Of all the nuclear reactors in operation today, light water reactors and pressurized water reactors in particular remain one of the most common designs. With 298 functioning units as of 2019, this type accounts for over 66% of all operating reactors [1]. The presented work attempts to expand the understanding of a pressurized water reactor (PWR) steam generator (SG) in a particular mode of operation, referred to as reflux condensation. The scenario in which SG tubes operate in a reflux condenser mode remains relevant to PWR mid-loop operation as well as a possible loss-of-coolant (LOCA) accident. In these modes, steam condensation in SG tubes provides a very efficient path for heat removal from the primary circuit of the nuclear reactor. T...
The research in this thesis supports the design of a horizontal tube bundle condenser for passive he...
The NHR-200 reactor in China adopts the noncondensable gas self-stabilizing control and the nonconde...
Passive Containment Cooling System (PCCS) of the Economic Simplified Boiling Water Reactor (ESBWR) i...
In this paper we investigated reflux condensation in a single pressurized water reactor steam genera...
a Vertical U-Tube Reflux and natural circulation condensation in vertical inverted U-tube steam gene...
a Vertical U-Tube Reflux and natural circulation condensation in vertical inverted U-tube steam gene...
Graduation date: 2008Reflux condensation tests examining steam condensation in a PWR steam\ud genera...
One of the engineered safety systems in the advanced boiling water reactor is a passive containment ...
Passive Containment Cooling System (PCCS) of the Simplified Boiling Water Reactor (SBWR) is a passiv...
Proposed is the analysis of steam condensation in the presence of inert gases in a power plant conde...
Proposed is the analysis of steam condensation in the presence of inert gases in a power plant conde...
In the nuclear fusion reactor, ITER, the Loss of Coolant Accident (LOCA) in the Vacuum Vessel has to...
In the nuclear fusion reactor, ITER, the Loss of Coolant Accident (LOCA) in the Vacuum Vessel has to...
In the nuclear fusion reactor, ITER, the Loss of Coolant Accident (LOCA) in the Vacuum Vessel has to...
The main goal of the project is to study analytically and experimentally condensation heat transfer ...
The research in this thesis supports the design of a horizontal tube bundle condenser for passive he...
The NHR-200 reactor in China adopts the noncondensable gas self-stabilizing control and the nonconde...
Passive Containment Cooling System (PCCS) of the Economic Simplified Boiling Water Reactor (ESBWR) i...
In this paper we investigated reflux condensation in a single pressurized water reactor steam genera...
a Vertical U-Tube Reflux and natural circulation condensation in vertical inverted U-tube steam gene...
a Vertical U-Tube Reflux and natural circulation condensation in vertical inverted U-tube steam gene...
Graduation date: 2008Reflux condensation tests examining steam condensation in a PWR steam\ud genera...
One of the engineered safety systems in the advanced boiling water reactor is a passive containment ...
Passive Containment Cooling System (PCCS) of the Simplified Boiling Water Reactor (SBWR) is a passiv...
Proposed is the analysis of steam condensation in the presence of inert gases in a power plant conde...
Proposed is the analysis of steam condensation in the presence of inert gases in a power plant conde...
In the nuclear fusion reactor, ITER, the Loss of Coolant Accident (LOCA) in the Vacuum Vessel has to...
In the nuclear fusion reactor, ITER, the Loss of Coolant Accident (LOCA) in the Vacuum Vessel has to...
In the nuclear fusion reactor, ITER, the Loss of Coolant Accident (LOCA) in the Vacuum Vessel has to...
The main goal of the project is to study analytically and experimentally condensation heat transfer ...
The research in this thesis supports the design of a horizontal tube bundle condenser for passive he...
The NHR-200 reactor in China adopts the noncondensable gas self-stabilizing control and the nonconde...
Passive Containment Cooling System (PCCS) of the Economic Simplified Boiling Water Reactor (ESBWR) i...