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Journal Articles

Experimental study on local interfacial parameters in upward air-water bubbly flow in a vertical 6$$times$$6 rod bundle

Han, X.*; Shen, X.*; Yamamoto, Toshihiro*; Nakajima, Ken*; Sun, Haomin; Hibiki, Takashi*

International Journal of Heat and Mass Transfer, 144, p.118696_1 - 118696_19, 2019/12

 Times Cited Count:4 Percentile:49.6(Thermodynamics)

Journal Articles

Local gas-liquid two-phase flow characteristics in rod bundle geometry

Xiao, Y.*; Shen, X.*; Miwa, Shuichiro*; Sun, Haomin; Hibiki, Takashi*

Konsoryu Shimpojiumu 2018 Koen Rombunshu (Internet), 2 Pages, 2018/08

In order to develop constitutive equations of two-fluid model in rod bundle flow channels, experiments of adiabatic air-water upward two-phase flow in 6$$times$$6 rod bundle flow channel were performed. Local flow parameters such as void fraction, interfacial area concentration (IAC) and so on were measured by a double-sensor optical probe. The area-averaged void fraction and IAC data were compared with the predictions from a drift-flux model and an IAC correlation.

Journal Articles

Some characteristics of gas-liquid two-phase flow in vertical large-diameter channels

Shen, X.*; Schlegel, J. P.*; Hibiki, Takashi*; Nakamura, Hideo

Nuclear Engineering and Design, 333, p.87 - 98, 2018/07

 Times Cited Count:5 Percentile:30.29(Nuclear Science & Technology)

Journal Articles

Measurement of void fraction distribution in steam-water two-phase flow in a 4$$times$$4 bundle at 2 MPa

Liu, W.; Nagatake, Taku; Shibata, Mitsuhiko; Takase, Kazuyuki; Yoshida, Hiroyuki

Transactions of the American Nuclear Society, 114, p.875 - 878, 2016/06

To contribute to the clarification of the Fukushima Daiichi Accident, JAEA is working on getting instantaneous void fraction distribution data in steam water two - phase flow in rod bundle geometry under high pressure, high temperature condition, with using Wire Mesh Sensor (WMS) developed at JAEA for high pressure, high temperature condition, focusing on the low flow rate condition after the reactor scram. This paper reports the experimental results for the measured void fraction distribution in steam vapor two-phase flow in a 4 $$times$$ 4 bundle under 1.6 MPa (202 $$^{circ}$$C), 2.1 MPa (215 $$^{circ}$$C) and 2.6 MPa (226 $$^{circ}$$C) conditions. The data is expected to be used in the validation of the detailed two-phase flow codes TPFIT and ACE3D developed at JAEA. The time and space averaged void fraction data is also expected being used in the validation of the drift flux models implemented in the two fluids codes, such as TRACE code.

Journal Articles

("3D"+"2D+Time") visualization of vapor/water in the reactor observed by neutron beam

Kureta, Masatoshi

VizJournal, (11), 5 Pages, 2004/06

This paper explains the neutron radiography thermal-hydraulic measurement technique, especialy visualization technique, which was developed at Japan Atomic Energry Research Institute. Observation of large and fine-mesh data obtained by the new measurement technology is important from a research point of view. We developed the advanced visualization software which puts into practice effective observation by using new visualization methods, and we made the vizualization of phenomena possible by using VR and/or animation displays etc. by this system. Especially in this paper, the visualization techniques which were used in a prize-winning work of the "Visual Sience Festa 2003" by NIKKEI SCIENCE as easy to read for a general reader as possible by using many figures and movies.

Journal Articles

Experimental study on thermal-hydraulics and neutronics coupling effect on flow instability in a heated channel with THYNC facility

Iguchi, Tadashi; Shibamoto, Yasuteru; Asaka, Hideaki; Nakamura, Hideo

Proceedings of 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), 16 Pages, 2003/10

Thermal-hydraulic and neutronic dynamics are always interrelated in BWR core. This is called thermal-hydraulic and neutronic (T/N) coupling. Channel stability experiments with T/N coupling under non-nuclear condition are very limited. This is mainly due to the difficulties in the real-time simulation of neutron dynamics and in the fast-response void fraction measurement under high-pressure and temperature conditions. Authors have developed techniques to solve the above difficulties, and have succeeded in experimentally simulating T/N coupling under non-nuclear conditions with the THYNC facility. Using THYNC facility, T/N coupling effect on channel stability was investigated. Experiments were performed under Pressure=2-7MPa, Subcooling=10-40K, and Mass flux=270-660kg/m$$^{2}$$s. THYNC results indicated T/N coupling lowered the channel stability threshold. The reduction of channel stability threshold due to T/N coupling was small within 10% at 7MPa in the present THYNC experiment, although the experimental condition was set to be more severe than that supposed in a reactor.

Journal Articles

Unit sphere concept for macroscopic triggering of large-scale vapor explosions

Maruyama, Yu*; Moriyama, Kiyofumi; Nakamura, Hideo

Journal of Nuclear Science and Technology, 39(8), p.854 - 864, 2002/08

 Times Cited Count:4 Percentile:30.46(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Flow resistance of orifices and spacers of BWR thermal-hydraulic and neutronic coupling loop

Iguchi, Tadashi; Asaka, Hideaki; Nakamura, Hideo

JAERI-Research 2002-006, 152 Pages, 2002/03

JAERI-Research-2002-006.pdf:5.52MB

no abstracts in English

Journal Articles

Multi-dimensional thermal-hydraulic analysis for horizontal type PCCS

Arai, Kenji*; Kurita, Tomohisa*; Nakamaru, Mikihide*; Fujiki, Yasunobu*; Nakamura, Hideo; Kondo, Masaya; Obata, Hiroyuki*; Shimada, Rumi*; Yamaguchi, Ken*

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 7 Pages, 2002/00

no abstracts in English

JAEA Reports

Development of quick-response area-averaged void fraction meter; Application to BWR condition

Iguchi, Tadashi; Watanabe, Hironori; Kimura, Mamoru*; Anoda, Yoshinari

JAERI-Research 2001-032, 111 Pages, 2001/05

JAERI-Research-2001-032.pdf:4.14MB

no abstracts in English

Journal Articles

Visualization and measurements of liquid phase velocity and void fraction of gas-liquid metal two-phase flow by using neutron radiography

Saito, Yasushi*; Hibiki, Takashi*; Mishima, Kaichiro*; Tobita, Y.*; Suzuki, Toru*; Matsubayashi, Masahito

Proceedings of 9th International Symposium on Flow Visualization, p.391_1 - 391_10, 2000/00

no abstracts in English

Journal Articles

Numerical investigation of heat transfer enhancement phenomenon during the reflood phase of PWR-LOCA

Onuki, Akira; Akimoto, Hajime

Journal of Nuclear Science and Technology, 36(11), p.1021 - 1029, 1999/11

 Times Cited Count:1 Percentile:13.53(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Numerical prediction on transport behavior of cooling water injected into vacuum vessels of fusion reactors

Takase, Kazuyuki; Ose, Yasuo*; Akimoto, Hajime

Nihon Kikai Gakkai Dai-12-Kai Keisan Rikigaku Koenkai Koen Rombunshu, p.395 - 396, 1999/00

no abstracts in English

Journal Articles

The Review of the application of neutron radiography to thermal hydraulic research

Mishima, Kaichiro*; Hibiki, Takashi*; Saito, Yasushi*; Nakamura, Hideo; Matsubayashi, Masahito

Nuclear Instruments and Methods in Physics Research A, 424(1), p.66 - 72, 1999/00

 Times Cited Count:18 Percentile:77.12(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Visualization and measurement of gas-liquid metal two-phase flow with large density difference using thermal neutrons as microscopic probes

Mishima, Kaichiro*; Hibiki, Takashi*; Saito, Y.*; Nishihara, Hideaki*; Tobita, Y.*; *; Matsubayashi, Masahito

Nuclear Instruments and Methods in Physics Research A, 424(1), p.229 - 234, 1999/00

 Times Cited Count:29 Percentile:88.32(Instruments & Instrumentation)

no abstracts in English

Journal Articles

A Feasibility study on core cooling of pressurized heavy water moderated reactor with tight lattice core

Onuki, Akira; Okubo, Tsutomu; Akimoto, Hajime

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

Journal Articles

Assessment of REFLA/TRAC code for heat transfer enhancement phenomena during the reflood phase of PWR-LOCA

Onuki, Akira;

Proc. of 5th Int. Topical Meeting on Nuclear Thermal Hydraulics,Operations and Safety, 00(00), p.1 - 6, 1997/04

no abstracts in English

Journal Articles

Analysis of residual heat removal process due to natural circulation in a water pool of a passive safety light water reactor

Onuki, Akira; Araya, Fumimasa;

PHOENICS J. Comput. Fluid Dyn. Its Appl., 9(3), p.326 - 342, 1996/09

no abstracts in English

Journal Articles

Measurement of dynamic behavior of void fraction in tube-banks of a simulated fluidized-bed by neutron radiography

*; *; *; *; Matsubayashi, Masahito; Tsuruno, Akira

Fifth World Conf. on Neutron Radiography, 0, p.610 - 616, 1996/00

no abstracts in English

Journal Articles

Three-dimensional void fraction measurement of two-phase flow in a rod bundle by neutron radiography

*; *; Fujii, Terushige*; *; Matsubayashi, Masahito; Tsuruno, Akira

Fifth World Conf. on Neutron Radiography, 0, p.118 - 125, 1996/00

no abstracts in English

62 (Records 1-20 displayed on this page)