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Ogawa, Masuro*
JAEA-Technology 2019-010, 22 Pages, 2019/07
JAEA-Technology-2019-010.pdf:1.5MB
Transition phenomena from laminar to turbulent flow are roughly classified into three categories. Circular pipe flow of the third category is linearly stable against any small disturbance, despite that flow actually transitions and transitional flow exhibits intermittency. These are among major challenges that are yet to be resolved in fluid dynamics. Thus, author proposes hypothesis as follows; "Flow in a circular pipe transitions from laminar flow because of vortices released from separation bubble forming in vicinity of inlet of pipe, and transitional flow becomes intermittent because vortex-shedding is intermittent." Present hypothesis can easily explain why linear stability theory has not been able to predict transition in circular pipe flow, why circular pipe flow actually transitions, why transitional flow actually exhibits intermittency even due to small disturbance, and why numerical analysis has not been able to predict intermittency of transitional flow in circular pipe.
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
Fujimoto, Nozomu; Tachibana, Yukio; Saikusa, Akio*; Shinozaki, Masayuki; Isozaki, Minoru; Iyoku, Tatsuo
Nuclear Engineering and Design, 233(1-3), p.273 - 281, 2004/10
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)From a viewpoint of heat leakage, there were two incidents during HTTR power-rise-tests. One was a temperature rise of the primary upper shielding, and the other was a temperature rise of the core support plate. Causes of the both incidents were small amount of helium flow in structures. For the temperature rise of the primary upper shielding, countermeasures to reduce the small amount of helium flow, enhancement of heat release and installation of thermal insulator were taken. For the temperature rise of the core support plate, temperature evaluations were carried out again considering the small amount of helium flow and design temperature of the core support plate was revised. By these countermeasures, the both temperatures were kept below their limits.
Kameo, Yutaka; Nakashima, Mikio; Hirabayashi, Takakuni*
Nuclear Technology, 144(1), p.76 - 82, 2003/10
Times Cited Count：1 Percentile：10.87(Nuclear Science & Technology)Erosion behavior of stainless and carbon steel pipes by a swirling air flow containing alumina or cast-iron grit abrasive was investigated. Effects of operating conditions such as an abrasive concentration and a flow rate of air-stream on erosion ability was examined. Erosion depths of the test pipes were approximately proportional to the concentration of abrasives and exponent of flow rate of air-stream. The experimental results indicated that the present method could keep satisfactory erosion ability of abrasives even for a large size pipe. The present method was successfully applied to 
Co-contaminated specimens sampled from a pipe of the water clean-up system of the Japan Power Demonstration Reactor.
Takase, Kazuyuki; Akimoto, Hajime
Applied Electromagnetics in Materials, p.177 - 178, 2001/00
no abstracts in English
Tachibana, Yukio; Hontani, Koji*; Takeda, Takeshi; Saikusa, Akio; Shinozaki, Masayuki; Isozaki, Minoru; Iyoku, Tatsuo; Kunitomi, Kazuhiko
Nuclear Engineering and Design, 201(2-3), p.227 - 238, 2000/10
Times Cited Count：3 Percentile：26.4(Nuclear Science & Technology)no abstracts in English
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
*; Kunugi, Tomoaki
Nihon Kikai Gakkai Rombunshu, B, 64(617), p.65 - 70, 1998/01
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
Kunitomi, Kazuhiko; Tachibana, Yukio; *; Nakano, Masaaki*; Saikusa, Akio; Takeda, Takeshi; Iyoku, Tatsuo; ; Sawahata, Hiroaki; Okubo, Minoru; et al.
JAERI-Tech 97-040, 91 Pages, 1997/09
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
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
Nakamura, Hideo; Kukita, Yutaka; *
Journal of Nuclear Science and Technology, 32(9), p.868 - 879, 1995/09
Times Cited Count：4 Percentile：43.23(Nuclear Science & Technology)no abstracts in English
Nakamura, Hideo; Kukita, Yutaka; *
Journal of Nuclear Science and Technology, 32(7), p.641 - 652, 1995/07
Times Cited Count：5 Percentile：49.46(Nuclear Science & Technology)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
Takeda, Takeshi; Kunitomi, Kazuhiko; Baba, Osamu
Proc. 6th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics,Vol. 1; NURETH6, 0, p.1483 - 1488, 1994/00
no abstracts in English
*; *; *; *; Fumizawa, Motoo
The 4th Triennial Int. Symp. on Fluid Control,Fluid Measurement,and Visualization; FLUCOME 94, 0, p.691 - 695, 1994/00
no abstracts in English
