Measurement of Liquid Film in Annular Flow Using X-Ray Densitometry

dc.contributor.authorHarvey, Devlin McCaulen
dc.contributor.committeechairLiu, Yangen
dc.contributor.committeememberFreeman, David Wayneen
dc.contributor.committeememberZhang, Jinsuoen
dc.contributor.departmentMechanical Engineeringen
dc.date.accessioned2025-06-06T08:03:59Zen
dc.date.available2025-06-06T08:03:59Zen
dc.date.issued2025-06-05en
dc.description.abstractTwo-phase annular flow film thickness is a crucial parameter in nuclear thermal hydraulics, yet conventional measurement techniques such as impedance probes may compromise accuracy by directly contacting and potentially disturbing the flow. Non-intrusive measurement methods are needed to provide more reliable film thickness data for improved reactor safety calculations in Boiling Water Reactors (BWR), Pressurized Water Reactors (PWR), and accident scenarios such as Loss of Coolant Accidents (LOCA), where accurate film thickness data is essential for reliable predictions in reactor analysis codes. This thesis evaluates x-ray densitometry as a non-intrusive alternative that measures film thickness without flow disturbance. Film thickness measurements were obtained for two-phase annular flow in a 9.5 mm pipe across various superficial gas and liquid velocities and compared against impedance probe data and established correlations. Through a calibration procedure, a correction factor is determined to enhance the x-ray densitometry system's measurement accuracy for film thickness. Using a specially designed test facility available at RPI, comprehensive film thickness data across annular flow conditions is generated, while simultaneously capturing dynamic wave characteristics including wave height, velocity and frequency. The experimental results were benchmarked against RPI's parallel-wire impedance probe data and established film thickness correlations. Based on these comparisons, one film thickness correlation was refined to achieve better agreement with both the x-ray densitometry results and two supplementary experimental datasets.en
dc.description.abstractgeneralInside nuclear reactors, water can flow inside the pipes as water or steam. When water and steam are flowing together, this is referred to as two-phase flow. When enough water boils into steam, a particular type of two-phase flow can occur called annular flow. This is characterized by a liquid film flowing on the inside of pipe walls while a steam column flows through the center. The thickness of this liquid film is a crucial parameter in heat transfer for the safe operation of nuclear reactors. This research uses an x-ray densitometry system to measure these films without having any direct influence on the flow itself. This is an advantage that x-ray densitometry system techniques have over traditional measurement methods, which require inserting a device into the flow, potentially disrupting the flow they are trying to measure. This study compares the measurement data of the x-ray densitometry system to that of the traditional measurement techniques as well as theoretical correlations developed by studies in the past. In addition to the measurement of liquid films, this study also analyzes various characteristics of waves that form on the surfaces of these films such as their height, speed, and frequency. This information can be used to help engineers understand the behaviors of liquid films and potentially develop more accurate correlations. These correlations can then be used to predict the behaviors of nuclear reactors during normal operations and accident scenarios to better prepare themselves and mitigate problems before they occur. By understanding these liquid films, this research can contribute to safe and efficient operation of nuclear power plants.en
dc.description.degreeMaster of Scienceen
dc.format.mediumETDen
dc.identifier.othervt_gsexam:44156en
dc.identifier.urihttps://hdl.handle.net/10919/135097en
dc.language.isoenen
dc.publisherVirginia Techen
dc.rightsIn Copyrighten
dc.rights.urihttp://rightsstatements.org/vocab/InC/1.0/en
dc.subjectfilm thicknessen
dc.subjectx-rayen
dc.subjectx-ray densitometryen
dc.subjectnuclear engineeringen
dc.subjectnuclear reactor safetyen
dc.titleMeasurement of Liquid Film in Annular Flow Using X-Ray Densitometryen
dc.typeThesisen
thesis.degree.disciplineNuclear Engineeringen
thesis.degree.grantorVirginia Polytechnic Institute and State Universityen
thesis.degree.levelmastersen
thesis.degree.nameMaster of Scienceen

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