垂直上升圆环形通道内超临界压力水的传热特性

在压力P=23～28 MPa、质量流速G=350～1000 kg/(m2.s)、外壁面热流密度q=200～1000 kW/m2的试验参数范围内,对垂直上升圆环形通道内超临界压力水的传热特性进行试验研究。分析q、P、G、螺旋绕丝对传热特性的影响,比较有、无绕丝结构时出现的两种传热恶化。试验结果表明:提高G或降低q都可以强化超临界水的传热;在不同的传热类型下,P对传热特性有不同的影响;螺旋绕丝具有很好的局部强化传热作用,并且可以推迟在高热流密度、低质量流速下发生的传热恶化。     

非均匀加热条件下超临界压力水在垂直管中的传热特性

对超临界压力水在非均匀加热的垂直上升管中的传热特性进行了试验研究.试验参数范围:p＝23～30 MPa,质量流速G＝600～1 200 kg/(m2·s),内壁平均热负荷q＝200～600 kW/m2.试验结果表明:对于周向非均匀加热情况,热负荷及传热系数的周向分布的不均匀性随雷诺数的增加而减小;同一截面上可以同时存在传热恶化和传热强化现象,传热恶化是由局部的峰值热负荷引起的;不均匀加热的垂直上升管内的平均传热系数可以采用均匀加热条件下的公式在相应的平均热负荷下进行计算;非均匀受热管传热恶化后,加热侧中点的壁温升高比相应热负荷下的均匀加热管的低.     

超临界水冷堆类四边形子通道亚临界水的传热试验研究

在压力为11~19 MPa,质量流速为700~1300 kg/(m2·s),热流密度为200~600 k W/m2的工况范围内,对超临界水冷堆(SCWR)堆芯棒直径为8 mm,栅距比为1.2的类四边形子通道的传热特性进行试验研究。结果表明:热流密度对类四边形子通道管管内的传热特性的影响显著,热流密度越高,传热恶化越容易发生;在较低的质量流速下,传热恶化发生可能性较大,质量流速较高时,对传热特性影响较小;压力对类四边形管管内传热特性的影响明显,压力越高,传热恶化现象越易发生,且临界干度值越低,传热恶化所覆盖的焓值区域越大。     

垂直上升内螺纹管中超超临界压力水的传热特性研究

在P=25～35MPa、G=450～1800kg/(m2·s)、q=200～600kw/m2的试验参数范围内,研究了(φ)28.6×5.8mm垂直上升内螺纹管内水的传热特性及管壁温分布.试验结果表明:在超临界及超超临界压力区,垂直上升内螺纹管对水的传热在拟临界点前后不同,在低焓区管壁温度随焓增平缓增加,管壁温度在临界焓值区存在跃升;质量流速的提高可强化传热、推迟壁温跃升,但热负荷的增加有相反的作用.文中还给出了超超临界压力区适用于不同焓值范围的换热系数试验关联式.     

2×2稠密棒束内超临界水的传热特性试验研究

在压力p=23～28 MPa、质量流速G=350～1 000 kg/(m²•s)、热流密度q=200～1000 kW/m²的试验参数范围内,对2×2棒束内超临界水的传热特性进行了试验研究。试验得到了加热管周向壁温分布规律,并就出现周向温度差异的原因进行了分析。此外,给出了压力、质量流速及热流密度等系统参数对平均传热特性的影响,分析了低质量流速下出现的传热恶化现象。试验结果表明：加热管周向壁温并不均匀,边角子通道壁温最高,中心子通道壁温最低,周向壁温的高低与横截面流通面积的不均匀性紧密相关。随着热流密度的提高或质量流速的降低,超临界水的传热受到抑制,当q/G增大到一定程度时,棒束内发生传热恶化。     

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。     

类三角形堆芯子通道超临界水传热试验研究

针对超临界水冷堆(SCWR)堆芯垂直上升类三角形子通道,开展超临界水的流动传热试验研究。反应堆堆芯类三角形子通道棒束直径为8 mm、栅距比为1.4。试验参数范围为:热流密度q=200~800 kW/m~2、压力P=23~28 MPa、质量流速G=700~1 300 kg/(m~2×s)。分析了q、P和G等热工参数对超临界水传热特性的影响。试验结果表明:超临界压力下,壁面温度T_w随q和P的增加而升高,传热系数峰值降低;提高G能够强化超临界水的传热,G增加,T_w降低,传热系数增大;当G增大到一定的程度,改变G对传热起到强化作用的效果不如在低G下显著;当q达到800 kW/m~2时,在大比热区,T_w随焓值变化剧烈,传热系数峰值不明显;当P提高到28 MPa时,大比热区的强化传热作用被削弱。     

倾斜内螺纹管中亚临界及超临界压力汽-液传热特性研究

在p=9～28MPa,G=600～1200kg/(m2ˇs),q=200～600kW/m2的工况范围内,研究了φ38.1×7.5mm倾斜上升内螺纹管(水平倾角α=19.5°)中亚临界以及超临界汽-液的传热特性。试验结果表明在亚临界压力区,内螺纹管有效地抑制了膜态沸腾的发生,但近临界压力区内螺纹管传热强化作用减弱;超临界压力区内螺纹管的传热良好;工程设计时要保证足够的管内最小质量流速;文中还给出了临界质量流速的试验关联式。     

竖直圆管内超临界压力氟利昂传热试验研究

深入研究超临界压力下流体特殊的对流传热特性,对超临界水冷反应堆的堆芯设计至关重要。在上海交通大学SMOTH氟利昂回路上开展了压力4.3~4.7 MPa、质量流速600~2 500kg/(m2·s)、热流密度20~180kW/m2参数下的圆管内超临界上升流传热试验。远离拟临界温度区间内换热系数和Dittus-Boelter公式计算值很接近,热流密度越大,近拟临界区换热系数越小,小质量流速大热流密度下,发生显著传热恶化。加速效应无量纲数和浮升力无量纲数对传热特性显示了强烈的相关性。提出了氟利昂工质传热试验的传热恶化起始点关系式。Bishop关系式计算换热系数和试验值之间标准差很小,但整体略偏大;Jackson关系式计算值和试验值之间平均偏差很小,但标准差偏大。     

垂直管内超临界水传热实验研究

在宽广的实验范围内对直径10 mm垂直管内超临界水在不同工况下的传热特性进行了实验研究,分析了热流密度、质量流速及压力变化对内壁面温度及传热系数的影响规律。实验参数为：压力23、25、26 MPa,质量流速450~1 200 kg/（m²•s）,热流密度200~1 200 kW/m²。实验结果表明：随主流温度的升高,壁面温度逐渐上升,在拟临界点附近由于物性剧变存在传热强化现象;热流密度的增加以及质量流速的减小均会削弱传热强化现象,并导致传热恶化;压力的影响主要体现在传热恶化、强化的起始热流密度和起始主流温度的不同。     

圆管内超临界水传热恶化数值模拟及模型评价

采用计算流体力学(CFD)方法对圆管通道内超临界水的传热恶化特性进行数值模拟研究,将现有模型对超临界条件计算的适用性和可靠性进行了评估。计算结果表明,在低质量流速条件下,传热恶化发生时流道内将会出现M型的速度分布,最大速度处的湍动能明显减小;在高质量流速条件下,传热恶化时各物性参数中热导率对其传热特性有明显的影响。模型评估结果表明,本研究中SST模型能够用于高质量流速条件下传热恶化的计算。     

Experimental investigation on heat transfer from a heated rod with a helically wrapped wire inside a square vertical channel to water at supercritical pressures

A supercritical water heat transfer test section has been built at Xi’an Jiaotong University to study the heat transfer from a 10 mm rod inside a square vertical channel with a wire-wrapped helically around it as a spacer. The test section is 1.5 m long and the wire pitch 200 mm. Experimental conditions included pressures of 23–25 MPa, mass fluxes of 500–1200 kg/m² s, heat fluxes of 200–800 kW/m², and inlet temperatures of 300–400 °C. Wall temperatures were measured with thermocouples at various positions near the rod surface. The experimental Nusselt numbers were compared with those calculated by empirical correlations for smooth tubes. The Jackson correlation showed better agreement with the test data compared with the Dittus-Boelter correlation but overpredicted the Nusselt numbers almost within the whole range of experimental conditions. Both correlations cannot predict the heat transfer accurately when deterioration occurred at low mass flux and relatively high heat flux in the pseudocritical region. Comparison of experimental data at two different supercritical pressures showed that the heat transfer was more enhanced at the lower supercritical pressure but the deterioration was more likely to occur at the higher pressure, meaning increased safety. Based on a comparison with an identical channel without the helical wrapped wire, it was found that the wire spacer does not enhance the heat transfer significantly under normal heat transfer conditions, but it contributes to the improvement of the heat transfer in the pseudocritical region and to a downstream shift of the onset of the deterioration. The Jackson buoyancy criterion is found to be valid and works well in predicting the onset of heat transfer deterioration occurring in the experiments without wire.     

类四边形堆芯子通道内超临界水传热特性研究

基于类四边形堆芯子通道超临界水的传热试验,建立棒径为8 mm、栅距比为1.2的超临界水冷反应堆（SCWR）类四边形堆芯子通道物理模型,采用SSG湍流模型,在p=23～28 MPa超临界压力范围,研究了子通道内超临界水的传热特性,分析了压力、质量流速和热流密度等热工参数对类四边形子通道内超临界水传热特性的影响。研究结果表明：采用SSG湍流模型数值研究计算得到的内壁温度与试验结果变化趋势一致。在拟临界区,随压力的增大,相应的换热系数峰值逐渐降低。质量流速的增加,在整个焓区均能明显加强子通道内传热现象。随热流密度的增加,内壁温度逐渐升高,对应的换热系数峰值降低,同时逐渐向低焓区方向移动。     

Numerical investigation of acceleration effect on heat transfer deterioration phenomenon in supercritical water

It is important to understand the heat transfer deterioration (HTD) phenomenon for specifying cladding temperature limits in the fuel assembly design of supercritical water-cooled reactor (SCWR). In this study, a numerical investigation of heat transfer in supercritical water flowing through vertical tube with high mass flux and high heat flux is performed by using six low-Reynolds number turbulence models. The capabilities of the addressed models in predicting the observed phenomena of experimental study are shortly analyzed. Mechanisms of the effect of flow structures and fluid properties on heat transfer deterioration phenomenon are also discussed. Numerical results have shown that the turbulence is significantly suppressed when the large-property-variation region spreads to the buffer layer near the wall region, resulting in heat transfer deterioration phenomenon. The property variations of dynamic viscosity and specific heat capacity in supercritical water can impair the deterioration in heat transfer, while the decrease of thermal conductivity contributes to the deterioration.     

同心环形管内沸腾两相流动与传热实验研究

对窄缝为2．1mm的同心环形管,试验研究了外管加热条件下水的沸腾两相流动阻力与传热特性,得到了以下结果：窄缝环形管内两相流动的阻力较普通圆管内大,沸腾换热得到了较明显的强化,换热系数弓压力、热平衡干度、工质流量、加热负荷均有关系,且与缝隙宽度和加热方式有关;提出了环形管强化传热的微液膜蒸发机理与汽泡扰动机理的物理解释;得到了环形管内流动摩擦阻力系数与传热系数的实验关联式。     

超临界水冷堆类三角形子通道流动传热特性研究

基于类三角形子通道超临界水的传热试验,建立了超临界水冷堆三角形子通道物理模型。采用雷诺应力湍流模型SSG,在压力为23～28 MPa、质量流速为700～1300 kg/(m²•s)、热流密度为200～1000 kW/m²参数范围内,对棒径8 mm、栅距比为1.4的子通道内超临界水流动与传热特性进行了数值研究。分析了系统参数对流动和传热特性的影响,对比了不同焓区的二次流特性。结果表明：采用SSG模型对超临界水冷堆三角形子通道内流动传热的CFD模拟结果与试验数据较吻合。质量流速越高,传热能力越强;子通道换热系数峰值随压力的提高而减小;热负荷越高,内壁温度越高;在大比热容区换热系数峰值随热流密度的增大而明显减小,传热存在恶化趋势。超临界区子通道内在与主流垂直方向形成了明显的二次流,存在6个对称的漩涡,二次流速最大值出现在子通道窄缝区间隙。通道内不同焓区二次流结构相似,但二次流强度随焓的提高而增大。     

10 mm垂直单管通道内超临界水传热弱化现象的实验与数值分析

超临界压力下的流体因拟临界点附近物性的剧烈变化,形成了非常奇特的传热现象。因流体密度突变,在低流量下会引起强烈的浮升力作用,对超临界流体的流动和传热均有极大影响。本工作通过实验获得10 mm单管内传热弱化现象的实验数据,并采用改进的低雷诺数湍流模型,使用数值方法模拟该传热弱化现象。计算结果表明,不同于以往传统的模型会高估壁面温度,改进的低雷诺数湍流模型能较好预测实验结果。数值模拟结果还揭示了浮升力对湍流剪切应力和速度分布的影响,进而引起传热弱化和传热恢复。     

Investigation of forced convection heat transfer of supercritical pressure water in a vertically upward internally ribbed tube

In the present paper, the forced convection heat transfer characteristics of water in a vertically upward internally ribbed tube at supercritical pressures were investigated experimentally. The six-head internally ribbed tube is made of SA-213T12 steel with an outer diameter of 31.8 mm and a wall thickness of 6 mm and the mean inside diameter of the tube is measured to be 17.6 mm. The experimental parameters were as follows. The pressure at the inlet of the test section varied from 25.0 to 29.0 MPa, and the mass flux was from 800 to 1200 kg/(m² s), and the inside wall heat flux ranged from 260 to 660 kW/m². According to experimental data, the effects of heat flux and pressure on heat transfer of supercritical pressure water in the vertically upward internally ribbed tube were analyzed, and the characteristics and mechanisms of heat transfer enhancement, and also that of heat transfer deterioration, were also discussed in the so-called large specific heat region. The drastic changes in thermophysical properties near the pseudocritical points, especially the sudden rise in the specific heat of water at supercritical pressures, may result in the occurrence of the heat transfer enhancement, while the covering of the heat transfer surface by fluids lighter and hotter than the bulk fluid makes the heat transfer deteriorated eventually and explains how this lighter fluid layer forms. It was found that the heat transfer characteristics of water at supercritical pressures were greatly different from the single-phase convection heat transfer at subcritical pressures. There are three heat transfer modes of water at supercritical pressures: (1) normal heat transfer, (2) deteriorated heat transfer with low HTC but high wall temperatures in comparison to the normal heat transfer, and (3) enhanced heat transfer with high HTC and low wall temperatures in comparison to the normal heat transfer. It was also found that the heat transfer deterioration at supercritical pressures was similar to the DNB at subcritical pressures.