Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges

GH Yeoh - Experimental and Computational Multiphase Flow, 2019 - Springer
Thermal hydraulic analysis of nuclear reactor core and its associated systems can be
performed using analysis system, subchannel or computational fluid dynamics (CFD) codes …

A review of CCFL phenomenon

S Al Issa, R Macian - Annals of Nuclear Energy, 2011 - Elsevier
Counter current flow limitation CCFL is an important phenomenon for numerous engineering
applications and safety of light water reactors. In particular, the possible occurrence of CCFL …

Scale effects on countercurrent gas-liquid flow in a horizontal tube connected to an inclined riser

A Ohnuki, H Adachi, Y Murao - Nuclear Engineering and Design, 1988 - Elsevier
The scale effects of a flow path under countercurrent flow limitation (CCFL)(air/water or
steam/saturated water) in a horizontal tube connected to an inclined riser have been …

Study of countercurrent flow limitation in a horizontal pipe connected to an inclined one

MA Navarro - Nuclear Engineering and Design, 2005 - Elsevier
Experiments with air and water in small hot leg reproductions were carried out aiming to
acquire a better understanding of the countercurrent flow limitation (CCFL) in this geometry …

Two-phase countercurrent flow in a model of a pressurized water reactor hot leg

S Wongwises - Nuclear Engineering and Design, 1996 - Elsevier
The onset of flooding or countercurrent flow limitation (CCFL) determines the maximum rate
at which one phase can flow countercurrently to another phase. In the present study, the …

Statistical characterization of liquid film fluctuations during gas-liquid two-phase counter-current flow in a 1/30 scaled-down test facility of a pressurized water reactor …

AH Astyanto, JAE Pramono, I Catrawedarma - Annals of Nuclear Energy, 2022 - Elsevier
The present work investigates the statistical characteristics of the fluctuations of the liquid
film thickness obtained by resistive-conductance probe signals of a complex geometry …

A simple model for vertical annular and horizontal stratified two-phase flows with liquid entrainment and phase transitions: one-dimensional steady state conditions

V Stevanovic, M Studovic - Nuclear Engineering and Design, 1995 - Elsevier
A simple one-dimensional three-fluid model is presented for the simulation and analyses of
vertical annular and stratified horizontal or inclined two-phase flows. The model has been …

Gas–liquid countercurrent two-phase flow in a PWR hot leg: a comprehensive research review

T Höhne, D Lucas, K Vierow - Nuclear Engineering and Design, 2012 - Elsevier
Research into gas–liquid countercurrent two-phase flow in a model of pressurized water
reactor (PWR) hot leg has been carried out over the last several decades. An extensive …

Hydraulic jump induced flooding and slugging in stratified gas-liquid flow–An experimental appraisal

M Dhar, S Ray, G Das, PK Das - Experimental Thermal and Fluid Science, 2022 - Elsevier
The paper presents an experimental approach to investigate the role of planar hydraulic
jump in termination of stratified gas-liquid flow in a narrow rectangular conduit. When the …

Experimental studies of flooding in nearly horizontal pipes

KY Choi, HC No - International journal of multiphase flow, 1995 - Elsevier
To investigate the flooding phenomenon in nearly horizontal pipes, experimental studies are
performed for air and water countercurrent flow in a test section with a length of 2160 mm …