The three-dimensional two-fluid model analysis code ACE-3D is developed in Japan Atomic Energy Agency for the thermal design procedure on two-phase flow thermal-hydraulics of light water-cooled reactors. In order to perform thermal hydraulic analysis of SCWR, ACE-3D is enhanced to supercritical pressure region. As a result, it is confirmed that transient change in subcritical and supercritical pressure region can be simulated smoothly using ACE-3D, that ACE-3D can predict the results of the past heat transfer experiment in the supercritical pressure condition, and that introduction of thermal conductivity effect of the wall restrains fluctuation of wall.
- Nuclear Engineering Division
Numerical Analysis of Heat Transfer Test of Supercritical Water in a Tube Using the Three-Dimensional Two-Fluid Model Code
Misawa, T, Yoshida, H, Tamai, H, & Takase, K. "Numerical Analysis of Heat Transfer Test of Supercritical Water in a Tube Using the Three-Dimensional Two-Fluid Model Code." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Instrumentation and Controls. Orlando, Florida, USA. May 11–15, 2008. pp. 713-720. ASME. https://doi.org/10.1115/ICONE16-48690
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