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Browsing Department of Mechanical and Industrial Engineering by Subject "Pressurized water reactors -- Critical heat flux"

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Estimation of critical heat flux in vertically downward two-phase flows

Sripada, Rajeshwar (2020)

Critical Heat Flux (CHF) is one of the important design considerations of two-phase flow equipment used in many industries including nuclear, chemical and power plants. If the CHF is not accounted for properly, it may ...

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