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 ...
Quenching of a Heated Rod: Physical Phenomena, Heat Transfer, and Effect of Nanofluids
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The physical phenomena of rewetting and quenching are of prime importance in nuclear reactor safety in the event of a loss of coolant accident (LOCA). Generally, top spray or bottom flooding concepts are used in reactors. ...
Exploring the Use of Alumina Nanofluid as Emergency Coolant for Nuclear Fuel Bundle
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Nanofluids are suspensions of nanosized particles in any base fluid that show significant enhancement of their heat transfer properties at modest nanoparticle concentrations. Due to enhanced thermal properties at low ...
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 ...