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Análisis de Sensibilidad en una Rotura de Tamaño Intermedio con TRACES

Querol Vives, Andrea; Gallardo Bermell, Sergio; Verdú Martín, Gumersindo Jesús (Grupo Senda, 2012)

Los datos experimentales disponibles sobre pequeñas roturas en una central nuclear son muy abundantes en comparación con los datos sobre roturas intermedias. Por este motivo, dentro del Proyecto OECD/NEA ROSA-2, se ha ...
Análisis termohidráulico de la instalación LSTF/ROSA utilizando el código TRACE5. Aportaciones a la metodología de escalado

Querol Vives, Andrea (Universitat Politècnica de València, 2016-01-07)

[EN] The origin of the scaling-issue is the impossibility to obtain measured data in case of an accident in nuclear reactors. The knowledge of thermal hydraulic phenomena oc-curring in Nuclear Power Plants (NPP) during an ...
Appliance of scaling methodologies for designing counterpart experiments dominated by natural circulation phenomena

Lorduy, M.; Gallardo Bermell, Sergio; Verdú Martín, Gumersindo Jesús (Elsevier, 2021-12-01)

[EN] The utility of the Integral Test Facilities (ITF) for the study of thermohydraulic phenomena that can occur in nuclear power plants has been demonstrated. However, direct extrapolation of data between different scales ...
Scaling analysis of an IBLOCA counterpart test between the ATLAS and LSTF facilities

Lorduy, M.; Gallardo Bermell, Sergio; Verdú Martín, Gumersindo Jesús (Elsevier, 2020-09)

[EN] The experiments carried out in test facilities improve knowledge of the phenomena that would occur in a nuclear power plant during an accident, and support the validation of the thermal-hydraulic codes used in the ...

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