東京工業大学 · 工学
教授の研究室は、高温・高速な冷却媒体を用いる原子炉の熱・力学的挙動を解明することを柱としています。特に、液体金属冷却炉における低流量下の熱伝達特性や自然循環の安定性、ならびに炉の内在的安全性を評価するための熱・力学・核計算の連成解析に注力しています。実験的・数値的アプローチを併用し、次世代炉の設計・安全評価に貢献する研究が進められています。
Figures are computed from collected data and may differ slightly.
The aims of the study are to correlate instability data in ATR (Advanced Thermal Reactor) channels using dimensionless parameters, and validate the ATRECS-II code. Various kinds of experiments were conducted with the 14 MW Heat Transfer Loop (HTL) and the 6MW ATR Safety Experimental Loop (SEL). Experimental ranges of parameters are listed below: — Natural circulation or forced circulation with channel flow rate of 0.5~3.6kg/s Pressure ranging 0.2~7 MPa — Subcooling ranging 5~70°C — Outlet pipe o
The present paper describes the liquid metal heat transfer in heat exchangers under low flow rate conditions. Measured data from some experiments indicate that heat transfer coefficients of liquid metals at very low Péclet number are much lower than what are predicted by the well-known empirical relations. The cause of this phenomenon was not fully understood for many years. In the present study, one countercurrent-type heat exchanger is analyzed using three, separated countercurrent heat exchan
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