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 …
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 …
applications and safety of light water reactors. In particular, the possible occurrence of CCFL …
CATHENA: A thermalhydraulic code for CANDU analysis
BN Hanna - Nuclear Engineering and Design, 1998 - Elsevier
This paper describes the Canadian algorithm for thermal hydraulic network analysis
(CATHENA) transient, thermalhydraulics code developed for the analysis of postulated …
(CATHENA) transient, thermalhydraulics code developed for the analysis of postulated …
Numerical simulations of counter-current two-phase flow experiments in a PWR hot leg model using an interfacial area density model
T Höhne, D Lucas - International journal of heat and fluid flow, 2011 - Elsevier
In order to improve the understanding of counter-current two-phase flows and to validate
new physical models, CFD simulations of 1/3rd scale model of the hot leg of a German …
new physical models, CFD simulations of 1/3rd scale model of the hot leg of a German …
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 …
at which one phase can flow countercurrently to another phase. In the present study, the …
Experimental investigation of countercurrent flow limitation (CCFL) in a large-diameter hot-leg geometry: A detailed description of CCFL mechanisms, flow patterns …
S Al Issa, R Macian-Juan - Nuclear Engineering and Design, 2014 - Elsevier
Countercurrent flow limitation (CCFL) is experimentally investigated in large-diameter hot-
leg geometry. COLLIDER test facility consists of reactor vessel simulator (RVs), hot-leg pipe …
leg geometry. COLLIDER test facility consists of reactor vessel simulator (RVs), hot-leg pipe …
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 …
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 …
reactor (PWR) hot leg has been carried out over the last several decades. An extensive …
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 …
performed for air and water countercurrent flow in a test section with a length of 2160 mm …
Flooding in the pressurizer surge line of AP600 plant and analyses of APEX data
K Takeuchi, MY Young, AF Gagnon - Nuclear engineering and design, 1999 - Elsevier
For the passive AP600 plant, the three stages of ADS (automatic depressurization system)
valves are attached to the top of pressurizer. The existence of these valves makes liquid flow …
valves are attached to the top of pressurizer. The existence of these valves makes liquid flow …