Article ID Journal Published Year Pages File Type
1729597 Annals of Nuclear Energy 2010 5 Pages PDF
Abstract

In this paper, utilizing a simplified physical model an analytical expression for the prediction of most probable corium fragment size as function of relative velocity corium–coolant is derived. Combining this equation with the available experimental data an important consequence for the nuclear safety result: the existence of a critical velocity corium–coolant which maximizes the destabilization of film boiling when an external pressure wave is supplied.

Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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