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Journal Articles

Experimental study on outer surface cooling of containment vessel by using CIGMA

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

Proceedings of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) (USB Flash Drive), 14 Pages, 2017/09

Journal Articles

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

Journal Articles

Thermal-hydraulic safety research on nuclear containment vessel at JAEA

Shibamoto, Yasuteru; Yonomoto, Taisuke; Hotta, Akitoshi*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 58(9), p.553 - 557, 2016/09

no abstracts in English

Journal Articles

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

Journal Articles

RANS analyses on erosion behavior of density stratification consisted of helium-air mixture gas by a low momentum vertical buoyant jet in the PANDA test facility, the third international benchmark exercise (IBE-3)

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

Nuclear Engineering and Design, 289, p.231 - 239, 2015/08

 Times Cited Count:13 Percentile:79.22(Nuclear Science & Technology)

Journal Articles

Thermal hydraulic safety research at JAEA after the Fukushima Dai-ichi Nuclear Power Station accident

Yonomoto, Taisuke; Shibamoto, Yasuteru; Takeda, Takeshi; Satou, Akira; Ishigaki, Masahiro; Abe, Satoshi; Okagaki, Yuria; Sun, Haomin; Tochio, Daisuke

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.5341 - 5352, 2015/08

Journal Articles

A Study on improvement of RANS analysis for erosion of density stratified layer of multicomponent gas by buoyant jet in a containment vessel

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

Journal of Energy and Power Engineering, 9(7), p.599 - 607, 2015/07

The analysis on a density stratification layer consisting of multiple gases in the reactor containment vessel is important for the safety assessment of sever accidents. The Japan Atomic Energy Agency (JAEA) has started the project on the containment thermal hydraulics. We carried out Computational Fluid Dynamics (CFD) analyses in order to investigate the erosion of the density stratification layer by a vertical buoyant jet under this project. We used the Reynolds averaged numerical simulation (RANS) and Large eddy simulation (LES) models to analyze the erosion of a density stratification layer by a vertical buoyant jet in a small vessel which represents a containment vessel. This numerical study calculates the turbulent mixing of a two-component (air and helium) gas mixture. The turbulence models used for the RANS analyses are two types of k-$$varepsilon$$ models. The first model is the low Reynolds number k-$$varepsilon$$ model developed by Launder and Sharma. The second model is modified from the first model in order to accurately consider the turbulent production and damping in a stratification layer. The results indicated while the erosion rate calculated by the low-Re k-$$varepsilon$$ model was much faster than that of the LES model, the modified k-$$varepsilon$$ model could calculate the erosion rate similar to the LES result.

Oral presentation

A Study on density stratification phenomena in a reactor containment vessel during a severe accident

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

no journal, , 

no abstracts in English

Oral presentation

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.

Oral presentation

Research program of thermal hydraulic behavior in containment vessel

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

no journal, , 

no abstracts in English

Oral presentation

Experimental and numerical study on density stratification erosion by a vertical jet in a small vessel

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

no journal, , 

no abstracts in English

Oral presentation

Experiment and analysis on thermal-hydraulics research of containment vessel at NSRC of JAEA

Shibamoto, Yasuteru

no journal, , 

no abstracts in English

Oral presentation

First experiments using the CIGMA facility on LWR containment thermal hydraulics

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

no journal, , 

no abstracts in English

Oral presentation

CIGMA experiment CC-PL-04 on thermal hydraulics behavior in containment vessel by outer surface cooling, 1; Experimental results and RELAP5 analysis

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

no journal, , 

no abstracts in English

Oral presentation

The CIGMA facility experiment on containment vessel outer surface cooling; Effect of initial gas composition

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

no journal, , 

no abstracts in English

Oral presentation

The CIGMA facility experiment on containment vessel outer surface cooling, 2; Effect of initial gas composition, 2

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

no journal, , 

no abstracts in English

Oral presentation

The CIGMA facility experiment on containment vessel outer surface cooling; Effect of boundary heat transfer

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

no journal, , 

no abstracts in English

17 (Records 1-17 displayed on this page)
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