K-1338 T字形合流管内の流れに関する研究 : 原子力プラントでの低周波流動振動に関する数値解析(S15-12 管内のはく離)(S15 噴流・はく離流れの計測と制御)

概要

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Fluid-structure thermal interaction phenomena characterized by stationary random temperature fluctuations, namely thermal striping are observed in the downstream region such as a T-junction piping system of liquid metal fast reactors (LMFRs). Therefore the piping wall located in the downstream region must be protected against the stationary random thermal process which might induced high-cycle fatigue. This paper describes thermohydraulic characteristics of velocity and temperature fluctuations at the downstream region based on numerical results with a computer code system which consists of three thermohydraulics computer programs AQUA, DINUS-3 and THEMIS and of three thermomechanical computer programs BEMSET, FINAS and CANIS, for an actual thermal fatigue event occurred at a French LMFR Phenix.
一般社団法人日本機械学会の論文
2001-08-22