Search
Now showing items 1-4 of 4
Critical Heat Flux on Curved Calandria Vessel of Indian PHWRs During Severe Accident Condition
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In pressurized heavy water reactors (PHWRs), during an unmitigated severe accident, the absence of adequate cooling arising from multiple failures of the cooling system leads to the collapse of pressure tubes and calandria ...
In-Vessel Retention of PHWRs: Experiments at Prototypic Temperatures
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In pressurized heavy water reactors (PHWRs), multiple failures of engineered safety features may cause a failure of core cooling eventually leading to core collapse. The failed fuel and fuel channels relocate to the bottom ...
Experimental Demonstration of AHWR Safety During Prolonged Station Black Out
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Fukushima accident has raised a strong concern and apprehension about the safety of a nuclear reactor failing to remove the decay heat following an extreme event. After Fukushima accident, the reactor designers worldwide ...
Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop
Publisher: The American Society of Mechanical Engineers (ASME)