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Journal Articles

Preliminary numerical investigation of turbulence behavior in a spallation target

Takase, Kazuyuki; Kitamura, Tatsuaki*; Kume, Etsuo; Ichimiya, Koichi*; Komada, Ichiro*

Nihon Kikai Gakkai Kanto Shibu Yamanashi Koenkai (2003) Koen Rombunshu, No.030-4, p.77 - 78, 2003/00

no abstracts in English

Journal Articles

Three-dimensional numerical simulations of heat transfer in an annular fuel channel with periodic spacer ribs under a fully developed turbulent flow

Takase, Kazuyuki

Nuclear Technology, 118(2), p.175 - 185, 1997/05

 Times Cited Count:5 Percentile:42.84(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental results of heat transfer coefficients and friction factors in a 2D/3D rib-roughened annulus

Takase, Kazuyuki

Experimental Thermal and Fluid Science, 13(2), p.142 - 151, 1996/08

 Times Cited Count:8 Percentile:49.95(Thermodynamics)

no abstracts in English

Journal Articles

Helium-air exchange flow through annular and round tubes

Fumizawa, Motoo; Hishida, Makoto

Nuclear Technology, 109, p.123 - 131, 1995/01

 Times Cited Count:1 Percentile:17.53(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Numerical simulation of turbulent heat transfer in an annular fuel channel augmented by spacer ribs

Takase, Kazuyuki; Akino, Norio

Proc. of the 30th Intersociety Energy Conversion Engineering Conf., 0, P. 95_169, 1995/00

no abstracts in English

Journal Articles

Numerical prediction of turbulent heat transfer characteristics of a fuel rod with very small square ribs for high temperature gas-cooled reactors

Takase, Kazuyuki; Akino, Norio

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.535 - 540, 1995/00

no abstracts in English

Journal Articles

Analytical study on characteristics of falling water limitation in countercurrent two-phase flow in vertical annular channels

Sudo, Yukio

Nihon Kikai Gakkai Rombunshu, B, 60(576), p.2888 - 2894, 1994/08

no abstracts in English

JAEA Reports

Study on improvement of constitutive equations and numerical methods for three-fluid model(3)

The Japan Society of Multiphase Flow*; Special Committee for Examination of Thermohydraulic Analysis Code based on Three-Fluid Model*

PNC TJ9565 94-001, 530 Pages, 1994/03

PNC-TJ9565-94-001.pdf:12.01MB

The purpose of the present study is to improve a numerical prediction method for multiphase flows based on the three-fluid model. Conducted were (1)improvement of a numerical method, (2)survey and examination on constitutive equations for mass transfer terms in annular-mist flow, (3) survey and verification of constitutive equations for momentum transfer terms, (4)collection of experimental database on steam-water and air-water annular-mist flows and numerical analyses of the database to verify the prediction method, (5)extensivc survey on expelimental techniques for annular-mist flow and (6)examination on the governing equations. As a result, the following conclusions were obtained: (a)multi-fluid modeling for all flow regimes were completed, (b)numerical stability of the three-fluid model was darified, (c)stability-enhanced solution method was developed, (d)ill-posedness of the equation system was revealed, (c)a physically-rational and well-posed multi-fluid model was proposed for dispersed flows, (f)systematic survcy and evaluation of constitutive equations for entrainment and deposition were conducted and summarized, (g)a theoretical method for evaluating film thickness, interfacial shear stress and wall shear stress was presented, and (h)it was confirmed that FIDAS-1DS can accurately predict critical heat fluxes under atmosphelic pressure, and that it can givc qualitatively good predictions concerning film thickness, droplet flow rate and so forth of the air-water annular-mist flow.

JAEA Reports

Study on improvement of constitutive equations and numerical methods for three-fluid model

The Japan Society of Multiphase Flow*; Special Committee for Examination of Thermohydraulic Analysis Code based on Three-Fluid Model*

PNC TJ9565 93-001, 265 Pages, 1993/04

PNC-TJ9565-93-001.pdf:6.09MB

The purpose of the present study is to improve a numerical method for multiphase flows based on the three-fluid model. Conducted were (1) improvement of a numcrical scheme, (2)examination on the validity of governing equations, (3)survey and verification of available constitutive equations, (4)development of theoretical constitutive equations and (5) numerical analyses of experimental database on steam-water and air-water annular-mist flows. As a result, the following conclusions were obtained: (a)multi-fluid modelling for all flow regimes were completed, (b)numerical stability of the three-fluid model was clarified, (c)stability-enhanced solution method was developed, (d)a physically-rational and well-posed multi-fluid model was proposed for dispersed flows, (e)systematic survey and evaluation of available constitutive equations for entrainment was conducted and summarized, (f)a theoretical method for the evaluation of film thickness and interfacial shear stress was presented, and(g)it was confirmed that FIDAS-1DS can accurately predict critical heat fluxes under atmospheric pressure, and that it can give qualitatively good predictions conserning film thickness, droplet flow rate and so forth of the air-water annular-mist flow.

Journal Articles

Experimental study of helium-air exchange flow through an annular tube

Fumizawa, Motoo; Hishida, Makoto

Proc. of the 2nd ASME/JSME Nuclear Engineering, p.85 - 92, 1993/00

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

Experimental and theoretical investigations on heat transfer of strongly heated turbulent gas flow in an annular duct

Fujii, Sadao*; Akino, Norio; Hishida, Makoto; *; Sanokawa, Konomo

JSME Int. J., Ser. 2, 34(3), p.348 - 354, 1991/00

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

Journal Articles

Hydraulics of a coolant flow through a control rod channel in the very high temperature gas cooled reactor

Ogawa, Masuro; Akino, Norio; ; ; ; Emori, Kouichi; Ouchi, Mitsuo; ;

Journal of Nuclear Science and Technology, 24(1), p.75 - 83, 1987/01

 Times Cited Count:1 Percentile:19.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Laminar-turbulent transition in coneentric annuli

;

Nihon Genshiryoku Gakkai-Shi, 28(6), p.524 - 526, 1986/00

 Times Cited Count:0 Percentile:0.35(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Effect of flow obstacle on droplet size distribution in vertical annular air-water flow

Shibamoto, Yasuteru; Yonomoto, Taisuke

no journal, , 

no abstracts in English

Oral presentation

Effect of pressure gradient along axial direction of vortex-core on gas entrainment flow rate

Torikawa, Tomoaki*; Odaira, Naoya*; Ito, Daisuke*; Ito, Kei*; Saito, Yasushi*; Matsushita, Kentaro; Ezure, Toshiki; Tanaka, Masaaki

no journal, , 

On free surface of a sodium cooled fast reactor, gas entrainment can be caused by free surface vortices, which may result in disturbance in core power. It is important to develop an evaluation model to predict accurately entrained gas flow rate. In this study, the effect of pressure gradient in vortex axis direction on the gas entrainment flow rate is investigated in a simple gas experimental apparatus, in which upper and lower tanks are connected by a suction pipe. As a result, it was observed that there are two flow regime: swirling annular flow regime shows the tendency that only the gas entrainment flow rate increases with almost constant pressure gradient, then, when liquid plug is induced by the development of free surface disturbance, the gas entrainment flow rate increases as the pressure gradient increases. In addition, it was confirmed that the transformation of those two flow regimes is advanced by higher liquid level in the upper tank.

22 (Records 1-20 displayed on this page)