突然破碎前会有小气泡分裂现象发生。40KΔTsub75K时气泡破碎形成的微气泡的直径和速度在量级上与气泡微细化沸腾区域的微气泡接近。随过冷度的升高,微气泡的直径减小,速度增加,且蒸汽气泡破碎前其表面上波动的波数迅速增加,波动的最大幅值先增加后减少。     

One-dimensional critical heat flux concerning surface orientation and gap size effects

Tests were conducted to examine the critical heat flux (CHF) on a one-dimensional downward heating rectangular channel having a narrow gap by changing the orientation of the copper test heater assembly in a pool of saturated water under atmospheric pressure. The test parameters include both the gap sizes of 1, 2, 5 and 10 mm, and the surface orientation angles from the downward-facing position (180°) to the vertical position (90°), respectively. Also, the CHF experiments were performed for pool boiling with varying heater surface orientations in the unconfined space at atmospheric pressure using the rectangular test section. It was observed that the CHF generally decreases as the surface inclination angle increases and as the gap size decreases. In consistency with several studies reported in the literature, it was found that there exists a transition angle at which the CHF changes with a rapid slope. An engineering correlation is developed for the CHF during natural convective boiling in the inclined, confined rectangular channels with the aid of dimensional analysis. This correlation agrees with the experimental data of this study within ±20%.     

朝下针翅结构表面稳态临界沸腾换热实验研究

针对商用压水堆核电站堆内熔融物滞留(IVR)策略对提高压力容器外表面沸腾换热临界热流密度(CHF)的迫切需求,本文采用冷喷涂技术在铜基体表面制备了一种由针翅凸起结构与多孔涂层相结合的毫米-微米双尺度结构表面,运用稳态池沸腾实验研究了铜光表面和针翅涂层结构表面在朝下不同倾角下的沸腾换热性能。结果表明：朝下表面的CHF随倾角的增加而增大,与铜光表面相比,针翅涂层结构表面CHF至少提高了63%,具有较好的工程应用前景。     

Steady-state Experimental Study of Critical Boiling Heat Transfer on Downward Facing Surface with Pin-fin Coating Structure

Enhancing the critical heat flux (CHF) of boiling heat transfer to achieve in-vessel retention (IVR) strategy has become an urgent requirement of commercial PWR nuclear power plants’ security. A new kind of millimeter-micro multi-scale structure surface was fabricated on the surface of copper substrates by cold spraying technology, which combined pin-fin structures with porous coating structures. Steady-state pool boiling experiment was conducted on a plain copper surface and the pin-fin coating structure surface under different inclination angles. The experimental results show that the CHF increases with the inclination angles on downward facing surface, compared with the plain surface, the pin-fin coating structure enhances the CHF more than 63%, which testifies its superior engineering application prospects.     

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。     

Experimental Research on Critical Heat Flux for Downward-facing Pool Boiling with SA508 Steel Plate

The external reactor vessel cooling (ERVC) is one of the important methods to achieve the in-vessel retention (IVR), while the critical heat flux (CHF) on the outside wall of the reactor pressure vessel (RPV) decides the maximum heat removal capacity of ERVC. In present work, a small CHF test facility was established. The test surface was made of SA508 steel which was the same surface material of prototype RPV. The deionized water was used as coolant in downward-facing CHF test under pool boiling condition. The influence of the real RPV material surface at different inclination angles and sub-cooling conditions on the CHF characteristics was studied. The influence of aging on CHF was also studied. The results show that the SA508 steel surface is easily oxidized, so its CHF is higher than that of copper and stainless steel surfaces. The CHF of SA508 steel surface increases with inclination angle, but there is a turning point near 30° and the CHF below the turning angle has no obvious trend with the increase of inclination angle. The CHF increases with the sub-cooling, and it shows linear growth characteristics. The test results provide a further understanding of the CHF behavior on the RPV outside wall and lay the foundation for future research work on CHF enhancement methods.     

池沸腾下朝向SA508钢表面临界热流密度特性试验研究

反应堆压力容器外部冷却（ERVC）是实现熔融物堆内滞留（IVR）的重要方案之一,而反应堆压力容器（RPV）外壁面的临界热流密度（CHF）决定了ERVC冷却能力的限值。为此建立小型CHF试验装置,并采用RPV用SA508钢制作试验块加热表面。以去离子水为试验工质,开展池沸腾下朝向CHF试验,研究真实RPV表面材料在不同倾角和过冷度条件下的CHF特性,及其老化效应对CHF的影响。结果表明：SA508钢表面极易氧化生锈,其CHF较不易生锈的铜和不锈钢表面要高;SA508钢表面CHF随倾角的增大而增加,但在30°附近存在转折,转折角以下范围内的CHF随倾角增加趋势不明显;CHF随过冷度的增加而增加,且基本呈线性变化。本试验有助于进一步认识RPV外壁面的CHF行为,为后续开展CHF增强方法研究奠定基础。     

内螺纹管临界热流密度预测与数值计算

基于壁面汽泡壅塞理论,针对近临界压力区两相流动沸腾的偏离泡核沸腾(DNB)现象,对垂直上升内螺纹管的DNB型临界热流密度(CHF)进行了数值计算研究。以内螺纹管为分析对象改进已有的汽泡壅塞模型,计算了汽泡层区与主流区的极限传递质量流量、湍流速度分布、汽泡层区临界截面含气率等本构关系,汽泡脱离直径的计算考虑了汽泡接触角的影响。本文模型还根据大量CHF实验数据拟合得到了新的α_b关联式。最后,基于Fortran语言编制了CHF的理论预测数值模型程序,研究分析了压力、质量流速、热平衡干度及进口欠焓对CHF的影响,并根据CHF查表值对本文模型进行评估,同时将实验得到的内螺纹管CHF数据与采用Bowring模型、Katto模型、Shah模型和本文模型计算的CHF进行比较,发现本文模型的误差最小,与实验值吻合结果较好,说明本文模型能较好地对垂直上升内螺纹管DNB型CHF进行预测。     

锆-4在冷却水中的骤冷沸腾传热实验研究

为了研究锆-4在冷却水中的骤冷行为与沸腾传热特性,本文采用可视化方法,并测量了锆-4在骤冷过程中的温度变化。基于一维导热反问题求解,计算得到锆-4表面的热流密度和温度。在骤冷过程中锆-4会依次经历膜态沸腾、过渡沸腾、核态沸腾以及单相对流换热4个阶段,并且分析了轴向高度和冷却水过冷度对骤冷行为以及沸腾传热的影响。结果表明,随着过冷度的增大,骤冷时间减小,最小膜态沸腾温度增大,并且核态沸腾与过渡沸腾传热受加热表面局部特性影响显著,并建立了锆-4表面最小膜态沸腾温度的关系式,对反应堆的安全分析具有重要的意义。      

Vibration Characteristic of Heated Rod Induced by Subcooled Flow Boiling

A subcooled boiling loop with annular flow channel on an electrically heated rod at the channel axial center was used to make an experimental approach to investigate the vibration characteristic induced by subcooled flow boiling. The experiments were carried out to measure vibration induced in the rod under different conditions of incoming coolant subcooling temperature of 10–80 K, coolant flow rates of 0.1–0.35 × 10^?3 m³/s and imposed linear power densities of 17–600 W/cm. Distilled water was used as coolant in the loop. The vibration behavior of the rod was measured by using an accelerometer. Also, a high-speed motion analyzer system was used to analyze the bubble behaviors in the different subcooled boiling conditions.

The results show the intensive SBIV (subcooled boiling-induced vibration) which highly depends on dynamic force generated by rapid growth and collapse of vapor bubbles under high heat flux loading whilst they still attach to the heating surface. These behaviors were influenced strongly by the conditions of subcooling temperature, linear power density and flow rate.     

Critical heat flux of forced convection boiling in an oscillating acceleration field — III. Reduction mechanism of CHF in subcooled flow boiling

To investigate the effect of variation in acceleration on the critical heat flux (CHF) in subcooled flow boiling, a photographic study was made. The test section was an internally heated vertical annulus with a glass shroud, in which Freon-113 flowed upwardly. The observation was made at a pressure of 3 bar, a mass flux of 920 kg/m²s, an inlet subcooling 45 K and a slightly lower heat flux level than steady CHF. The vertical acceleration was oscillated with amplitude of 0.3g_e and a period of 6 s.At low apparent gravitational acceleration, bubbles generated on the heated surface moved longer along the surface without detachment and coalesced with other bubbles to form large vapor slugs. This causes early CHF, the mechanism of which is dry-out of the liquid film existing between the heated surface and vapor slugs.