Abstract
The paper contains the results of numerical simulation of stainless steel melt motions on the surface of uranium dioxide. The investigations are performed for purposes of understanding of the fuel rod behavior during the core disruptive accident in the fast reactors. The systems of mass, energy and momentum conservation equations are solved to simulate melt motion on the surface of the fuel pin. Heat transfer and friction between melt and pin's surface and melt and coolant flow are taken into consideration. The dependences of mass of the melt and the features of the melt motion on coolant velocity and contact angle between melt and surface of the fuel rod are presented.
Highlights
Core disruptive accidents are characterized by fuel rods assembly destruction with release of huge amount of fission products
These types of rods are characterized by low yield stress of fuel cladding with compare of fuel rods with low burnout
The film flow regime is typical for stainless steel melt motion during loss-of-coolant accident
Summary
Core disruptive accidents are characterized by fuel rods assembly destruction with release of huge amount of fission products. The fuel rod destruction may be caused by several reasons. The first reason is a mechanical destruction due to large mechanical stress of stainless steel fuel cladding. The second reason is a melting of fuel rod due to overheating. The first mechanism is realized in fuel rods with large burnout. These types of rods are characterized by low yield stress of fuel cladding with compare of fuel rods with low burnout. The second mechanism is the main object of the presented investigation. The importance of this mechanism connected with the fact that melting of fuel rods is the most dangerous for reactors safety and can cause irreversible sequences in the reactor operation. In the paper the features of stainless steel melt motion on the surface of uranium dioxide are discussed
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