A collaborative effort between US and Hungarian specialists was undertaken to investigate the response of a VVER-440/213-type NPP to a maximum design-basis accident, defined as a guillotine rupture with double-ended flow from the largest pipe (500 mm) in the reactor coolant system. Analyses were performed to evaluate the magnitude of the peak containment pressure and temperature for this event; additional analyses were performed to evaluate the ultimate strength capability of the containment. Separate cases were evaluated assuming 100% effectiveness of the bubbler-condenser pressure suppression system as well as zero effectiveness. The pipe break energy release conditions were evaluated from three sources: (1) FSAR release rate based on Sov...
AbstractSince the inception of nuclear power as a commercial energy source, safety has been recogniz...
Being the Vacuum Vessel Pressure Suppression System (VVPSS) one of the most important passive safety...
The consequences of sever reactor accident depend greatly on containment safety features and contain...
A collaborative effort between US and Hungarian specialists was undertaken to investigate the respon...
AbstractIn a reactor coolant system of a nuclear power plant (NPP), an overpressure protection syste...
Due to the Three Mile Island accident in 1979 the Swedish government took the decision in 1986 to im...
Containment Filtered Vent Systems (CFVSs) have been mainly equipped in nuclear power plants in Europ...
ABSTRACT Demonstrating the structural integrity of U.S. nuclear power plant (NPP) containment struct...
This diploma thesis deals with a pressure suppression system containment during the loss of coolant ...
Containment behaviour plays a key role in the safety framework of a Nuclear Power Plant (NPP). The G...
This paper describes the results of an analysis of loss of coolant accidents (LOCA`s) for the Soviet...
Accident conditions involving significant core degradation are termed severe accidents /IAEA: NS-G-2...
In SECY-90-016, the NTRC proposed a safety goal of a conditional containment failure probability (CC...
A general review is given of containment technology for water-coolednuclear reactors, including disc...
ABSTRACT- NPP Krsko is a Pressure Water Reactor (PWR) Plant which has four barriers to prevent relea...
AbstractSince the inception of nuclear power as a commercial energy source, safety has been recogniz...
Being the Vacuum Vessel Pressure Suppression System (VVPSS) one of the most important passive safety...
The consequences of sever reactor accident depend greatly on containment safety features and contain...
A collaborative effort between US and Hungarian specialists was undertaken to investigate the respon...
AbstractIn a reactor coolant system of a nuclear power plant (NPP), an overpressure protection syste...
Due to the Three Mile Island accident in 1979 the Swedish government took the decision in 1986 to im...
Containment Filtered Vent Systems (CFVSs) have been mainly equipped in nuclear power plants in Europ...
ABSTRACT Demonstrating the structural integrity of U.S. nuclear power plant (NPP) containment struct...
This diploma thesis deals with a pressure suppression system containment during the loss of coolant ...
Containment behaviour plays a key role in the safety framework of a Nuclear Power Plant (NPP). The G...
This paper describes the results of an analysis of loss of coolant accidents (LOCA`s) for the Soviet...
Accident conditions involving significant core degradation are termed severe accidents /IAEA: NS-G-2...
In SECY-90-016, the NTRC proposed a safety goal of a conditional containment failure probability (CC...
A general review is given of containment technology for water-coolednuclear reactors, including disc...
ABSTRACT- NPP Krsko is a Pressure Water Reactor (PWR) Plant which has four barriers to prevent relea...
AbstractSince the inception of nuclear power as a commercial energy source, safety has been recogniz...
Being the Vacuum Vessel Pressure Suppression System (VVPSS) one of the most important passive safety...
The consequences of sever reactor accident depend greatly on containment safety features and contain...