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

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11

The structure of system thermal-hydraulic (SYS-TH) code for nuclear energy applications

D. Bestion    Atomic Energy Commission, Grenoble, France

Abstract

The system thermal-hydraulic (SYS-TH) codes have played and will play a major role for investigating thermalhydraulics of complex systems in various situations and particularly in safety analysis. They have integrated the available knowledge which was produced during decades from the analysis of a large number of experiments. SYS-TH codes include an interface to build a nodalization of a reactor, thermal-hydraulic balance equations, models for conduction, radiation, neutron physics, fuel thermomechanics, chemical reactions, and instrumentation and control (I&C) systems. They are used to ...

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