In Japan Atomic Energy Agency (JAEA), the three-dimensional two-fluid model analysis code considering the supercritical pressure water based on ACE-3D (Advanced Code for Evaluation of 3-Dimensional two-phase flow) has been developed to establish the thermal-hydraulics design by numerical analytical approach for the Super Critical Water Reactor (SCWR). In this paper, in order to evaluate the prediction accuracy of ACE-3D for the heat transfer-characteristics at the pseudo critical point, a numerical analysis of the supercritical water using ACE-3D based on the three dimensional two-fluid model has been conducted for simulating the experiments in a heated tube with both upward and downward flow. For the turbulence model in this analysis, both the standard k-ε model and the low-Reynolds number type k-ε model which uses the Launder-Sharma model were examined to investigate the influence of the turbulence model on the heat transfer-characteristics near the heated wall near the pseudo critical point. As a result, it was found that the numerical results of wall temperature using the low-Reynolds number k-ε model for upward flow in a heated tube were in good agreement with experimental data compared with that of using the standard k-ε model.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5581-2
PROCEEDINGS PAPER
Numerical Analysis on Heat Transfer-Characteristics of Supercritical Pressure Water in a Heated Tube Based on Three Dimensional Two-Fluid Model
Yasuo Ose,
Yasuo Ose
Yamato System Engineer, Hitachi, Ibaraki, Japan
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Takayuki Suzuki,
Takayuki Suzuki
Yamato System Engineer, Hitachi, Ibaraki, Japan
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Takeharu Misawa,
Takeharu Misawa
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Hiroyuki Yoshida,
Hiroyuki Yoshida
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Kazuyuki Takase
Kazuyuki Takase
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Yasuo Ose
Yamato System Engineer, Hitachi, Ibaraki, Japan
Takayuki Suzuki
Yamato System Engineer, Hitachi, Ibaraki, Japan
Takeharu Misawa
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Hiroyuki Yoshida
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Kazuyuki Takase
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Paper No:
ICONE21-16435, V004T09A089; 8 pages
Published Online:
February 7, 2014
Citation
Ose, Y, Suzuki, T, Misawa, T, Yoshida, H, & Takase, K. "Numerical Analysis on Heat Transfer-Characteristics of Supercritical Pressure Water in a Heated Tube Based on Three Dimensional Two-Fluid Model." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 4: Thermal Hydraulics. Chengdu, China. July 29–August 2, 2013. V004T09A089. ASME. https://doi.org/10.1115/ICONE21-16435
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