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Journal Articles

Prediction of heater surface temperature change at subcooled flow boiling DNB

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.

Journal Articles

Ultrahigh CHF prediction for subcooled flow boiling based on homogenous nucleation mechanism

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.

Journal Articles

Study of critical heat flux mechanism in flow boiling using bubble crowding model; Application to CHF in short tube and in tube with twisted tape under non-uniform heating conditions

Kinoshita, Hidetaka; Nariai, Hideki*; Inasaka, Fujio*

JSME International Journal, Series B, 44(1), p.81 - 89, 2001/01

no abstracts in English

Journal Articles

Critical heat flux in subcooled water flow of one-side-heated screw tubes

J.Boscary*; Araki, Masanori; ; ; Akiba, Masato

Fusion Technology, 35(3), p.289 - 296, 1999/05

no abstracts in English

Journal Articles

Critical heat flux at high velocity channel flow with high subcooling

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

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:28 Percentile:87.65(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Dimensional analysis of critical heat flux in subcooled water flow under one-side heating conditions for fusion application

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

JAEA Reports

Analysis of the JAERI critical heat flux data base for fusion application

J.Boscary*; Araki, Masanori; Akiba, Masato

JAERI-Research 97-053, 50 Pages, 1997/08

JAERI-Research-97-053.pdf:1.71MB

no abstracts in English

JAEA Reports

Critical heat flux database of JAERI for high heat flux components for fusion application

J.Boscary*; Araki, Masanori; Akiba, Masato

JAERI-Data/Code 97-033, 12 Pages, 1997/08

JAERI-Data-Code-97-033.pdf:0.51MB

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

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:54 Percentile:92.65(Thermodynamics)

no abstracts in English

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

JAEA Reports

Effects of high temperature ECC injection on small and large break BWR LOCA simulation tests in ROSA-III program; RUNs 940 and 941

Suzuki, Mitsuhiro; Nakamura, Hideo; Kumamaru, Hiroshige; Anoda, Yoshinari; Yonomoto, Taisuke; Murata, Hideo; Tasaka, Kanji

JAERI-M 90-051, 256 Pages, 1990/03

JAERI-M-90-051.pdf:6.41MB

no abstracts in English

Journal Articles

Summary of RETRAN calculations on LaSalle 2 neutron flux oscillation event performed at JAERI

Araya, Fumimasa; Hirano, Masashi; ; Matsumoto, Kiyoshi; Yokobayashi, Masao; Kosaka, Atsuo

CSNI-178, p.370 - 384, 1990/00

no abstracts in English

JAEA Reports

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:36 Percentile:94.27(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A Study of subcooled film-boiling heat transfer under reactivity initiated accident conditions in light water reactor

; ;

Nuclear Science and Engineering, 88, p.331 - 341, 1984/00

 Times Cited Count:17 Percentile:82.92(Nuclear Science & Technology)

no abstracts in English

30 (Records 1-20 displayed on this page)