2019 Fall Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 304-1 Thermal Hydraulics, Energy Conversion, Energy Transfer, Energy Storage

[2F01-04] Gas-Liquid Two-Phase Flow

Thu. Sep 12, 2019 9:30 AM - 10:35 AM Room F (Common Education Bildg. 2F C21)

Chair:Tomio Okawa(UEC)

10:00 AM - 10:15 AM

[2F03] Numerical Simulation of Bubble Behavior in PWR Rod Bundle by Interface Tracking Method

*Hiroyuki Yoshida1, Ayako Ono1, Masaaki Okano2, Yasushi Makino2 (1. JAEA, 2. NDC)

Keywords:PWR fuel assembly, Bubble behavior, Numerical simulation, TPFIT

To reduce dependency of large scale test, that require huge cost and time, on thermal-hydraulic design of nuclear reactor, we have been developing a two-phase flow simulation method based on the interface tracking method. This method applied to various two-phase flow conditions, however, two-phase flow under operating conditions of PWR was not performed. In this study, to check the applicability for the operating conditions of PWR, the developed simulation method is applied to bubbly flow in PWR fuel bundle. In this simulation, single-phase flow in PWR fuel bundle was performed by using the STAR-CCM+, and this result was used as boundary conditions of two-phase flow. And the effects of a grid spacer are considered by using simulation results.