Cooling system in nuclear reactor is much influenced by counter-current flow. When a leakage is occured, coolant in primary circuit of hotleg and hot steam from reactor will flows in counter-current condition. An experimental investigation has been performed to examine the effect of flooding phenomenon on the pressure drop. It was observed using acrylic complex pipe as hotleg simulator consisting of three parts: horizontal, bend and inclined pipe. Geometrical sizes of pipes was in scale of 1/30 of the actual hotleg geometrical size in the PWR with inner diameter=25.4 mm, the horizontal pipe length L=635 mm, and inclined pipe length was 20 mm with an angle of 50o. Pressure drop was meassured by using differential pressure sensor installed in...
A new correlation for the prediction of the Countercurrent Flow Limitation (CCFL) in a large diamete...
A nuclear power plant operation requires reliability safety systems. Therefore, an accidental scenar...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR),...
Thesis (B.S.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1980.MICROFIC...
International audienceThis paper presents experimental investigations on flooding phenomenon of coun...
Countercurrent flow limitation (CCFL) is an important phenomenon for numerous engineering applicatio...
For certain values of fluid velocity of two phases, a wave forms covering as well as blocking the ar...
This research has been conducted study the effect of horizontal pipe length on flooding phenomenon. ...
Gas/liquid two-phase stratified flows in horizontal channels are frequently encountered in nuclear r...
Counter-Current Flow Limitation (CCFL) is of importance for PWR safety analyses in several accident ...
A counter current annular flow experiment was performed to determine flooding conditions for varying...
[[abstract]]The authors have set up a transparent air-water flow system, with an internal contractio...
An experimental study on flooding with steam and water in a large diameter vertical tube was conduct...
Research and study into gas-liquid countercurrent two-phase flow in a model of pressurized water rea...
To continue improving nuclear energy, new materials must be tested in testing reactors such as the A...
A new correlation for the prediction of the Countercurrent Flow Limitation (CCFL) in a large diamete...
A nuclear power plant operation requires reliability safety systems. Therefore, an accidental scenar...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR),...
Thesis (B.S.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1980.MICROFIC...
International audienceThis paper presents experimental investigations on flooding phenomenon of coun...
Countercurrent flow limitation (CCFL) is an important phenomenon for numerous engineering applicatio...
For certain values of fluid velocity of two phases, a wave forms covering as well as blocking the ar...
This research has been conducted study the effect of horizontal pipe length on flooding phenomenon. ...
Gas/liquid two-phase stratified flows in horizontal channels are frequently encountered in nuclear r...
Counter-Current Flow Limitation (CCFL) is of importance for PWR safety analyses in several accident ...
A counter current annular flow experiment was performed to determine flooding conditions for varying...
[[abstract]]The authors have set up a transparent air-water flow system, with an internal contractio...
An experimental study on flooding with steam and water in a large diameter vertical tube was conduct...
Research and study into gas-liquid countercurrent two-phase flow in a model of pressurized water rea...
To continue improving nuclear energy, new materials must be tested in testing reactors such as the A...
A new correlation for the prediction of the Countercurrent Flow Limitation (CCFL) in a large diamete...
A nuclear power plant operation requires reliability safety systems. Therefore, an accidental scenar...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR),...