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Liu, W.; Podowski, M. Z.*
Nihon Kikai Gakkai Netsu Kogaku Konfuarensu 2015 Koen Rombunshu (CD-ROM), 2 Pages, 2015/10
This paper gives prediction to the transient heat transfer at Departure of Nucleate Boiling (DNB) point for subcooled flow boiling. The prediction is carried out by solving the heat conduction equations in cylindrical coordinates with convective boundary condition, which changes with the change of the heat transfer mode on the heated surface. DNB is assumed to happen at the complete dryout of liquid sublayer trapped between the heated wall and an elongated vapor clot, during the passing time of the vapor clot. Important parameters including initial thickness of the liquid sublayer, vapor clot length, vapor clot velocity and void fraction etc., are calculated from the Liu - Nariai model. The initial heater surface temperature is derived from the Jens-Lottes correlation. The transient changes of liquid sublayer thickness, surface temperature at DNB are reported. No obvious temperature jumping is observed at DNB. To predict temperate excursion at Critical Heat Flux (CHF), more simulations to the transient boiling and film boiling processes are needed.
Liu, W.; Nariai, Hideki*
Journal of Heat Transfer, 127(2), p.149 - 158, 2005/02
Times Cited Count:17 Percentile:53.93(Thermodynamics)Homogeneous nucleation, although being discounted as a mechanism for vapor formation for water in most conditions, is found being possible to occur under some extreme conditions in subcooled flow boiling. In this paper, firstly, the existence of the homogeneous nucleation governed condition is indicated. Followed, a criterion is developed to judge a given working condition is the conventional one or the homogeneous nucleation governed one. With the criterion, subcooled flow boiling data are categorized and typical homogeneous nucleation governed datasets are listed. CHF triggering mechanism for the homogeneous nucleation governed condition is proposed and verified. Parametric trends of the CHF, in terms of mass flux, pressure, inlet subcooling, channel diameter and the ratio of heated length to diameter are also studied.
Kinoshita, Hidetaka; Nariai, Hideki*; Inasaka, Fujio*
JSME International Journal, Series B, 44(1), p.81 - 89, 2001/01
no abstracts in English
J.Boscary*; Araki, Masanori; ; ; Akiba, Masato
Fusion Technology, 35(3), p.289 - 296, 1999/05
no abstracts in English
Sudo, Yukio; Kaminaga, Masanori
Nucl. Eng. Des., 187, p.215 - 227, 1999/00
Times Cited Count:8 Percentile:49.29(Nuclear Science & Technology)no abstracts in English
Kaminaga, Masanori; Yamamoto, Kazuyoshi; Sudo, Yukio
Journal of Nuclear Science and Technology, 35(12), p.943 - 951, 1998/12
Times Cited Count:28 Percentile:87.65(Nuclear Science & Technology)no abstracts in English
J.Boscary*; Araki, Masanori; J.Schlosser*; Akiba, Masato; F.Escorbiac*
Fusion Engineering and Design, 43(2), p.147 - 171, 1998/00
Times Cited Count:46 Percentile:94.14(Nuclear Science & Technology)no abstracts in English
J.Boscary*; Araki, Masanori; Akiba, Masato
JAERI-Research 97-053, 50 Pages, 1997/08
no abstracts in English
J.Boscary*; Araki, Masanori; Akiba, Masato
JAERI-Data/Code 97-033, 12 Pages, 1997/08
no abstracts in English
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.
Kaminaga, Masanori; Sudo, Yukio
Nihon Kikai Gakkai Rombunshu, B, 58(553), p.2799 - 2804, 1993/09
no abstracts in English
Sudo, Yukio; Kaminaga, Masanori
J. Heat Transfer, 115, p.426 - 434, 1993/05
Times Cited Count:54 Percentile:92.65(Thermodynamics)no abstracts in English
Tanzawa, Sadamitsu; Ishijima, Kiyomi
JAERI-M 91-183, 31 Pages, 1991/11
no abstracts in English
Onuki, Akira; Iwamura, Takamichi; Abe, Yutaka; ; Murao, Yoshio
JAERI-M 90-236, 76 Pages, 1991/01
no abstracts in English
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
Suzuki, Mitsuhiro; Nakamura, Hideo; Kumamaru, Hiroshige; Anoda, Yoshinari; Yonomoto, Taisuke; Murata, Hideo; Tasaka, Kanji
JAERI-M 90-051, 256 Pages, 1990/03
no abstracts in English
Araya, Fumimasa; Hirano, Masashi; ; Matsumoto, Kiyoshi; Yokobayashi, Masao; Kosaka, Atsuo
CSNI-178, p.370 - 384, 1990/00
no abstracts in English
; Tasaka, Kanji; ; ; ; ; ; Koizumi, Yasuo
JAERI-M 86-038, 275 Pages, 1986/03
no abstracts in English
Sudo, Yukio; ; ; Kaminaga, Masanori
Journal of Nuclear Science and Technology, 23(1), p.73 - 82, 1985/00
Times Cited Count:36 Percentile:94.27(Nuclear Science & Technology)no abstracts in English
; ;
Nuclear Science and Engineering, 88, p.331 - 341, 1984/00
Times Cited Count:17 Percentile:82.92(Nuclear Science & Technology)no abstracts in English