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Journal Articles

Large-scale simulations on bubbly flow dynamics in a fuel channel with the earth simulator

Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*

Hai Pafomansu Komputingu To Keisan Kagaku Shimpojium (HPCS 2005) Rombunshu, P. 16, 2005/01

no abstracts in English

Journal Articles

Numerical analysis on liquid-gas two-phase flow behavior in fusion reactors

Takase, Kazuyuki; Ose, Yasuo*; Suzuki, Takayuki*; Akimoto, Hajime

Nihon Kikai Gakkai Yamanashi Koenkai Koen Rombunshu (000-4), p.173 - 174, 2000/00

no abstracts in English

Journal Articles

A Numerical method for an adiabatic two-fluid model based on the modified SOLA method; 1st report, Numerical solution method

Hirano, Masashi; *

Nihon Kikai Gakkai Rombunshu, B, 58(556), p.3613 - 3618, 1992/12

no abstracts in English

Journal Articles

The Effect of the virtual mass term on the stability of the two-fluid model against perturbations

Watanabe, Tadashi; Kukita, Yutaka

Nucl. Eng. Des., 135, p.327 - 340, 1992/00

 Times Cited Count:12 Percentile:72.75(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

MINI-TRAC code; A Driver program for assessment of constitutive equations for two-fluid model

; Abe, Yutaka; Onuki, Akira; Murao, Yoshio

JAERI-M 91-086, 470 Pages, 1991/05

JAERI-M-91-086.pdf:7.54MB

no abstracts in English

Journal Articles

Estimation of shear stress in counter current annular flow

Abe, Yutaka; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 28(3), p.208 - 217, 1991/03

no abstracts in English

Journal Articles

Analysis of interfacial and wall friction factors of counter-current flow in vertical pipe

Abe, Yutaka; ; Murao, Yoshio

6th Proc. of Nuclear Thermal Hydraulics, p.401 - 408, 1990/11

no abstracts in English

Journal Articles

Analysis of interfacial and wall friction factors of countercurrent flow in vertical pipes

Abe, Yutaka; ; Murao, Yoshio

Transactions of the American Nuclear Society, 62, p.719 - 720, 1990/11

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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