This research addresses the critical need for precise two-phase flow data in the development of computer simulation models, with a specific focus on the annular flow regime's droplet behavior. The study aims to contribute to the evaluation of safety and efficiency in nuclear reactors that handle fluids transitioning between liquid and gas states for thermal energy transport. Central to the investigation is the collection and analysis of droplet size and velocity distribution data, particularly to help with developing models for the water-cooled nuclear power plants. The experimental setup employs advanced tools, including a high-speed camera, lens, teleconverter, and a selected light source, to capture high-resolution images of droplets. Calibration procedures, incorporating depth of field testing, are implemented to ensure accurate droplet size measurements. A critical component of the research is the introduction of a droplet identification program, developed using Matlab, which facilitates efficient processing of experimental data. Preliminary results from the Virginia Tech test facility demonstrate the system's capability to eliminate out-of-focus droplets and obtain precise droplet data in a reasonable amount of time. Experimental results from the Rensselaer Polytechnic Institute test facility provide droplet size and velocity distributions for a variety of annular flow conditions. This facility has a concurrent two-flow system that pumps air and water at different rates through a 9.525 mm inner diameter tube. The conditions tested include gas superficial velocities ranging from 22 to 40 m/s and liquid superficial velocities ranging from 0.09 to 0.44 m/s. The measured flow has a temperature of 21°C and a pressure of 1 atm. / Master of Science / This research explores the behavior of small droplets as fluids transition between liquid and gas states, particularly within the context of the cooling water in nuclear power plants. The overarching goal is to collect data on these droplets to improve computer simulations that help design nuclear reactors and assess their safety. This is important because it is often infeasible due to safety, monetary, or time restrictions to physically test some nuclear reactor equipment. The study employs state-of-the-art technology, including high-speed cameras and specialized imaging tools, to capture and analyze droplet size distribution data. This investigation is pivotal in ensuring the fuel in nuclear reactors remain adequately cooled during part of the boiling process. The research methodology includes the development of a droplet identification program using Matlab, ensuring efficient processing of experimental data. Preliminary findings from experimental tests at Virginia Tech showcase the program's capability to filter out irrelevant data and provide accurate droplet information. Experimental results from the Rensselaer Polytechnic Institute annular flow test facility provide droplet size and velocity data for a range of conditions that cooling water may face. Beyond its contributions to nuclear engineering, this research holds promise for influencing advancements in various applications that involve liquid droplets, opening avenues for innovation in the broader scientific and engineering communities.
| Identifer | oai:union.ndltd.org:VTETD/oai:vtechworks.lib.vt.edu:10919/119243 |
| Date | 03 June 2024 |
| Creators | Cohn, Ayden Seth |
| Contributors | Mechanical Engineering, Liu, Yang, Pierson, Mark Alan, Haghighat, Alireza |
| Publisher | Virginia Tech |
| Source Sets | Virginia Tech Theses and Dissertation |
| Language | English |
| Detected Language | English |
| Type | Thesis |
| Format | ETD, application/pdf |
| Rights | In Copyright, http://rightsstatements.org/vocab/InC/1.0/ |
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