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Shen, X.*; Sun, Haomin; Deng, B.*; Hibiki, Takashi*; Nakamura, Hideo
Proceedings of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) (USB Flash Drive), 14 Pages, 2017/09
An experimental study on the upward bubbly air-water flows in a vertical large-diameter square duct have been performed by using four-sensor probes. The four-sensor probe were applied in the local measurements at 3 axial positions along the flow direction to obtain interfacial area concentration, 3-D bubble velocity vector and bubble diameter. The obtained void fraction, interfacial area concentration, 3-D bubble velocity vector and bubble diameter provided valuable insight into the flow structure and will serve as a valuable database to develop the mechanistic models for interfacial area transport equation sources and sinks.
Shen, X.*; Schlegel, J. P.*; Hibiki, Takashi*; Nakamura, Hideo
Proceedings of 2017 Japan-US Seminar on Two-Phase Flow Dynamics (JUS 2017), 6 Pages, 2017/06
Shen, X.*; Sun, Haomin; Deng, B.*; Hibiki, Takashi*; Nakamura, Hideo
Progress in Nuclear Energy, 89, p.140 - 158, 2016/05
Times Cited Count：23 Percentile：89.61(Nuclear Science & Technology)An experimental study was performed on the local structure of upward air-water two-phase flow in a vertical large diameter square duct by using a four-sensor probe. The four-sensor probe method classifying spherical and non-spherical bubbles was applied as a key measurement way to obtain local parameters such as 3-D bubble velocity vector, bubble diameter and interfacial area concentration. Both the local void fraction and interfacial area concentration indicated radial core-peak and wall-peak distributions at low and high liquid flow rates respectively. The 2 components of the bubble velocity vector in the cross-section revealed that there exists a rotating secondary flow in the octant symmetric triangular area and the magnitude of the rotating secondary flow increases with the liquid flow rate. Some of constitutive correlations of drift-flux model and interfacial area concentration are reviewed to study their predictabilities against the present data.
Shibamoto, Yasuteru; Sun, Haomin; Yonomoto, Taisuke
Proceedings of 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10) (USB Flash Drive), 10 Pages, 2014/12
Ezato, Koichiro; Dairaku, Masayuki; Taniguchi, Masaki; Sato, Kazuyoshi; Suzuki, Satoshi; Akiba, Masato; Ibbott, C.*; Tivey, R.*
Fusion Science and Technology, 46(4), p.530 - 540, 2004/12
Times Cited Count：14 Percentile：66.01(Nuclear Science & Technology)The first fabrication and heating test of a large-scale CFC monoblock divertor mock-up using annular flow concept have been performed to demonstrate its manufacturability and thermo-mechanical performance. Prior to the fabrication of the mock-up, brazed joint tests between the CFC monoblock and the CuCrZr tube have been carried out to find the suitable heat treatment mitigating loss of the high mechanical strength of the CuCrZr material. Basic mechanical examination on CuCrZr undergoing the brazing heat treatment and FEM analyses are also performed to support the design of the mock-up. High heat flux tests on the large-scale divertor mock-up have been performed in an ion beam facility. The mock-up has successfully withstood more than 1,000 thermal cycles of 
for 15 s and 3,000 cycles more than 
for 15 s, which simulates the heat load condition of the ITER divertor. No degradation of the thermal performance of the mock-up has been observed throughout the thermal cycle test.
Onuki, Akira; Akimoto, Hajime
International Journal of Multiphase Flow, 26(3), p.367 - 386, 2000/03
Times Cited Count：131 Percentile：96(Mechanics)no abstracts in English
Onuki, Akira; *; Akimoto, Hajime
Konsoryu Shimpojiumu '98 Koen Rombunshu, p.221 - 222, 1998/00
no abstracts in English
Onuki, Akira; Akimoto, Hajime
Proc. of 1st European-Japanese Two-phase Flow Group Meeting, p.1 - 8, 1998/00
no abstracts in English
Onuki, Akira; Kamo, Hideki*; Akimoto, Hajime
Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 3, p.1670 - 1676, 1997/00
no abstracts in English
; Kumamaru, Hiroshige; Murata, Hideo; Kukita, Yutaka
JAERI-Research 96-038, 55 Pages, 1996/07
JAERI-Research-96-038.pdf:1.63MB
no abstracts in English
Onuki, Akira;
Int. J. Multiph. Flow, 22(6), p.1143 - 1154, 1996/00
Times Cited Count：41 Percentile：83.45(Mechanics)no abstracts in English
Onuki, Akira; Kamo, Hideki*;
Proceedings of Japan-US Seminar on Two-Phase Flow Dynamics, 0, p.75 - 82, 1996/00
no abstracts in English
Onuki, Akira;
Proc. of ASME Heat Transfer and Fluids Engineering Divisions (HTD-Vol. 321,FED-Vol. 233), 0, p.473 - 478, 1995/00
no abstracts in English
Onuki, Akira; ; Sudo, Yukio
Proc. of the 2nd Int. Conf. on Multiphase Flow 95-Kyoto, 0, p.FT1.17 - FT1.23, 1995/00
no abstracts in English
*; Murata, Mikio
Earozoru Kenkyu, 7(3), p.230 - 239, 1992/00
no abstracts in English
Sudo, Yukio; *; Kaminaga, Masanori
JSME Int. J., Ser. 2, 34(2), p.169 - 174, 1991/00
no abstracts in English
; Onuki, Akira; Abe, Yutaka; Murao, Yoshio
Proc. of the Int. Conf. on Multiphase Flows 91-TSUKUBA, p.369 - 372, 1991/00
no abstracts in English
Sudo, Yukio; *; ; ; Kaminaga, Masanori
JAERI-M 85-126, 95 Pages, 1985/09
no abstracts in English
Sudo, Yukio; *; ; Kaminaga, Masanori
Journal of Nuclear Science and Technology, 23(1), p.73 - 82, 1985/00
Times Cited Count：34 Percentile：93.68(Nuclear Science & Technology)no abstracts in English
Sudo, Yukio; *; ; Kaminaga, Masanori;
Journal of Nuclear Science and Technology, 22(8), p.604 - 618, 1985/00
Times Cited Count：59 Percentile：97.81(Nuclear Science & Technology)no abstracts in English
