Experimental design and analysis for film boiling heat transfer in a circular tube

Y Zhao, B Kuang, C Cao, G Wang, P Liu, J Deng… - Progress in Nuclear …, 2023 - Elsevier
In order to study the heat transfer of water during film boiling, stable film boiling heat transfer
experiments are conducted in a circular tube. As the temperature of the heater surface …

Experimental study of post-CHF heat transfer in a vertical tubular test section

Q Liu, H Sun, Y Liu, J Kelly, X Sun - International Journal of Heat and Mass …, 2021 - Elsevier
In this paper, post-CHF (critical heat flux) experiments are performed in a vertical tubular test
section with water as the working fluid to study the heat transfer characteristics during the …

Wall heat transfer in the inverted annular film boiling regime

Q Liu, X Sun - Nuclear Engineering and Design, 2020 - Elsevier
Inverted annular film boiling (IAFB) is one of the post critical heat flux (post-CHF) regimes,
which may occur during the core reflooding phase following large-break loss of coolant …

High-Resolution X-Ray Radiography Methods Developed for Post-CHF Experiment

J Diaz, Q Liu, V Petrov, A Manera, X Sun - Nuclear Technology, 2023 - Taylor & Francis
Radiation transmission measurement methods have become widely implemented in the
study of two-phase flow due to leaping advancements in detector efficiency, spatial …

Void fraction measurement and prediction of two-phase boiling flows in a tubular test section

Q Liu, J Diaz, V Petrov, A Burak… - Journal of …, 2023 - asmedigitalcollection.asme.org
Void fraction is one of the most important parameters that affect two-phase flow heat transfer
and pressure drop. In this paper, a commercial gamma densitometer and a high-speed X …

Flow regime transition in the post-CHF flow regimes under subcooled and low-quality conditions

Q Liu, J Kelly, X Sun - International Journal of Multiphase Flow, 2021 - Elsevier
Post critical heat flux (post-CHF) heat transfer may occur during loss of coolant accidents
(LOCAs) in water-cooled nuclear reactors when makeup water quenches the uncovered …

Study on interfacial friction in the inverted annular film boiling regime

Q Liu, J Kelly, X Sun - Nuclear Engineering and Design, 2021 - Elsevier
The interfacial friction factor is an important closure model in the two-fluid model for the
inverted annular film boiling (IAFB) regime. Almost all the interfacial friction factor …

Tree-Based Ensemble Learning Models for Wall Temperature Predictions in Post-Critical Heat Flux Flow Regimes at Subcooled and Low-Quality Conditions

Q Liu, Y Liu, A Burak, J Kelly… - ASME Journal of …, 2023 - asmedigitalcollection.asme.org
Accurately predicting post-critical heat flux (CHF) heat transfer is an important but
challenging task in water-cooled reactor design and safety analysis. Although numerous …

Radiation Transmission Imaging Applications for Nuclear Reactor Systems

J Diaz - 2022 - deepblue.lib.umich.edu
Computational advancements in the past couple of decades have propelled the capabilities
to design, model, and benchmark nuclear reactor systems. However, the lack of high …

Desing of the high Pressure HIgh temperature annuLUS flow (PHILUS) Facility

AH Karabacak - 2022 - vtechworks.lib.vt.edu
Critical heat flux (CHF) and post-CHF are two critical phenomena in light water-cooled
nuclear power plants regarding safety. Even though the general trends of CHF and post …