Outcome of first containment cooling experiments using CIGMA

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

Proceedings of 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11) (USB Flash Drive), 10 Pages, 2016/10

First experiments at the CIGMA facility for investigations of LWR containment thermal hydraulics

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

Proceedings of 24th International Conference on Nuclear Engineering (ICONE-24) (DVD-ROM), 9 Pages, 2016/06

http://doi.org/10.1115/ICONE24-60515

The ROSA-SA project on containment thermal hydraulics

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

no journal, , 

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.