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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.
Nakamura, Hideo; Kukita, Yutaka;
Journal of Nuclear Science and Technology, 32(7), p.641 - 652, 1995/07
Times Cited Count：9 Percentile：65.15(Nuclear Science & Technology)no abstracts in English
G.R.Noghrehkar*; Kawaji, Masahiro*; A.M.C.Chan*; Nakamura, Hideo; Kukita, Yutaka
J. Fluids Eng., 117, p.1 - 9, 1995/03
no abstracts in English
Nakamura, Hideo; Murata, Hideo; Ito, Hideo; Anoda, Yoshinari; Kumamaru, Hiroshige; Kukita, Yutaka
ANS Proc. 1991 National Heat Transfer Conf., Vol. 5, p.175 - 180, 1991/00
no abstracts in English
