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JAEA Reports

Flow separation at inlet causing transition and intermittency in circular pipe flow

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.

Journal Articles

Stability of a silica membrane prepared by CVD using $$gamma$$- and $$alpha$$-alumina tube as the support tube in the Hi-H$$_{2}$$O gaseous mixture

Hwang, G.*; Kim, J.*; Choi, H.*; Onuki, Kaoru

Journal of Membrane Science, 215(1-2), p.293 - 302, 2003/04

 Times Cited Count:16 Percentile:56.48(Engineering, Chemical)

no abstracts in English

JAEA Reports

Carbon-14 in neutron-irradiated graphite for graphite-moderated reactors (Joint research)

Fujii, Kimio; Matsuo, Hideto*

JAERI-Review 2002-034, 44 Pages, 2002/12

JAERI-Review-2002-034.pdf:3.34MB

Graphite material is used as a moderator and reflector of graphite-moderated gas-cooled reactors such as the Tokai Nuclear Power Station of Japan Atomic Power Company. For the decommissioning of those reactors, it is very important to obtain the density of carbon-14 in the graphite of which half-time is very long, and the development of the reduction technique for density of carbon-14 is one of the main technical issues as well. The reactor ceased the commercial operation on March 1998, and is in the process of the decommissioning. Technical developement on nuclear graphite disposal is one of the main issues, and it is pointed out that carbon-14 density is an impotant factor for the treatment on the disposal of the nuclear graphite. In order to resolve the problem, literatures survey was carried out for describing the status of technical development on resolving the problem. This report describes the outline of the literatures surveyed and the list of the related literatures is attached as well.

Journal Articles

A Steady-state simulation model of gas separation system by hollow-filament type membrane module

Iwai, Yasunori; Yamanishi, Toshihiko; Nishi, Masataka

Journal of Nuclear Science and Technology, 36(1), p.95 - 104, 1999/01

 Times Cited Count:12 Percentile:66.24(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Hydrogen separation in H$$_{2}$$-H$$_{2}$$O-HI gaseous mixture using the silica membrance prepared by chemical vapor deposition

Hwang, G.*; Onuki, Kaoru; Shimizu, Saburo; *

J. Membr. Sci., 162(1-2), p.83 - 90, 1999/00

 Times Cited Count:65 Percentile:90.18(Engineering, Chemical)

no abstracts in English

Journal Articles

Numerical evaluation of interfacial area concentration using the immiscible lattice gas

Watanabe, Tadashi; Ebihara, Kenishi

Nucl. Eng. Des., 188(1), p.111 - 121, 1999/00

 Times Cited Count:6 Percentile:45.66(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Studies on hydrogen separation membrane for IS process; Membrane preparation with porous $$alpha$$-alumina tube

Hwang, G.*; Onuki, Kaoru; Shimizu, Saburo

JAERI-Research 98-002, 8 Pages, 1998/01

JAERI-Research-98-002.pdf:0.53MB

no abstracts in English

Journal Articles

Development of methane conversion improvement method by recycling of residual Methane for steam reforming as a part of R&D of HTGR-hydrogen production system

Inagaki, Yoshiyuki; Haga, Katsuhiro; ; Sekita, Kenji; *; Hino, Ryutaro

Nihon Genshiryoku Gakkai-Shi, 40(1), p.59 - 64, 1998/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Study on methane separation from steam reforming product gas with polyimide membrane

*; Inagaki, Yoshiyuki; ; Sekita, Kenji; Haga, Katsuhiro; Hino, Ryutaro

JAERI-Research 97-076, 33 Pages, 1997/10

JAERI-Research-97-076.pdf:1.3MB

no abstracts in English

Journal Articles

Development of a computer-controlled on-line rapid ion-exchange separation system

Tsukada, Kazuaki*; Otsuki, Tsutomu*; Sueki, Keisuke*; *; *; *; Nakahara, Hiromichi*; Shinohara, Nobuo; ; Usuda, Shigekazu; et al.

Radiochimica Acta, 51(2), p.77 - 84, 1990/00

no abstracts in English

Journal Articles

Preparation of gas chromatographic column for separation of hydrogen isotopes and its application to analysis in commercially available tritium gas

Saeki, Masakatsu; Hirabayashi, Takakuni; ; *; Tachikawa, Enzo

Journal of Nuclear Science and Technology, 20(9), p.762 - 768, 1983/00

 Times Cited Count:11 Percentile:75.53(Nuclear Science & Technology)

no abstracts in English

Journal Articles

In-line gas chromatograph for analysis of UF$$_{6}$$ and/or F$$_{2}$$

;

Journal of Nuclear Science and Technology, 14(2), p.147 - 152, 1977/02

 Times Cited Count:1

no abstracts in English

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