An independent assessment of Groeneveld et al.'s 1995 CHF look-up table

The prediction capability of the 1995 CHF look-up table (Groeneveld D.C., et al., Nucl. Eng. Des. 163 (1996) 1–23) is independently assessed based on the KAIST data base consisting of 10?822 data for uniformly-heated, vertical, round tubes. This confirms the error statistics for the heat balance method reported by Groeneveld et al. and shows overall average and RMS errors of 4.2 and 36.7%, respectively, for the direct substitution method. The new 1995 table shows better prediction capability than the 1986 AECL-UO table (Groeneveld et al., 1986), especially for the low-pressure, low-flow region. The error analysis indicates the length effect even for significantly long tubes.     

Some problems for bundle CHF prediction based on CHF measurements in simple flow geometries

A comparison of critical heat flux (CHF) fuel bundles data with CHF data obtained in simple flow geometries was made. The base for the comparison was primary experimental data obtained in annular, circular, rectangular, triangular, and dumb-bell shaped channels cooled with water and R-134a. The investigated range of flow parameters (pressure, mass flux, and critical quality) in R-134a was chosen to be equivalent to modern nuclear reactor water flow conditions (p=7 and 10 MPa, G=350–5000 kg (m² s)⁻¹, x_cr=−0.1–1). The proper scaling laws were applied to convert the data from water to R-134a equivalent conditions and vise versa. The effects of flow parameters (p, G, x_cr) and the effects of geometric parameters (D, L) were evaluated during comparison. The comparison showed that no one simple flow geometry can be used for accurate and reliable bundle CHF prediction in wide range of flow parameters based on local (critical) conditions approach. The comparison also showed that the limiting critical quality phenomenon is unique characteristic for each flow geometry which depends on many factors: flow conditions (pressure and mass flux), geometrical parameters (diameter or surface curvature, gap size, etc.), flow obstructions (spacers, appendages, turbulizers, etc.) and others.     

Check of the 2005-look up table for prediction of CHF in bundles

The check whether it is possible to use the 2005-look up table primary designed for heated pipes also for heated rod bundles gives the surprising result that the bundle critical power for five data sets of three different bundles and different power distributions are predicted by a simple method described above using the 2005-look up table within the accuracy reported by the authors of this table.     

A critical heat flux approach for square rod bundles using the 1995 Groeneveld CHF table and bundle data of heat transfer research facility

The critical heat flux (CHF) approach using CHF look-up tables has become a widely accepted CHF prediction technique. In these approaches, the CHF tables are developed based mostly on the data bank for flow in circular tubes. A set of correction factors was proposed by Groeneveld et al. [Groeneveld, D.C., Cheng, S.C., Doan, T., 1986. 1986 AECL-UO Critical Heat Flux lookup table. Heat Transf. Eng. 7(1–2), 46] to extend the application of the CHF table to other flow situations including flow in rod bundles. The proposed correction factors are based on a limited amount of data not specified in the original paper. The CHF approach of Groeneveld and co-workers is extensively used in the thermal hydraulic analysis of nuclear reactors. In 1996, Groeneveld et al. proposed a new CHF table to predict CHF in circular tubes [Groeneveld, D.C., et al., 1996. The 1995 look-up table for Critical Heat Flux. Nucl. Eng. Des. 163(1), 23]. In the present study, a set of correction factors is developed to extend the applicability of the new CHF table to flow in rod bundles of square array. The correction factors are developed by minimizing the statistical parameters of the ratio of the measured and predicted bundle CHF data from the Heat Transfer Research Facility. The proposed correction factors include: the hydraulic diameter factor (K_hy), the bundle factor (K_bf), the heated length factor (K_hl), the grid spacer factor (K_sp), the axial flux distribution factors (K_nu), the cold wall factor (K_cw) and the radial power distribution factor (K_rp). The value of constants in these correction factors is different when the heat balance method (HBM) and direct substitution method (DSM) are adopted to predict the experimental results of HTRF. With the 1995 Groeneveld CHF Table and the proposed correction factors, the average relative error is 0.1 and 0.0% for HBM and DSM, respectively, and the root mean square (RMS) error is 31.7% in DSM and 17.7% in HBM for 9852 square array data points of HTRF.     

高流速下窄矩形通道内临界热流密度试验研究

在常压下,对具有窄间隙的矩形通道进行了下降流大流速临界热流密度试验研究。研究发现：大流速下临界热流密度随着流速的增加而呈线性增加,随出口含汽量的增加而减小Sudo公式的预测值较试验值要小在人口参数相同时。即相同的人口过冷度和质量流速式矩形通道的长度对临界热流密度的影响较小;如果从出口质量流速和出口含汽量来看,在相同的出口参数下,长度的增加将显著降低临界热流密度。     

Thermal unsteady regimes in one-dimensional flow of heat generating fluids

The thermal unsteady regimes in one-dimensional flow of heat generating fluids, caused by flow-rate changes, are studied when heat is transferred to surroundings of constant temperature. The heat generation is a function of time and temperature. General results are then applied to solve particular situations. Some numerical results are related and a short discussion is given.     

Application of artificial neural networks in analysis of CHF experimental data in round tubes

Artificial neural networks (ANNs) are applied successfully to analyze the critical heat flux (CHF) experimental data from some round tubes in this paper. A set of software adopting artificial neural network method for predicting CHF in round tube and a set of CHF database are gotten. Comparing with common CHF correlations and CHF look-up table, ANN method has stronger ability of allow-wrong and nice robustness. The CHF predicting software adopting artificial neural network technology can improve the predicting accuracy in a wider parameter range, and is easier to update and to use. The artificial neural nefwork method used in this paper can be applied to some similar physical problems.     

Experimental Investigation on CHF of Water Flowing in Upward Tube from Subcooled to High Quality Condition

<正>Critical heat flux experiment is performed in a tube of 8.2mm in inner diameter with 2.4min heated length.The pressure covers the ranges from 3to 21MPa,mass flux from 963to 3 883kg/(m~2·s),and outlet quality from-0.87to 0.78.For all the condition,CHF almost goes up linearly while mass flux or inlet subcooling increases,     

The effect of flow direction and magnitude on CHF for low pressure water in thin rectangular channels

Critical heat flux (CHF) at low flow condition can become important in an MTR-type research reactor under a number of accident conditions. Regardless of the initial stages of these accidents, a condition which is basically the decay heat removal by natural convention boiling can develop. Under such conditions, burnout may occur even at a very low heat flux. In view of this, the CHF at low-flow-rate and low-pressure conditions has been studied for water flowing in thin rectangular channels.Experiments were carried out with two types of rectangular test sections, namely, the one heated from one wide side and the other heated from two opposite sides. In order to observe the effects of gravity, CHF was measured both in upflow and downflow. The CHF at complete bottom blockage was also studied.The results indicate that burnout can occur at a much lower heat flux than pool-boiling CHF or than predicted by the conventional correlations. There was observed a minimum CHF at complete bottom blockage and at very low downflow. The low CHF at very low downflow appears to be due to the stagnation of the bubble in the heated section. This fact indicates that special care should be taken in analyzing the boiling phenomenon which occurs when the coolant flow is very low in a low pressure system.     

Experimental study on flow pattern and heat transfer of inverted annular flow

Experimental results are presented on flow pattern and heat transfer in the regions from inverted annular flow to dispersed flow in a vertical tube using freon R-113 as a working fluid at atmospheric pressure to discuss the correspondence between them. Axial distributions of heat transfer coefficient are measured and flow patterns are observed. The heat transfer characteristics are divided into three regions and a heat transfer characteristics map is proposed. The flow pattern changes from inverted annular flow (IAF) to dispersed flow (DF) through inverted slug flow (ISF) for lower inlet velocities and through agitated inverted annular flow (AIAF) for higher inlet velocities. A flow pattern map is obtained which corresponds well with the heat transfer characteristic map.     

Effect of rolling on the flowing and heat transfer characteristic of turbulent flow in sub-channels

The flowing and heat transfer of turbulent flow in typical 4 rod bundles in rolling motion is investigated with LES and URANS. As the rolling period decreases, the average wall shear stress increases, and the frictional resistance increases. The wall shear stress solved by LES is not good enough, while that of URANS is consistent with experiments. The variation of frictional resistance coefficient, Nusselt number and Reynolds stress with rolling amplitude is very weak. In rolling motion, the biggest frictional resistance coefficient is not located in a constant time.     

摇摆状态下气液两相流流型转变的实验研究

通过可视化观察和数码照片对摇摆状态下光滑有机玻璃管内气液两相流流型进行分类和定义,并分析了不同管径、摇摆角度以及摇摆周期对流型之间转变的影响.结果表明:在液相折算流速一样的情况下,管径增加、摇摆周期缩短或摇摆角度减小会使得环状流形成需要更高的气体折算流速;弹状流向搅混流转变所需气相流量则随着管径的减小、摇摆周期的增加或摇摆角度的减小而增加.而在气相折算流速一样的条件下,管径增加、摇摆周期缩短或摇摆角度增大会使泡状流产生需要更高的液相流量.     

Distribution of coolant flow rate in a steam generator in natural coolant circulation regimes

Conclusions The large hydraulic nonuniformity of steam generator pipes operating in parallel in the natural coolant circulation regime results in a lower efficiency of the heat-transfer surface during emergency cooldown of the reactor plant, and it limits the operational possibilities, specifically, for using this regime at partial power levels. It is obvious that circulation reversal in the pipes of steam generators in the natural circulation regime can have an unfavorable influence on individual structural elements of steam generators as a result of additional temperature stresses appearing in the metal. As one can see from Eq. (6), the conditions of the distribution of the coolant flow rate over pipes in a steam generator can be improved at the design stage. Specifically, they can be realized as an efficient ratio of the “macrogeometric” characteristics of the first loop ΔH and H_sgp as well as by the influence on the ratio of the hydraulic resistance of individual sections of the loop, which determine the numerical value of the parameter m. As m increases, other conditions remaining the same, the character of the distribution of the coolant flow rate in the pipes of a horizontal steam generator improves. Thus, designers of a nuclear power plant have ways to search for optimal solutions. It is obvious that the interrelations of the conditions of operation of a steam generator, examined above, and the natural circulation in the loop require that the distribution of the flow rate in a pipe bundle be taken into account in the physical simulation using special thermohydraulic stands. St. Petersburg State Technical University. Translated from Atomnaya énergiya, Vol. 83, No. 3, pp. 169–174, September, 1997.     

垂直上升矩形流道内气液两相流流型图的数值模拟

两相流流型在分析换热、流动不稳定性以及临界热流密度方面具有基础性作用.本文基于VOF(Volume of Fluid)多相流模型,对垂直上升矩形流道内气液两相流动进行数值模拟,表观气速0.1～110 m/s,表观液速0.1～3.2 m/s.得到了流道内气液两相流的主要流型:泡状流、弹状流、搅混流和环状流,分析了流道内截面含气率分布与流型的对应关系,以及截面含气率与气液两相流容积含气率的关系;分析了各种流型下的压降分布特性,并绘制了基于气液表观动能通量的不同流量下气液两相流的流型图,直观的表示出各种流型的分布区域及各流型间的流型转换边界,与已发表文献的实验结果对比符合较好.     

The effects of gas flow pattern on the generation of ozone in surface dielectric barrier discharge

Ozone production utilizing surface dielectric barrier discharge (SDBD) was experimental studied for different flow patterns considering the influences of transversal flow, lateral flow and different lateral flow positions. Results show that the flow patterns have a remarkable impact on the ozone yield by affecting the uniformity and turbulence of gas flow. Meanwhile, distributing the O₂ flow rate according to the intensity of the plasma reaction would also increase the generation efficiency of SDBD for ozone production. By improving the uniformity and introducing the lateral flow to the transversal flow, the highest ozone yield was obtained in flow pattern ‘F’. In this case, the ozone yield increased by 28.4% to 131 gkWh ⁻¹ from 102.8 gkWh⁻¹ in flow pattern ‘A’.     

Pressure effect on CHF enhancement in pool boiling of nanofluids

This paper investigates critical heat flux (CHF) in saturated pool boiling for water and TiO₂ nanofluid on a 7-mm-diameter vertical copper surface at pressures of 0.1–0.8 MPa. The nanofluid was prepared by dispersing 0.002 wt% TiO₂ nanoparticles in deionized water. The CHF of the nanofluid was enhanced about two times over that of water boiling at atmospheric pressure. With the increasing pressure, however, the CHF enhancement with the nanofluid decreases, and almost disappears at 0.8 MPa.     

Investigation on symmetry and characteristic properties of the fragmenting source in heavy-ion reactions through reconstructed primary isotope yields

In this report, a kinematical focusing technique will be briefly described, and using this technique, the primary hot isotope yields from the multiplicities of evaporated light particles, associated with isotopically identified intermediate mass fragments, are reconstructed. Symmetry energy and characteristic properties of the fragmenting source at the time of the intermediate mass fragment formation are extracted from these reconstructed primary isotope yields using a self-consistent manner. The extracted density-dependent symmetry energy is further compared with those experimentally extracted from other heavy-ion reactions in literatures. A direct connection between the freeze-out concept and transport model sim-ulations in a multifragmenting regime of heavy-ion colli-sions is also demonstrated quantitatively in the present work.     

Investigation on applicability of time-averaged X-ray CT images in two-phase flow measurement

ABSTRACT

Measuring the void fraction between fuel rods contributes to optimizing the geometrical design of fuel bundles for boiling water reactors (BWR). In this article, a method for reconstructing a three-dimensional void fraction distribution of two-phase flow by using an X-ray CT system is proposed. The performance was evaluated by both simulation and experiment. The simulation results suggested that the accuracy of the proposed method was within ±0.02, and from the experimental results, the void fraction in gas-liquid two-phase flows was successfully obtained with sufficient accuracy.     

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。