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

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11.14 Predictive capabilities of SYS-TH codes

11.14.1 Status of current system codes

The current generation of best-estimate system codes fully met the difficult challenge of replacing the previous conservative evaluation models to provide more accurate and reliable safety analyses of most accidental transients of interest for LWRs.

A huge effort was spent to provide sufficient experimental data to develop and validate the 150-to-200 closure laws of the system of equations. This experimental program considerably improved the knowledge of the two-phase flow phenomenology at system, component and local levels. The SETs covered all local and component physical situations. The various IET facilities were necessary to validate the global consistency ...

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