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Oral presentation

Thermodynamic analysis for the fuel materials

Shirasu, Noriko

no journal, , 

This lecture consists of the basics of phase diagrams and the Calphad methodology, and introduction of thermodynamic analysis for the fuel materials. In the lecture, the thermodynamic analysis for U-Zr-O system and the thermodynamic evaluation on chemical reaction between degraded nuclear fuel and B$$_{4}$$C control rod are described.

Oral presentation

Study on boiling heat transfer characteristics in debris beds

Sakurada, Keishi*; Kawakami, Taira*; Sakashita, Hiroto*; Ono, Ayako; Yoshida, Hiroyuki

no journal, , 

This study measured the dryout heat fluxes for bottom heated debris beds, where small spherical particles were placed on a 75mm diameter heating surface. The data were obtained by varying the particle size in the range of 3 to 10mm, and compared with the predicted results with the one dimensional model proposed by Lipinski.

Oral presentation

Study on boiling heat transfer characteristics in debris beds, 2; Dryout heat flux for bottom and volume heated debris beds

Sakurada, Keishi*; Kawakami, Taira*; Sakashita, Hiroto*; Ono, Ayako; Yoshida, Hiroyuki

no journal, , 

This study measured the dryout heat fluxes on a bottom surface for bottom and volume heated debris beds, where small spherical metal particles were placed on a 75 mm diameter heating surface and internally heated by induction heating. The data were obtained by varying the particle size and the volumetric heated rate, and compared with the available correlations.

Oral presentation

Study on boiling heat transfer characteristics in debris beds, 3; Effects of volumetric heated rate and bed height on critical heat flux

Kawakami, Taira*; Sakurada, Keishi*; Sakashita, Hiroto*; Ono, Ayako; Yoshida, Hiroyuki

no journal, , 

The effect of height and density of accumulated particles on the critical heat flux was investigated on the heating surface, where the particles were accumulated, in order to investigate the cooling process of debris under the severe accident. The thermal-hydraulic behavior on the heating surface was visualized from the backsides of heating surface made of glass.

Oral presentation

Study on boiling heat transfer characteristics in debris beds, 4; Visualization of boiling behaviors on a heating surface

Kawakami, Taira*; Sakashita, Hiroto*; Ono, Ayako; Yoshida, Hiroyuki

no journal, , 

Understanding the boiling heat transfer characteristics in debris beds is indispensable to assess the coolability of molten debris at severe accident. However, the trigger mechanism of the critical heat flux on the bottom heated debris beds has not been fully elucidated. This study performed the visualization measurements using a transparent heating surface on which small particles are accumulated. The boiling behaviors were observed via a total reflection technique, and effects of particle size on dryout and rewetting process of the heating surface were examined.

Oral presentation

Estimation of the in-depth debris status of Fukushima Unit-2 and Unit-3 with multi-physics modeling, 9; Fukushima-Daiichi Unit-3 plant data analysis focusing on estimated fuel debris relocation to the pedestal

Sato, Ikken; Yamaji, Akifumi*; Furuya, Masahiro*; Oishi, Yuji*; Li, X.*; Madokoro, Hiroshi; Fukai, Hirofumi*

no journal, , 

no abstracts in English

Oral presentation

Estimation of the in-depth debris status of Fukushima Unit-2 and Unit-3 with multi-physics modeling, 12; Evaluation of debris-relocation history to the pedestal in Fukushima-Daiichi Units 2 and 3

Sato, Ikken; Yamaji, Akifumi*; Furuya, Masahiro*; Oishi, Yuji*; Li, X.*; Madokoro, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

Development of fluid-rigid strongly coupled particle method for the estimation of the relocation behavior of damaged in-core structures

Fukuda, Takanari; Yoshida, Hiroyuki

no journal, , 

The presenters have developed a new fluid-rigid coupled particle method for the estimation of the relocation of in-core structures mechanically interacting with fluid phases existing in a reactor. Amid a severe accident, there might exist relatively large in-core structure, the scale of which is comparable to that of the maximum spatial scale of the fluid (e.g. scale of containment vessel). Such a calculation configuration can result in numerical instability with the conventional fluid-rigid weakly coupled methods. Hence, we have derived fluid-rigid strongly coupled time-development equations on the basis of Hamilton's least action principle and developed a new particle method for solving those equations numerically.

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