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Journal Articles

Conductance of a long rectangular channel; Pressure dependence

Ogiwara, Norio; Hikichi, Yusuke*; Kamiya, Junichiro; Kinsho, Michikazu; Yoshida, Hajime*; Arai, Kenta*

Journal of the Vacuum Society of Japan, 60(12), p.475 - 480, 2017/12

Journal Articles

Helium-air counter flow in rectangular channels

Fumizawa, Motoo; Tanaka, Gaku*; Zhao, H.*; Hishida, Makoto*; Shiina, Yasuaki

Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(4), p.313 - 322, 2004/12

This paper deals with a computer simulation of a helium-air counter flow in a rectangular channel. The inclination angle is varied from 0$$^{circ}$$(horizontal) to 90$$^{circ}$$(vertical). Velocity profiles and concentration profiles are calculated with a computer program VSOP sub-module. Following main features of the counter flow are discussed. (1) Time required to establish a quasi-steady state counter flow. (2) The relationship between the inclination angle and the flow patterns of the counter flow (3) The developing process of velocity profiles and concentration profiles (4) The relationship between the inclination angle of the channel and the velocity profiles of upwards flow and the downwards flow (5) The relationship between the concentration profile and the inclination angle (6) The relationship between the net in-flow rate and the inclination angle We compared the computed velocity profile and the net in-flow rate with experimental data. A good agreement is obtained between the calculation and the experiment.

Journal Articles

Numerical analysis of a water-vapor two-phase film flow in a narrow coolant channel with a three-dimensional rectangular rib

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

JSME International Journal, Series B, 47(2), p.323 - 331, 2004/05

no abstracts in English

Journal Articles

Experimental study on the critical heat flux (CHF) in a rectangular channel with micro ribs for a solid target and proton beam window design

Kaminaga, Masanori; Kinoshita, Hidetaka; Haga, Katsuhiro; Hino, Ryutaro; Sudo, Yukio

Proceedings of International Workshop on Current Status and Future Directions in Boiling Heat Transfer and Two-Phase Flow, p.135 - 141, 2000/00

no abstracts in English

Journal Articles

Improvement of critical heat flux correlation for research reactors using plate-type fuel

Kaminaga, Masanori; Yamamoto, Kazuyoshi; Sudo, Yukio

Journal of Nuclear Science and Technology, 35(12), p.943 - 951, 1998/12

 Times Cited Count:13 Percentile:72.4(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Critical heat flux of forced flow boiling in a narrow one-side heated rectangular flow channel

L.Zheng*; Iguchi, Tadashi; Kureta, Masatoshi; Akimoto, Hajime

JAERI-Research 97-054, 85 Pages, 1997/08

JAERI-Research-97-054.pdf:2.18MB

no abstracts in English

Journal Articles

Improvement of CHF correlations for research reactors using plate-type fuels

Kaminaga, Masanori; Yamamoto, Kazuyoshi; Sudo, Yukio

Proceedings of 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), Vo.3, p.1815 - 1822, 1997/00

In research reactors, plate-type fuel elements are generally adopted so as to produce high power densities and are cooled by a downward flow. A core flow reversal from a steady-state forced downward flow to an upward flow due to natural convection should occur during operational transients such as "Loss of the primary coolant flow". Therefore, in the thermal hydraulic design of research reactors, critical heat flux (CHF) under a counter-current flow limitation (CCFL) or a flooding condition are important to determine safety margins of fuel against CHF during a core flow reversal. The authors have proposed a CHF correlation scheme for the thermal hydraulic design of research reactors, based on CHF experiments for both upward and downward flows including CCFL condition. When the CHF correlation scheme was proposed, a subcooling effect for CHF correlation under CCFL condition had not been considered because of a conservative evaluation and a lack of enough CHF data to determine the subcooling effect on CHF. A too conservative evaluation is not appropriate for the design of research reactors because of construction costs etc. Also, conservativeness of the design must be determined precisely. In this study, therefore, the subcooling effect on CHF under the CCFL conditions in vertical rectangular channels heated from both sides were investigated quantitatively based on CHF experimental results obtained under uniform and nonuniform heat flux condition. As a result, it was made clear that CHF in this region increase linearly with an increase of the channel inlet subcooling and a new CHF correlation including the effect of channel inlet subcooling was proposed.

Journal Articles

Heat transfer characteristics of rectangular coolant channels with various aspect ratios in the plasma-facing components under fully developed MHD laminar flow

Takase, Kazuyuki; M.Z.Hasan*

16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), 2, p.1538 - 1541, 1995/00

no abstracts in English

Journal Articles

Experimental study of differences in CHF between upflow and downflow in vertical rectangular channels; Effect of subcooling

Kaminaga, Masanori; Sudo, Yukio

Nihon Kikai Gakkai Rombunshu, B, 58(553), p.2799 - 2804, 1993/09

no abstracts in English

Journal Articles

A New CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors

Sudo, Yukio; Kaminaga, Masanori

J. Heat Transfer, 115, p.426 - 434, 1993/05

 Times Cited Count:34 Percentile:87.24(Thermodynamics)

no abstracts in English

JAEA Reports

Experimental study on DNB heat flux of plate-type fuel in pressurized condition

; ; Kaminaga, Masanori; Ishitsuka, Etsuo; ; Sudo, Yukio; Saito, Minoru;

JAERI-M 92-097, 61 Pages, 1992/07

JAERI-M-92-097.pdf:2.42MB

no abstracts in English

Journal Articles

Experimental study of the critical heat flux in a narrow vertical rectangular channel

Kaminaga, Masanori; Sudo, Yukio; Murayama, Yoji; *

Heat Transfer-Jpn. Res., 20(1), p.72 - 85, 1991/03

no abstracts in English

Journal Articles

Journal Articles

A New CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors

Kaminaga, Masanori; Sudo, Yukio

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.73 - 79, 1991/00

no abstracts in English

Journal Articles

Heat transfer characteristics in narrow vertical rectangular channels heated from both sides

Sudo, Yukio; *; Kaminaga, Masanori

JSME Int. J., Ser. II, 33(4), p.743 - 748, 1990/00

no abstracts in English

Journal Articles

Experimental study of incipient nucleate boiling in narrow vertical rectangular channel simulating subchannel of upgraded JRR-3

Sudo, Yukio; *; ; Kaminaga, Masanori

Journal of Nuclear Science and Technology, 23(1), p.73 - 82, 1985/00

 Times Cited Count:31 Percentile:92.89(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental study of differences in DNB heat flux between upflow and downflow in a vertical channel

Sudo, Yukio; *; ; Kaminaga, Masanori;

Journal of Nuclear Science and Technology, 22(8), p.604 - 618, 1985/00

 Times Cited Count:50 Percentile:97.37(Nuclear Science & Technology)

no abstracts in English

18 (Records 1-18 displayed on this page)
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