During the first phase of the Fukushima Daiichi severe accident, the reactor core isolation cooling system (RCIC), installed in unit 2 (1F2) and unit 3 (1F3), was operated in order to maintain high core water levels. Even though the RCIC systems in the two units have quite similar design, the pressure increase in the two suppression chambers was significantly different. The main RCIC design is identical in the unit 2 and 3, except for the RCIC sparger. While in the 1F2 it is a vertical pipe open at its bottom, in the 1F3 it is a vertical multi-hole sparger, with 432 holes with 1 cm diameter along its top region, and 252 holes with 2.5 cm diameter in its bottom region. The very different configuration is believed to play an important role i...
This work considers the Pressure Suppression Chamber, a component of the Reactor Core Isolation Cool...
Unstable direct contact condensation called ``Chugging'’ that occurs in certain conditions in the pr...
In any conceptual reactor design under postulated accidental conditions, one parameter that is consi...
During the first phase of the Fukushima Daiichi severe accident, the reactor core isolation cooling ...
In the unlikely event of a nuclear power plant long duration station black-out, as in the Fukushima ...
Severe accident codes study the thermo-hydraulics of the suppression chamber with a limited numbers ...
Severe accident codes study the thermo-hydraulics of the suppression chamber with a limited numbers ...
In the unlikely event of a Nuclear Power Plant (NPP) long duration station black-out, as in the Fuku...
Steam is exhausted from a turbine into the BWR suppression pool as a means to remove energy from the...
Chugging of steam direct contact condensation is a well-known phenomenon and one of the most studied...
The primary safety concern at a nuclear reactor is to maintain water inventory inside the reactor co...
This work considers the Pressure Suppression Chamber, a component of the Reactor Core Isolation Cool...
Unstable direct contact condensation called ``Chugging'’ that occurs in certain conditions in the pr...
In any conceptual reactor design under postulated accidental conditions, one parameter that is consi...
During the first phase of the Fukushima Daiichi severe accident, the reactor core isolation cooling ...
In the unlikely event of a nuclear power plant long duration station black-out, as in the Fukushima ...
Severe accident codes study the thermo-hydraulics of the suppression chamber with a limited numbers ...
Severe accident codes study the thermo-hydraulics of the suppression chamber with a limited numbers ...
In the unlikely event of a Nuclear Power Plant (NPP) long duration station black-out, as in the Fuku...
Steam is exhausted from a turbine into the BWR suppression pool as a means to remove energy from the...
Chugging of steam direct contact condensation is a well-known phenomenon and one of the most studied...
The primary safety concern at a nuclear reactor is to maintain water inventory inside the reactor co...
This work considers the Pressure Suppression Chamber, a component of the Reactor Core Isolation Cool...
Unstable direct contact condensation called ``Chugging'’ that occurs in certain conditions in the pr...
In any conceptual reactor design under postulated accidental conditions, one parameter that is consi...