Thermal-hydraulic Analysis of MONJU Upper Plenum under 40％ Rated Power Operational Condition
Plant dynamics analysis codes and multi-dimensional thermal-hydraulic analysis codes are required for design and safety assessment of future FBRs. In this study, we calculated the thermal-hydraulics of the upper plenum of Monju by a detailed analysis model using commercial FVM code, FrontFlow/Red. The present analysis model has high resolution meshes representing all structures which are Flow Guide Tubes, Thermocouple plug, Fuel Handling Machine, etc. And the computational model consists of approximately 13.7 million cells. In these meshes, however, the surface of the upper instrument structure (UIS) was modeled as adiabatic since it was estimated not to affect the thermal-hydraulics in the upper plenum in the present steady state conditions. The fully-implicit scheme of SIMPLE method was applied to all equations. The first order upwind and the second order central difference scheme were respectively applied to the advection and diffusion terms. The RANS approach to turbulence modeling (RNG k-ε model) was also applied to the present calculations. These calculated results indicated that the structures installed in the plenum except for UIS did not affect largely to the temperature and velocity distributions, the flow characteristics by the present model resulted in similar tendencies with porous media approaches applied to the upper core structure region and the measured temperatures could predict the core outlet temperatures with only a few degree errors in the present conditions.
Monju upper plenum Monju system start-up test Thermal-hydraulics Numerical simulation RNG k-? model Finite volume method
Kei HONDA Hiroaki OHIRA Masutake SOTSU Shinji YOSHIKAWA
Japan Atomic Energy Agency 1 Shiraki, Tsuruga, Fukui, 919-1279 Japan
国际会议
上海
英文
438-449
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）