Thermal-hydraulic response of a reactor core following large break loss-of-coolant accident under flow blockage condition

Flow Blockage Accident Analysis of Tehran Research Reactor Fuel Assembly

Tehran Research Reactor (T.R.R.) is a pool-type, 5 MW thermal research reactor. One probable event is that if some external objects or debris fall down into the reactor core and cause obstruction of the coolant flow through one of the fuel assemblies, decreasing the surface flow area, ceases the coolant flow, and also raises the fuel and sheaths tempe...

Integral Behavior of the Atlas Facility for a 3-inch Small Break Loss of Coolant Accident

Over the past 30 years, several large integral facilities have been utilized in order to understand transient behavior in nuclear power plants. The main objective of these integral facilities was to enhance our physical understanding of transient phenomena during LOCA or non-LOCA transients. An integral database was also used as a basis for the development and verification of thermal hydraulic ...

effect of sub-grid scales on large eddy simulation of particle deposition in a turbulent channel flow

چکیده ندارد.

The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents

The effect of variation in thermal conductivity of light water reactor fuel elements on core response during loss-of-coolant accident scenarios is examined. Initially, a simplified numerical analysis is utilized to determine the time scales associated with dissipation of stored energy from the fuel into the coolant once the fission reaction is stopped. The analysis is then followed by full reac...

Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions