Tokyo Institute of Technology · Engineering
Professor Hiroyasu Mochizuki's research lab specializes in advanced thermal-hydraulics and nuclear reactor safety, with a focus on natural circulation flows, heat transfer phenomena in liquid-metal-cooled systems, and transient behavior in advanced nuclear reactors. The lab conducts experimental and computational studies on instability mechanisms in advanced reactors such as the Advanced Thermal Reactor (ATR) and molten chloride salt fast reactors, emphasizing accurate modeling of heat transfer and fluid dynamics under low-flow and passive safety conditions. Their work integrates neutronics and thermal-hydraulics coupling analyses to evaluate intrinsic safety characteristics and fuel temperature responses during transients. The lab also investigates anomalies in heat transfer coefficients at low Péclet numbers, challenging conventional empirical correlations in liquid metal systems.
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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