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Kojima, Yuya*; Murakawa, Hideki*; Sugimoto, Katsumi*; Kondo, Teppei*; Abe, Yuta; Aizawa, Kosuke
Proceedings of 13th International Symposium on Measurement Techniques for Multiphase Flows (ISMTMF 2025) (Internet), 5 Pages, 2025/10
Muhammad, I.; Nagatake, Taku; Uesawa, Shinichiro; Ono, Ayako
Proceedings of 21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-21) (Internet), 12 Pages, 2025/08
This research aims to validate ACE-3D using data from a two-phase flow experiment. For this purpose, a two-phase flow experiment was conducted in a four-by-four unheated fuel assembly. In the experiment, the time-averaged void fraction distribution was measured using a wire mesh sensor system under high temperatures and high-pressure conditions. The experimental results were analyzed, and the data were visualized to understand better the behavior and characteristics of the two-phase flow in the fuel assembly. A two-phase flow data set is being developed, covering a wide range of experimental conditions, including higher-pressure regions, which can be used for validating thermal-hydraulic codes. Finally, the ACE-3D code was applied to the two-phase flow experiment. The calculation results were then compared to the experimental ones, and the issues were identified for improving ACE-3D in future simulations.
Sun, Haomin; Hibiki, Takashi*
International Journal of Heat and Mass Transfer, 237, p.126445_1 - 126445_14, 2025/02
Times Cited Count：4 Percentile：36.61(Thermodynamics)
4 simulated fuel bundle for validation of thermal-hydraulics simulation codesOno, Ayako; Nagatake, Taku; Uesawa, Shinichiro; Shibata, Mitsuhiko; Yoshida, Hiroyuki
Proceedings of Specialist Workshop on Advanced Instrumentation and Measurement Techniques for Nuclear Reactor Thermal-Hydraulics and Severe Accidents (SWINTH-2024) (USB Flash Drive), 7 Pages, 2024/06
Japan Atomic Energy Agency (JAEA) is developing a neutronics/thermal-hydraulics coupling simulation code for light-water reactors. Thermal-hydraulic simulation codes applied to the coupling code are expected to calculate the void fraction distribution in a rod bundle under operational conditions, which are necessary for neutron transport simulation, and need to be validated using void fraction distribution data in a rod bundle under high-temperature and high-pressure conditions. Therefore, we have conducted the measurement of the instantaneous void distribution in the 4 4 simulated fuel bundle using a developed wire mesh sensor, which is installed in the pressurized two-phase flow experimental loop of JAEA to obtain the data for code validation.
Sun, Haomin; Kunugi, Tomoaki*; Yokomine, Takehiko*; Shen, X.*; Hibiki, Takashi*
International Journal of Heat and Mass Transfer, 211, p.124214_1 - 124214_17, 2023/09
Times Cited Count：7 Percentile：44.98(Thermodynamics)Onuki, Akira; Shibata, Mitsuhiko; Tamai, Hidesada; Akimoto, Hajime; Yamauchi, Toyoaki*; Mizokami, Shinya*
Nihon Konsoryu Gakkai Nenkai Koenkai 2003 Koen Rombunshu, p.35 - 36, 2003/07
Analytical evaluation of maximum critical power by so-called subchannnel code is indispensable for design of reduced moderation water reactor. In this study, two-phase flow distribution in a tight-lattice rod bundle is investigated using 19-rod bundle experimental rig and subchannnel analysis code NASCA. The flow distribution was measured under so-called churn flow regime and the predictive capability of NASCA was assessed. NASCA can predict the flow distribution qualitatively depending on local pressure drop. Quantitative prediction is also reasonable for liquid phase but the gas phase distribution was underestimated. Void-drift model has a dominant contribution and we should improve the model for the tight-lattice rod bundle.
Yamamoto, Tetsuya*; Matsumura, Akira*; Yamamoto, Kazuyoshi; Kumada, Hiroaki; Shibata, Yasushi*; Nose, Tadao*
Physics in Medicine & Biology, 47(14), p.2387 - 2396, 2002/07
Times Cited Count：30 Percentile：60.80(Engineering, Biomedical)The aim of this study was to determine the in-phantom thermal distribution derived from neutron beams for intraoperative boron neutron capture therapy (IOBNCT). Gold activation wires arranged in a cylindrical water phantom with (void-in phantom) or without (standard phantom) a cylinder styrene form placed inside were irradiated by using the epithermal beam (ENB) and the mixed thermal-epithermal beam (TNB-1) at the JRR-4. The thermal neutron distribution derived from both the ENB and TNB-1 was significantly improved in the void-in-phantom, and a double high dose area was formed lateral to the void. The flattened distribution in the circumference of the void was observed with the combination of ENB and the void-in-phantom. The measurement data suggest that the ENB may provide a clinical advantage in the form of an enhanced and flattened dose delivery to the marginal tissue in which residual and/or microscopically infiltrating tumor.
Onuki, Akira;
Int. J. Multiph. Flow, 22(6), p.1143 - 1154, 1996/00
Times Cited Count：45 Percentile：83.90(Mechanics)no abstracts in English
; ; Fujii, Terushige*; ; ; ; Matsubayashi, Masahito; Tsuruno, Akira
Nuclear Instruments and Methods in Physics Research A, 377, p.153 - 155, 1996/00
Times Cited Count：8 Percentile：57.84(Instruments & Instrumentation)no abstracts in English
Hibiki, Takashi*; Mishima, Kaichiro*; Tsuruno, Akira
Proc. of 2nd Int. Topical Meeting on Neutron Radiography System Design and Characterization, 0, p.316 - 323, 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
; Kumamaru, Hiroshige; Murata, Hideo; Anoda, Yoshinari; Kukita, Yutaka
JAERI-M 93-200, 56 Pages, 1993/10
no abstracts in English
; ; ;
JAERI-M 87-059, 57 Pages, 1987/05
no abstracts in English
Arigane, Kenji
JAERI-M 87-063, 133 Pages, 1987/04
no abstracts in English
; Tasaka, Kanji; ; ; ; ; ; Koizumi, Yasuo
JAERI-M 86-038, 275 Pages, 1986/03
no abstracts in English
;
Journal of Nuclear Science and Technology, 15(12), p.886 - 898, 1978/00
Times Cited Count：3no abstracts in English
Tomita, Hirobumi*; Maeshima, Takahiro*; Okada, Makoto*; Tate, Naofumi*; Aoki, Kunitomo*; Hiramatsu, Natsuki*; Ono, Koji*; Uesawa, Shinichiro; Yoshida, Hiroyuki
no journal, ,
Quantitative validation of instantaneous and local gas-liquid interface information is essential if detailed two-phase flow simulations are to replace or complement large-scale mockup experiments. Wire-mesh sensors (WMSs) are widely used for validation, but their spatial resolution is limited by the wire-crossing pitch, hindering characterization of fine interfacial structures. We are therefore developing a framework that combines WMS measurements, detailed two-phase flow and electrostatic simulations, and deep learning to infer highly accurate and high-resolution void-fraction distributions. In this presentation, pix2pix was used to estimate high-resolution void-fraction distributions from WMS measurements. The AI model of the pix2pix was trained using gas-liquid interface information and WMS measurements. The trained model generated images similar to CFD-derived two-phase flow data.
