Two-fluid model can simulate two-phase flow by computational cost less than detailed two-phase flow simulation method such as interface tracking method. Therefore, two-fluid model is useful for thermal hydraulic analysis in large-scale domain such as rod bundles in nuclear reactors. However, two-fluid model include a lot of constitutive equations. Then, applicability of these constitutive equations must be verified by use of experimental results, and the two-fluid model has problems that the results of analyses depend on accuracy of constitutive equations. To solve these problems, we have been developing an advanced two-fluid model. In this model, an interface tracking method is combined with the two-fluid model to predict large interface structure behavior accurately. Interfacial structures larger than a computational cells, such as large droplets and bubbles, are calculated using the interface tracking method. And droplets and bubbles that are smaller than cells are simulated by the two-fluid model. Constitutive equations to evaluate the effects of small bubbles or droplets on two-phase flow are required in the advanced two-fluid model as same as a conventional two-fluid model. However, dependency of small bubbles and droplets on two-phase flow characteristic is relatively small, and the experimental results to verify the equations are not required much. In this study, we modified the advanced two-fluid model to improve the stability of the numerical simulation and reduce the computational time. Moreover, the modified model was incorporated to the 3-dimensional two-fluid model code ACE-3D. In this paper, we describe the outline of this model and the modification performed in this study. Moreover, the numerical results of two-phase flow in various flow conditions.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4932-3
PROCEEDINGS PAPER
Development of Advanced Two-Fluid Model for Boiling Two-Phase Flow in Rod Bundles
Hiroyuki Yoshida,
Hiroyuki Yoshida
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Hideaki Hosoi,
Hideaki Hosoi
University of Tsukuba, Tsukuba, Ibaraki, Japan
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Takayuki Suzuki,
Takayuki Suzuki
Yamato System Engineer, Hitachi, Ibaraki, Japan
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Kazuyuki Takase
Kazuyuki Takase
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Hiroyuki Yoshida
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Hideaki Hosoi
University of Tsukuba, Tsukuba, Ibaraki, Japan
Takayuki Suzuki
Yamato System Engineer, Hitachi, Ibaraki, Japan
Kazuyuki Takase
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Paper No:
ICONE18-30219, pp. 1193-1200; 8 pages
Published Online:
April 8, 2011
Citation
Yoshida, H, Hosoi, H, Suzuki, T, & Takase, K. "Development of Advanced Two-Fluid Model for Boiling Two-Phase Flow in Rod Bundles." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B. Xi’an, China. May 17–21, 2010. pp. 1193-1200. ASME. https://doi.org/10.1115/ICONE18-30219
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