Engineering topics

Ferng, Yuh-Ming

Publications and source records attributed to Ferng, Yuh-Ming.

4 records

DOE OSTI2017

CFD Simulation of Bubble Growing Under a Downward Facing Surface

The heat removing of downward facing surface is an important issue in many areas, including nuclear safety, solar storage system and electronic cooling devices. Therefore, the characteristic and heat removal capability of downward facing boiling were investigated by many experiments in recent years. Among these studies, the thickness of bubble is considered as an important parameter. The increasing of bubble thickness will increase the thermal resistance of cooling process and reduce the cooling ability. In order to focus on the dynamics of bubble thickness, Das et al. injected air into sodium dodecyl sulphate (SDS) solution through a nozzle under the horizontal downward facing surface. The bubble will be formed by the air injection and kept under the horizontal plate. The diameter of nozzle, horizontal plate and SDS solution tank are 2 mm, 20 mm and 30 mm, respectively. The growing processing and the stable thickness of the bubble were recorded in the experiment. Basing on the conditions of Das's experiment, the appropriate computational fluid dynamics (CFD) simulation was conducted. The growing process and the stable thickness of bubble under difference contact angle are predicted by CFD in this study.

42 ENGINEERING↗

DOE OSTI2017

Processing Methodology for Double Sensor Probe in a Bubbly Flow

Bubbly flow phenomenon is the most common flow pattern in nuclear plant system. In this paper, according to Hibiki and Bartel, the experiment was designed to observe the fluid conditions surrounding nuclear rod. In recent years, double sensor probe is one of the measuring techniques for the bubbly flow. It can measure local void fraction and bubble velocity. After mathematical statistical calculation, interfacial area concentration is obtained by Kataoka. The double sensor probe method, with the advantage for measuring local interfacial area concentration, has become widely used in many measurement methods. The paper of Liu and Zhao were referred to establish the post-processing for the raw data obtained from measuring instrument. After drawing the signal of the probe, it is important to analyze the raw data for the elimination of unnecessary noise signal and highlight the characteristic signal. Based on the same experimental condition, the different filtering methods, Simple Moving Average (SMA) and Gaussian average, were compared and discussed by the double sensor probe.

42 ENGINEERING↗

DOE OSTI2017

The Flow Visualization for the Separation of Air-water Bubbly Two-phase Flow Through a Vertical T-junction

T-junction is a typical structure in many industrial systems such as power plants, chemical process, and hydrocarbon production industries. The separation of two-phase flow passing through T-junction is a common flow phenomenon. There are lots of investigations regarding two-phase flow separation in branching tees and wyes tees. The characteristic of the two-phase flow between the two outlets are always non-uniform, and this kind of fluid status may contribute to the unpredictable damage of downstream facilities. For the nuclear power plants, severe accidents analysis is important especially for Light-Water Reactors (LWR) when Loss of Coolant Accident (LOCA) occurs. The small break of the pipe may cause the coolant become two-phase flow due to the pressure drop. Under certain conditions, the behavior of T-junction is similar to a gas-liquid separator, as a result of the gas enters the side arm and the liquid flows straight along the run arm. The partial separation of gas-liquid mixtures can reduce the load on the main separator, probably leading to smaller units. The study aims to establish complete visual observations for the benchmark of Computational Fluid Dynamics (CFD) model. As a consequence, a vertical T-junction (D = 26 mm) experimental loop was set up for the purpose of elaborating the complex two-phase fluid phenomena. In this experiment, variables were manipulated under highly controlled conditions and a photographic method was proposed to analyze the images of phase separation. Furthermore, the images obtained by camera have been discussed to receive valuable information about the two phase flow behavior around the T-junction.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

DOE OSTI2017

Flow Characteristics of Intermediate Heat Exchanger with CFD Methodology on Nuclear Safety Application

The intermediate heat exchanger (IHX) plays an important role in the field of nuclear power plant, and its safety margin could strongly affected by the flow distribution of secondary flow inlet. As a result, the size of secondary inlet is crucial in thermal design. However, the IHX contains thousands of heat exchanger tubes, and it takes larger time to simulate each tube accurately. Other than that, there are more delicate devices in a nuclear power plant, so it would take too much time to simulate actual model. Although system code could solve problems effectively, it could not detect local deformation. On nuclear safety application, how to save time and receive specific results in an efficient way is necessary. Therefore, the porous media model and the heat exchanger model from computational fluid dynamics (CFD) were adopted in this study. The methodology not only can save much time than actual model but also receive more specific results than system code. To ensure the accuracy, validation of the methodology is also presented in this study by modeling RHR heat exchanger of L nuclear power plant. The results of the simulation were compared to experimental values from L nuclear power plant and receive small errors.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗