换热器传热强化的管束试验研究

以铜－镍合金整体低肋管和整体内外翅片管为元件，以油－水和水－水为介质为管束换热器模拟体进行了试验研究。试验结果表明，低肋管对于油－水换热，内外翅片管对于水－水换热有着比较明显的传热强化效果。在额定工况下，低肋管油－水换热模拟体的总传热系数是光滑管模拟体的１．５９倍，可相应节省换热面积３７％，管外油流的压力降较光管降低３３％；内外翅片管水－水换热模拟体的总传热系数是光滑管的１．３１倍，可节省换热面积     

管外上升R—113流体的沸腾换热试验

详细介绍了Ｒ－１１３流体管外上升流动的沸腾换热试验，包括试验台架，流量计和温度测量的修正，以及试验数据，拟合的换热关系式为ｑ＝５２８（Ｔｗ－Ｔｓ）＾１．３３。     

基于偏离设计工况运行的稳态考验回路换热能力补偿措施分析研究

稳态高温高压回路的换热能力与辐照参数的匹配性对燃料组件辐照考验的可行性及安全性有着重要的影响。本文研究了在各工况下试验回路换热能力与燃料组件辐照考验热工参数的匹配性问题，并分析了不同换热能力补偿措施的适应性。研究结果表明，当试验回路的运行偏离设计工况，回路中一次水的流量及辐照装置出口温度与主换热器能够实现的最大一次水温降以及最大换热功率之间是存在严格的对应关系。装置出口温度升高以及调节二次水流量对提升主换热器的换热效果不明显，而采用更低温度的二次水可以部分提升换热器的功率。主换热器后端散热方式在总的换热功率能力上要较前端换热强。换热器并联的换热效果并非总是强于单台独立运行，在低流量运行时，设置两台换热器并将其串联是最有效解决换热能力不足的手段，针对换热器一次水入口温度330℃及250℃，两台换热器串联的总换热功率将比单台运行时分别平均提高68.7%和80.4%。本文的研究方法及相应的研究结果可以用于指导燃料组件的稳态回路辐照论证以及考验过程中的试验回路运行参数选择。     

非能动余热排出换热器冷凝换热性能研究

以浸没在高位水箱中的竖直管束为研究对象,对不同热负荷条件下竖直管束内冷凝换热特性进行研究,通过对比中心管与周围旁管的凝液增长率以及冷凝换热热阻,分析了中心管与旁管换热特性的差异,解释了低压条件下冷凝换热系数剧烈下降现象。将管束冷凝试验数据与已有单管试验数据对比发现,在相同蒸汽工况下,单管的冷凝换热系数与旁管的冷凝换热系数吻合较好,但远低于中心管的冷凝换热系数,说明中心管的换热性能相对于旁管确实得到了强化。通过对比换热系数的试验值与经典努塞尔理论和努塞尔修正理论的计算值发现,中心管的试验值与努塞尔修正理论计算值吻合较好,但旁管的偏差较大。     

换热器传热强化单管筛选试验研究

介绍了油－水强化换热用整体外肋管和水－水强化换热用整体内，外翅片管的单管筛选试验情况，给出了传热和阻力测试结果，并给出了回归的传热系数关联式。试验结果表明，外肋管的总传热系数比光管提高约１５％，内、外翅片管比光管提高约５０％。     

环形狭缝通道内干涸后传热研究

以去离子水为工质的高温流体 ,由下向上流过电加热内、外管壁间的环形狭缝 ,对同心竖直环形狭缝进行了干涸后换热试验研究。试验结果表明 :环形缝隙中的干涸后换热 ,与普通环形通道中的换热有着明显不同。试验中发现在相同热流密度下内管换热能力大于外管。应用Groeneveld公式 ,拟给出适合试验数据的换热公式。在试验的基础上 ,对内外管中较大的热流密度 ,与内外管热流密度的平均值的比值建立变量 ,并应用多元线性回归方法 ,建立了适合工程实际应用的环形狭缝通道干涸后传热计算经验关联式。     

硬壳对熔融池换热特性影响试验研究

基于大型熔融池换热特性试验台架COPRA,分别采用水和非共晶摩尔比例20%NaNO₃-80%KNO₃混合物作为熔融物模拟物,进行熔融池换热特性试验研究。熔融池瑞利数Ra′可达到10¹⁶量级,与反应堆真实情况下的量级一致。试验对比了水试验和熔盐试验得到的熔融池温度场分布和壁面热流密度分布。结果表明,熔融物硬壳的形成对熔融池换热特性产生了明显影响。试验拟合得到了熔融池换热特性关系式,其中热流密度关系式与国际上其他试验得到的结果符合得较好。在同等Ra′量级下,COPRA试验得到的熔融池向下封头壁面的传热量较国际上其他试验的结果低。     

针翅管传热与压降特性研究

以润滑油为换热介质,对整体针翅管传热与阻力特性进行了理论分析与试验研究,研究结果可为针翅管的优化设计提供参考。在换热介质纵向冲刷换热管的条件下,对不同针翅长度的3种整体针翅管与光管进行了传热与阻力试验。结果表明：整体针翅管对润滑油换热具有很好的强化能力,在本试验范围内,整体针翅管对油流体扰动强烈,换热强度是同条件下光管的2~6倍;针翅长度是影响针翅管压降的主要因素,在雷诺数达300时,压降曲线出现转折。     

六边形排列的7棒束通道内液态钠流动换热特性试验研究

以液态钠作为试验工质,对六边形排列的7棒束通道内液态钠流动换热特性进行了试验研究。试验流速为0~4 m·s^-1,热流密度为0~120 kW·m^-2,系统压力为1.5~200 kPa,对应的雷诺数和佩克莱数分别为4 000~60 000和0~340。深入分析了部分热工参数对7棒束通道内液态钠流动换热特性的影响,通过对7棒束通道内液态钠流动换热的试验数据的非线性拟合,得到适用于7棒束通道内液态钠流动换热的经验关系式。结果表明：拟合得到的摩擦系数关系式和努塞尔数关系式能准确地预测7棒束通道内的试验数据,其预测误差分别小于5%和6%。将获得的努塞尔数关系式与其他研究者的试验数据进行比较,与其他研究者985%的试验数据误差在30%以内,表明获得的关系式适用于7棒束通道内液态钠流动换热。     

非能动余热交换器瞬态换热特性数值模拟及敏感性分析

以美国非能动型先进压水堆AP600的非能动余热交换器简化试验模型为FLUENT的数值计算模型,采用标准k-ε湍流模型和自然对流Boussinesq模型,对非能动余热交换器和内置换料水箱的自然对流换热特性进行数值模拟。模拟结果与试验结果基本一致,较好地再现了各瞬态工况下非能动余热交换器换热过程中温度、速度分布与加热时间的变化特性。敏感性分析表明,导流板结构及进口形式对自然对流影响很小,升高水箱初始温度或增加换热管数量均能加强换热效果。     

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。      

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.     

自然循环欠热沸腾起始点特性

利用适于强迫循环的伯格尔斯和罗斯诺经验方法、Davis和Anderson理论方法，以及本课题组依据自然循环实验提出的预测欠热沸腾起始点的经验公式，对两种类型的欠热沸腾起始点的热力学平衡干度进行比较计算，研究自然循环的欠热沸腾起始点的基本特性。研究结果表明：自然循环欠热沸腾起始点的热力学平衡干度对加热量、进口温度、系统压力有着更大的敏感特性，在同等条件下，更早发生欠热沸腾现象。统计物理的微观角度研究进一步指出：产生这一现象的根本原因在于处于自组织状态的自然循环耗散结构的特点、动力学的涨落力和动量力对热力学平衡的共同影响。此研究结果为今后研究和应用自然循环的欠热沸腾奠定了基础。     

Influence of subcooled boiling on out-of-phase oscillations in boiling water reactors

In this paper, we develop a reduced order model with modal kinetics for the study of the dynamic behavior of boiling water reactors. This model includes the subcooled boiling in the lower part of the reactor channels. New additional equations have been obtained for the following dynamics magnitudes: the effective inception length for subcooled boiling, the average void fraction in the subcooled boiling region, the average void fraction in the bulk-boiling region, the mass fluxes at the boiling boundary and the channel exit, respectively, and so on. Each channel has three nodes, one of liquid, one with subcooled boiling, and one with bulk boiling. The reduced order model includes also a modal kinetics with the fundamental mode and the first subcritical one, and two channels representing both halves of the reactor core. Also, in this paper, we perform a detailed study of the way to calculate the feedback reactivity parameters. The model displays out-of-phase oscillations when enough feedback gain is provided. The feedback gain that is necessary to self-sustain these oscillations is approximately one-half the gain that is needed when the subcooled boiling node is not included.     

人工神经网络在预测流动沸腾曲线中的应用

选用20世纪60年代以来的实验数据，应用人工神经网络分析入口欠热度、质量流速、压力等主要参数对沸腾曲线的影响。在整个传热区内，热流密度随入口欠热度的增加而增大；在过渡沸腾和膜态沸腾区，热流密度随质量流速的增加而增加；压力起重要的作用，除膜态沸腾区外，增加压力能强化传热。除泡核沸腾外，稳态和瞬态的流动沸腾曲线的差异很小。     

过冷流动沸腾中汽泡脱离直径的理论研究

汽泡脱离直径模型是壁面沸腾计算中的一个重要子模型。为了正确预测过冷流动沸腾中的壁面传热情况,研究结合新改进的汽泡生长模型,采用力平衡方法对过冷流动沸腾中的汽泡脱离直径进行了模拟。汽泡生长模型同时考虑了微液层、过热层和汽泡顶部过冷液体层对汽泡生长所做的贡献,并采用饱和沸腾与过冷沸腾2个实验对其进行了验证,结果表明预测曲线与实验值吻合良好。另外,选取了3个过冷流动沸腾实验来验证汽泡脱离直径模型,模拟结果均在可接受的误差范围内。      

低流速过冷沸腾净蒸汽产生点计算模型

已有的过冷沸腾净蒸汽产生点计算方法以高质量流速为主.对于低流速工况,到目前还未见普遍认同的净蒸汽产生点计算模型。本文通过加热壁面汽相蒸发与汽液界面冷凝传热的分析，建立于适用于低流速强迫循环及自然循环工况净蒸汽产生点的蒸发冷凝模型，在较宽广的工况范围内与已有实验数据进行了比较.研究表明,低流速工况下．该模型可以得出满意的预测结果，比目前广泛应用的Salla-Zuber模型以及Levy模型具有更高的预测精度.     

微重力下沸腾传热研究进展

微重力下的沸腾传热研究是航天技术领域最基本的研究课题之一．具有重要的学术意义和工程应用价值.本文从地面模拟技术、地面模拟实验、微重力实验和流动沸腾换热4个方面,介绍了微重力下沸腾传热研究进展.     

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.     

A comparative study of correlations of critical heat flux of pool boiling

Nucleate pool boiling is desirable for many engineering systems. One challenge task for designing a system with nucleate pool boiling is to estimate the critical heat flux (CHF), which needs an accurate pool boiling CHF correlation. A few evaluations of pool boiling CHF correlations were reported, which used limited experimental data or covered limited correlations, resulting in inconsistent results. Therefore, it is difficult to determine which one is more appropriate for a given application. In this paper, a database containing 600 data points of pool boiling CHF of 12 pure liquids on plain surfaces having orientation angles of 0°?180° is compiled from 40 published papers. The reduced pressure is from 0.0001 to 0.98, and the 13 fluids are water, helium, nitrogen, hydrogen, R113, FC-72, FC-87, HFE-7100, ethanol, benzene, hexane, pentane, and methanol. With the database, 21 pool boiling CHF correlations are assessed. The most accurate one has a mean absolute deviation of 27.1%, indicating a need for developing more accurate correlations for engineering applications. Besides, the factors affecting the accuracy of correlations are analyzed and some valuable conclusions are obtained. The work lays a valuable foundation for the further study of pool boiling CHF correlations and provides a guide for choosing proper correlations for given applications. Several topics worthy of attention for future studies are suggested.