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

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13

Verification and validation of system thermal-hydraulic computer codes, scaling and uncertainty evaluation of calculated code results

H. Glaeser    GRS, Garching, Germany

Abstract

The approximations of system thermal-hydraulic (SYS TH) codes necessitate proper verification and validation (V&V) processes. Validation by predictions of complex phenomena can only be performed after the availability of relevant experimental data. Since many experiments used to validate a code are in small scale compared with a nuclear reactor, the scaling effects have to be considered. Therefore, scaling effects or addressing the scaling issues must be part of the validation activity. Deviations between calculation results and experimental data are observed. ...

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