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Journal Articles

Analytical tool development for coarse break-up of a molten jet in a deep water pool

Moriyama, Kiyofumi; Nakamura, Hideo; Maruyama, Yu*

Nuclear Engineering and Design, 236(19-21), p.2010 - 2025, 2006/10

 Times Cited Count:23 Percentile:81.96(Nuclear Science & Technology)

A computer code JASMINE-pre was developed for the prediction of premixing conditions of fuel-coolant interactions and the debris bed formation behavior relevant to severe accidents of light water reactors. JASMINE-pre consists of three melt component models: melt jet, melt particles and melt pool, coupled with a two-phase flow model derived from the ACE-3D code developed at JAERI. Simulations of the FARO corium quenching experiments with a saturated water pool and with a subcooled water pool were performed with JASMINE-pre and ${tt pmjet}$. JASMINE-pre reproduced the pressurization and fragmentation behaviors observed in the experiments with a reasonable accuracy. The results by pmjet showed qualitatively the same trend with JASMINE-pre in the fragmentation behavior.

JAEA Reports

Vectorization, parallelization and porting of nuclear codes on the VPP500 system (Vectorization); Progress report fiscal 1997

*; *; *; *; *; Ogasawara, Shinobu*; Adachi, Masaaki*; *; Kume, Etsuo

JAERI-Data/Code 99-026, 91 Pages, 1999/05

JAERI-Data-Code-99-026.pdf:2.9MB

no abstracts in English

Oral presentation

Applicability on two-phase flow simulation codes for Venturi scrubber

Horiguchi, Naoki; Yoshida, Hiroyuki; Nakao, Yasuhiro*; Kanagawa, Tetsuya*; Kaneko, Akiko*; Abe, Yutaka*

no journal, , 

no abstracts in English

Oral presentation

Numerical simulation of two-phase flow in porous media based on two-fluid model

Yoshida, Hiroyuki; Horiguchi, Naoki

no journal, , 

In a severe accident in nuclear reactors, fuel debris is assumed to migrate and exist in porous media due to the solidification of molten fuel and other materials. Therefore, evaluating the thermal-hydraulic behavior in the porous media is necessary to understand the transition of severe accidents in nuclear reactors. In the severe accident of nuclear reactors, it is considered that various kinds of flow behaviors appear in the porous media, and it is essential to evaluate the two-phase flow behavior in the porous media to study the fuel debris temperature rise and remelting. Therefore, we are developing a multiphase CFD numerical simulation method based on the three-dimensional two-fluid model. This report describes the outline of the multiphase CFD numerical simulation method based on a three-dimensional two-fluid model and the analytical results.

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