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Journal Articles

Flow regime and void fraction predictions in vertical rod bundle flow channels

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

International Journal of Heat and Mass Transfer, 178, p.121637_1 - 121637_24, 2021/10

 Times Cited Count:0 Percentile:0.01(Thermodynamics)

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

Experimental study on interfacial area transport of two-phase bubbly flow in a vertical large-diameter square duct

Shen, X.*; Sun, Haomin; Deng, B.*; Hibiki, Takashi*; Nakamura, Hideo

International Journal of Heat and Fluid Flow, 67(Part A), p.168 - 184, 2017/10

 Times Cited Count:11 Percentile:61.97(Thermodynamics)

An experimental study on upward bubbly air-water flows in a vertical large-diameter square duct have been performed by mainly using four-sensor probes. Local measurements of interfacial area concentration (IAC), void fraction, 3D bubble velocity vector and bubble diameter at 3 axial positions were conducted. Although the interfacial area transport equation (IATE) and its bubble coalescence and breakup models have already played an important role in predicting the IAC in general two-phase flow fields, they are mainly developed based on the two-phase flow experimental data taken in round pipes or small diameter channels. To confirm their usability in large-diameter square duct, this study has evaluated the 1D one-group IATE with its 6 sets of bubble coalescence and breakup models with the presently-obtained database. It was found the relative error between the best prediction and the database was 25%.

Journal Articles

Axial flow characteristics of bubbly flow in a vertical large-diameter square duct

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.

Journal Articles

Multi-dimensional gas-liquid two-phase flow in vertical large-diameter channels

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

Journal Articles

Gas-liquid bubbly flow structure in a vertical large-diameter square duct

Shen, X.*; Sun, Haomin; Deng, B.*; Hibiki, Takashi*; Nakamura, Hideo

Progress in Nuclear Energy, 89, p.140 - 158, 2016/05

 Times Cited Count:13 Percentile:86.01(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.

Journal Articles

Local measurements of 3-D bubble velocity vector, bubble diameter and interfacial area concentration in a vertical large diameter square duct

Shen, X.*; Hibiki, Takashi*; Sun, Haomin; Nakamura, Hideo

Proceedings of 9th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-9) (CD-ROM), 10 Pages, 2014/11

no abstracts in English

Journal Articles

An Improved fast neutron radiography quantitative measurement method

Matsubayashi, Masahito; Hibiki, Takashi*; Mishima, Kaichiro*; Yoshii, Koji*; Okamoto, Koji*

Nuclear Instruments and Methods in Physics Research A, 533(3), p.481 - 490, 2004/11

 Times Cited Count:3 Percentile:25.71(Instruments & Instrumentation)

The validity of a fast neutron radiography quantification method, the $$Sigma$$-scaling method, which was originally proposed for thermal neutron radiography was examined with Monte Carlo calculations and experiments conducted at the YAYOI fast neutron source reactor. Water and copper were selected as comparative samples for a thermal neutron radiography case and a dense object, respectively. Although different characteristics on effective macroscopic cross-sections were implied by the simulation, the $$Sigma$$-scaled experimental results with the fission neutron spectrum cross-sections were well fitted to the measurements for both the water and copper samples. This indicates that the $$Sigma$$-scaling method could be successfully adopted for quantitative measurements in fast neutron radiography.

Journal Articles

Development of a fast neutron radiography converter using wavelength-shifting fibers

Matsubayashi, Masahito; Hibiki, Takashi*; Mishima, Kaichiro*; Yoshii, Koji*; Okamoto, Koji*

Nuclear Instruments and Methods in Physics Research A, 510(3), p.325 - 333, 2003/09

 Times Cited Count:9 Percentile:55.15(Instruments & Instrumentation)

A fluorescent converter for fast neutron radiography (FNR) comprising a scintillator and hydrogen-rich resin has been developed and applied to electronic imaging. The rate of the reaction between fast neutrons and the converter is increased by thickening the converter, but its opaqueness attenuates emitted light photons before they reach its surface. To improve the luminosity of a fluorescent converter for FNR, a novel type of converter was designed in which wavelength-shifting fibers were adopted to transport radiated light to the observation end face. The performance of the converter was compared with that of a polypropylene-based fluorescent converter in an experiment conducted at the fast-neutron-source reactor YAYOI in the University of Tokyo.

Journal Articles

Study on point of net vapor generation by neutron radiography in subcooled boiling flow along narrow rectangular channels with short heated length

Kureta, Masatoshi; Hibiki, Takashi*; Mishima, Kaichiro*; Akimoto, Hajime

International Journal of Heat and Mass Transfer, 46(7), p.1171 - 1181, 2003/03

 Times Cited Count:9 Percentile:40.01(Thermodynamics)

no abstracts in English

Journal Articles

Void fraction measurement in subcooled-boiling flow using high-frame-rate neutron radiography

Kureta, Masatoshi; Akimoto, Hajime; Hibiki, Takashi*; Mishima, Kaichiro*

Nuclear Technology, 136(2), p.241 - 254, 2001/11

 Times Cited Count:10 Percentile:60.79(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Measurement of boiling flow by high-frame-rate neutron radiography, 2; Point of net vapor generation of flow-boiling in rectangular channels with short heated length

Kureta, Masatoshi; Hibiki, Takashi*; Mishima, Kaichiro*; Akimoto, Hajime

Nihon Kikai Gakkai Rombunshu, B, 67(661), p.2295 - 2303, 2001/09

no abstracts in English

Journal Articles

Preliminary examination of the applicability of imaging plates to fast neutron radiography

Matsubayashi, Masahito; Hibiki, Takashi*; Mishima, Kaichiro*; Yoshii, Koji*; Okamoto, Koji*

Nuclear Instruments and Methods in Physics Research A, 463(1-2), p.324 - 330, 2001/05

 Times Cited Count:16 Percentile:74.78(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Measurement of boiling flow by high-frame-rate neutron radiography, 1; Error estimation and void fraction measurement

Kureta, Masatoshi; Hibiki, Takashi*; Mishima, Kaichiro*; Akimoto, Hajime

Nihon Kikai Gakkai Rombunshu, B, 67(653), p.179 - 188, 2001/01

no abstracts in English

Journal Articles

Present status on the development of a high-frame-rate neutron radiography system in JRR-3M

Matsubayashi, Masahito; Hibiki, Takashi*; Mishima, Kaichiro*

Nondestructive Testing and Evaluation, 16(2-6), p.267 - 275, 2001/01

no abstracts in English

Journal Articles

Design and characteristics of the JRR-3M thermal neutron radiography facility and its imaging systems

Matsubayashi, Masahito; Kobayashi, Hisao*; Hibiki, Takashi*; Mishima, Kaichiro*

Nuclear Technology, 132(2), p.309 - 324, 2000/11

 Times Cited Count:24 Percentile:82.34(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Fundamental Research of Two-Phase Flows with High Liquid/Gas Density Ratios

Mishima, Kaichiro*; Hibiki, Takashi*; Saito, Yasushi*; Tobita, Yoshiharu; Konishi, Kensuke; Suzuki, Toru

JNC TY9400 2000-018, 72 Pages, 2000/07

JNC-TY9400-2000-018.pdf:3.92MB

no abstracts in English

Journal Articles

Development of fast neutron radiography imaging technique using imaging plate

Matsubayashi, Masahito; Yoshii, Koji*; Hibiki, Takashi*; Mishima, Kaichiro*

Kashika Joho Gakkai-Shi, 20(Suppl.1), p.325 - 328, 2000/07

no abstracts in English

41 (Records 1-20 displayed on this page)