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。     

液态金属钠沸腾两相流动传热特性理论研究

在实验的基础上对液态金属钠沸腾两相流动传热特性进行理论研究。计算对象为环形流道。单相流动区域认为液态金属钠不可压缩;两相流动区域考虑钠蒸汽的可压缩性。两相流动区域选用均匀流模型,求解过程中采用迎风格式进行积分。将模型计算结果与相关实验数据进行对比,结果表明本文模型可用于计算液态金属钠沸腾两相流动传热特性,模型计算结果在一定程度上能完成对实验工作的拓展。     

环形通道内液态金属钠流动换热特性实验研究

对液态金属钠在环形通道内的单相流动换热特性进行了实验研究。结合实验数据,将液态金属钠单相流动分为层流区(Re≤2 000)、过渡区(2 000Re≤4 000)及湍流区(Re4 000),分别拟合得到不同流态下摩擦系数的计算关系式,并拟合得到液态金属钠环形通道内换热特性的相应关系式。结果表明:液态金属钠单相流动特性与常规流体(如水)类似,其层流区摩擦系数略大于水,湍流区与水的很接近。液态金属钠对流换热过程中,导热项占较大份额,同时Nu随Pe的增大而略有增大。     

环形通道内液态金属钠流动传热特性数值模拟

利用数值方法，使用商用软件ANSYS CFX，针对内径4~10 mm、外径7~20 mm的环形通道内不同边界条件下单相钠的流动和传热特性进行了研究，分析了流速、入口温度、内壁面热流密度和外壁面热流密度等对其流动传热的影响。结果表明，环形通道间隙对液态金属钠流动和传热影响较大，热流密度对其影响较小。将计算结果与文献中理论和实验结果进行了比较和分析，得出环形通道内液态金属钠的传热关系式。数值模拟结果与文献实验结果吻合较好，总体趋势符合良好。      

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。     

窄矩形通道两相流动沸腾压降特性实验研究

实验研究了横向均匀和非均匀(多项式和正弦分布)加热条件下垂直矩形通道(2 mm×60 mm×1 000 mm)的沸腾压降特性,实验段为双面加热,有效加热面尺寸为56 mm×700 mm。工作流体为去离子水,通过改变入口压力和流量边界开展不同参数工况下的实验研究。结果表明,两相压降梯度随饱和压力的增加而减小,随质量流速的增加而增大,含气率对两相压降的影响与质量流速有关,横向功率分布形式对流动沸腾压降也有重要影响。基于均匀加热实验数据对现有的两相压降预测模型进行了评价,发现使用等效黏度假设的均相模型极大低估了实验值,且预测结果的分散度较大;分相模型中Müller-Steinhagen和Heck、Li和Wu关系式预测效果最好,平均绝对误差分别为11.8%和12.3%,且大多数预测值在±20%误差带内。本文基于Müller-Steinhagen和Heck关系式形式引入邦德数Bo考虑表面张力的影响,拟合得到新的预测关系式,该关系式对实验数据的预测误差在±8%的误差范围内。     

管束通道内沸腾两相流特性的研究

以R113为工质,采用高速动态分析仪对垂直管束通道内的沸腾两相流型及其转变特性进行了实验研究。对管束狭窄通道内沸腾两相流型进行划分,并与圆管内的两相流型进行比较,在此基础上对通道几何形状及物理参数对管束通道内沸腾两相流型及其转变特性的影响进行分析,为进一步对管束通道内流型判定、沸腾换热及阻力压降的研究奠定了基础。     

环形狭缝膜态沸腾弥散两相流动特性研究

在 3种不同间隙的同心竖直环形狭缝膜态沸腾试验段中 ,研究了以去离子水为工质的两相弥散流摩擦压降 ,比较了环形狭缝和圆形通道中两相流动摩擦压降的不同 ,还研究了环形间隙对摩擦压降的影响。结果表明 :不同间隙下的环形狭缝内膜态沸腾弥散流摩擦压降可用修正的Sadatomi方法计算 ,该方法可应用于工程上的环形狭缝膜态弥散流动     

环形通道内液态铅铋合金流动换热特性实验研究

通过对环形通道内液态铅铋合金的流动换热特性进行实验研究,得到了气泡泵注气对液态金属流动的影响,并拟合出环形通道内液态铅铋合金的摩擦系数关系式和换热特性关系式。结果表明：采用气泡泵注气能有效提升铅铋合金的质量流速;相同Reynolds数下环形通道内液态铅铋合金的摩擦系数大于由布拉休斯公式计算得到的摩擦系数;液态铅铋合金对流换热过程中,导热项占主导地位,并且Nusselt数随Peclet数的增大而增大。     

环形窄缝通道中沸腾压降的实验研究

在1．5～6．0MPa压力下,通过内外管通电双面加热流体,对问隙为1．0mm和1．5mm垂直环形窄缝通道内饱和沸腾状态下的压降进行实验研究。通过实验得出了新的分液相摩擦倍增因子公式,用该公式得到的计算结果与实验数据符合较好,平均误差为11．6％。     

液钠沸腾两相流流型与临界热流密度(CHF)机理实验研究

通过大量的液态金属钠临界热流密度 (CHF)的实验研究 ,结合液钠两相传热流动特性及液钠的物性特点 ,分析了起始沸腾流型 ,泡状流 ,块状流 ,环状流和双向环状流的热工水力特性 ;并从实验结果出发 ,深入分析了液钠发生临界热流密度时的气泡爆炸和液膜撕裂或局部蒸干的两种传热恶化机理     

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.     

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。     

Experimental Study on Two-phase Flow Boiling Pressure Drop Characteristics in Narrow Rectangular Channel

The flow boiling pressure drop characteristics of a vertical rectangular channel (2 mm×60 mm×1 000 mm) were studied under transverse uniform and non uniform heating. The test section was double-sided heating with an effective heating area of 56 mm×700 mm. Three kinds of heating power distributions (uniform, polynomial and sinusoidal) were selected, and the working fluid was deionized water. A wide range of operating conditions was obtained by varying the inlet pressure and mass flux. The results show that the pressure drop gradient decreases with the increase of saturation pressure and increases with mass flux. The influence of vapor quality on two-phase pressure drop is related to mass flux, and the transverse power distribution has an important effect on the flow boiling pressure drop. Based on the experimental data of uniform heating, the existing two-phase pressure drop prediction model was evaluated. The homogeneous model using the equivalent viscosity assumption significantly underestimated the experimental values, and the data dispersion is relatively large. The Müller-Steinhagen and Heck and Li and Wu formulas are found to be the best with mean absolute errors of 11.8% and 12.3%, and most of predicted values are within ±20% error band. In this study, a new correlation based on the form of Müller-Steinhagen and Heck formula was proposed, and the Bond number Bo was introduced to consider the effect of surface tension. The prediction error of the new correlation for experimental data is within 8% error band.     

环形窄缝通道内流动不稳定性试验研究

设计了加热长度为1800mm，间隙尺寸为1．5mm的环形窄缝通道试验段；以去离子水为上质，进行了强迫循环下两相流动不稳定性试验研究。实验压力为1．5～3．0MPa，质量流量为3．0～25kg／h，加热功率为3．0～6．5kW，进口温度为20℃、40℃、60℃。实验发现，在一定加热功率和进口条件下，回路流量低于特定值，会发生不稳定现象。试验研究了进口过冷度、系统压力和质量流量等参数对不稳定性的影响，得到了环形窄缝通道内强迫循环下两相流动不稳定区间。     

Local Sodium Boiling behind Local Flow Blockage in Simulated LMFBR Fuel Subassembly

This paper deals with local sodium boiling in the downstream of a six-subchannel blockage in an electrically heated LMFBR fuel subassembly mock-up.

The first series of experiments were conducted to measure temperature distributions in the downstream of the blockage under non-boiling conditions. The measured temperature rise due to the blockage agreed fairly well with the calculation by the LOCK code.

The second series of experiments were performed to investigate local boiling phenomena. In the local boiling region, no flow instability was observed since the sub-channels near the wrapper wall were still filled with sub-cooled liquid. In the nearly bulk boiling region, however, considerable upstream voiding occurred and then the inlet flow decreased, leading to final dryout.

The boiling caused a considerable increase in acoustic noise intensity. The root-mean-square (RMS) noise level of approximately 20 mbar obtained in the present local boiling experiments with sodium was much higher than that (approximately 0.5 mbar) in the ordinary nucleate boiling experiments with water. The peak observed in the hertz ranges was due to the repetition of bubble formation and collapse. In the kilohertz ranges, however, resonance peaks were superposed on a smooth curve with a broad peak at approximately 7 kHz.

The frequency (2.9 and 20.2 sec^?1) of bubble formation decreased with the increase of the bubble size at its point of maximum development. The product of the bubble frequency and the equivalent diameter was found to be constant.