Experimental Investigation and Modeling of Void Drift in Modern BWR Fuel Designs

von Corre, Jean-Marie Le
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 13 of 14 (2018)

Rod Bundle Annular Two-phase Flow Simulations using SCADOP and MEFISTO-T

von Corre, Jean-Marie Le
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 8 of 14 (2018)