Advanced Diagnostics, Image Analysis, and Data-Driven Measurement of Two-Phase Flows in Nuclear Thermal Hydraulics

Reliable two-phase flow measurement is essential to nuclear thermal hydraulics because model development, validation, and safety analysis all depend on accurate information about flow structure, void fraction, interfacial area, bubble behavior, and phase distribution. In recent years, major progress has been made through the use of high-speed imaging, conductivity probes, x-ray methods, multi-sensor integration, and advanced image processing. At the same time, machine learning and data-driven analysis are creating new opportunities to improve feature extraction, uncertainty evaluation, and interpretation of complex experimental datasets. Important challenges remain, however, in measurement robustness, sensor fusion, uncertainty quantification, and the transfer of local experimental information into reactor-relevant modeling tools. This Research Topic aims to bring together contributions that advance experimental and data-analytic methods for two-phase flow measurement in nuclear systems.Goal:The goal of this Research Topic is to collect high-quality research that improves the measurement and interpretation of two-phase flow phenomena in nuclear thermal hydraulics. We aim to highlight advances in diagnostics, image analysis, and data-driven methods that strengthen the experimental basis for reactor safety and design analysis.Scope and information for Authors:We welcome focused contributions on experimental and data-driven methods for two-phase flow analysis in nuclear applications. Topics can include:• Optical, x-ray, probe-based, and integrated measurement methods for reactor-relevant two-phase flows• Image processing, computer vision, and machine learning for bubble detection, flow-regime analysis, and interfacial characterization• Uncertainty evaluation, sensor fusion, and validation of experimental thermal-hydraulic data• Applications of advanced diagnostics to bubbly, slug, annular, and other reactor-relevant flow conditions Topic editors: Dewei Wang, Yue Jin Source: https://www.frontiersin.org/research-topics/81079/advanced-diagnostics-image-analysis-and-data-driven-measurement-of-two-phase-flows-in-nuclear-thermal-hydraulics