The ROSA-SA project on containment thermal hydraulics

Yonomoto, Taisuke ; Shibamoto, Yasuteru ; Ishigaki, Masahiro ; Abe, Satoshi  

The thermal-hydraulic safety research group in JAEA is conducting the ROSA-SA (severe accident) project on containment thermal hydraulics based on the consideration of research issues after the Fukushima Dai-Ichi Nuclear Power Station accident. The project investigates phenomena related to over-temperature containment damage, hydrogen risk and fission product transport. Until now, we have designed a large-scale containment vessel test facility called CIGMA (Containment InteGral Measurement Apparatus), and analyzed phenomena including the erosion of density stratified layer by impinging jet and condensation with noncondensables using the computational fluid dynamics (CFD) code OpenFOAM. In this presentation, plans for researches and results obtained thus far are described.