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Thermal-Hydraulics of Water Cooled Nuclear Reactors by Francesco D'Auria

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7

Heat transfer in nuclear thermal hydraulics

P.L. Kirillov*; H. Ninokata    * Institute of Thermal Physics and Nuclear Science in the State Scientific Centre of the Russian Federation, Obninsk, Russia Tokyo Institute of Technology, Tokyo, Japan

Abstract

Power removal capability from structures housing the nuclear fuel is determined by heat transfer. Convection heat transfer in two-phase conditions sets the limits for the production of fission power. The amount of thermal power per unit area exchangeable from a solid to the two-phase mixture may suddenly change for two or three orders of magnitude (even more in certain conditions) when parameters like void fraction of fluid velocities reach some threshold values. Failures of safety barriers ...

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