SULTAN test facility for large-scale vessel coolability in natural convection at low pressure

Experimental investigation of the permeability of PWR insulation panels for ex-vessel cooling

“…4b). Numerous publications have investigated CHF (Dinh et al, 2003;Rouge, 1997;Kang et al, 2005;Jeong et al, 2003). In an open circuit CHF is mainly controlled by recirculation between the ascending two-phase flow near the lower head and the descending liquid flow in the cavity (Fig.…”

In-Vessel Core Degradation

“…A number of tests have been carried out using a variety of approaches. Among these, the most interesting large-scale tests are ULPU (UCSB) [33] [49] [50] [51] [52], SULTAN (CEA) [53], and KAIST (Korea) [54].…”

Corium Behavior in the Lower Plenum of the Reactor Vessel Under Ivr-Ervc Condition: Technical Issues

“…The CHF is determined to fix the maximum heat removal rate through the external coolant between the outer reactor vessel and the insulation of the reactor vessel. Many studies regarding the CHF on the outer reactor vessel, such as ULPU [14][15][16] and SULTAN [17][18], have been performed. For an application of the IVR-ERVC to a new nuclear power plant, it is necessary to verify water contact to the spherical outer reactor vessel and to determine the CHF.…”