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

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15

Applications of SYS TH codes to nuclear reactor design and accident analysis

F. D'Auria; G.M. Galassi    University of Pisa, Pisa, Italy

Abstract

Envisaged Nuclear Power Plant transient performances are translated via experiments and expert judgement into lists of accidents. Accident scenarios are at the origin of phenomena. Phenomena are characterized by parameters or variables. The parameter values can be translated into requirements for predictive capabilities in thermal-hydraulics. The safety acceptance criteria consist of threshold parameter values. These are established by logical processes typically independent upon thermal-hydraulics knowledge. A global vision of nuclear reactor thermal-hydraulics is provided in the chapter from ...

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