Simulation of subcooled flow instability for high flux research reactors using the extended code ATHLET


Simulation of subcooled flow instability for high flux research reactors using the extended code ATHLET

Hainoun, A.; Schaffrath, A.

Considering the specific features of high flux research reactors given by both high heat flux and high flow velocity, the ATHLET condensation model especially in subcooled flow conditions has been extended and a new correlation of critical heat flux (CHF) is implemented. To validate the extended program, the Thermal-Hydraulic Test Loop (THTL) of Oak Ridge National Laboratory (ORNL) was modeled with ATHELT and an extensive series of experiments concerning the onset of thermohydraulic flow instability (OFI) in subcooled boiling regime were calculated

  • Nuclear Engineering and Design 207 (2001) 2, 163-180

Permalink: https://www.hzdr.de/publications/Publ-3602