Experimental Investigation of Natural Convection in a Core of Marine Reactor in Rolling Motion
スポンサーリンク
概要
- 論文の詳細を見る
A series of single-phase natural circulation experiments in a simulated marine reactor mounted on a rolling bed was performed and the average Nusselt number in the core was evaluated in order to investigate effects of the rolling motion on the heat transfer in the core. Heat transfer with an upright attitude is well correlated with the Rayleigh number and is slightly lower than El-Genk’s correlation. Heat transfer in the core is not affected by the inclination angle because the inclination of the present experiment is not large enough to cause any remarkable changes in the flow pattern of the core. Heat transfer in the core is enhanced by the rolling motion which is thought to cause internal flow in the core. Heat transfer during the rolling motion is correlated with the Richardson number for rolling motion, RiR, and is classified into three regimes: (1) region A (0.05<RiR≤0.3) where heat transfer is dominated by the inertial force due to the rolling motion; (2) region B (0.3<RiR≤2) where heat transfer is affected by the combined effect of the inertial force and natural convection; and (3) region C (RiR>2) where heat transfer is affected only by the natural convection.
- 一般社団法人 日本原子力学会の論文
著者
-
Sawada Ken-ichi
Nuclear Technology Division Ship Research Institute Ministry Of Transport
-
MURATA Hiroyuki
Nuclear Technology Division, Ship Research Institute, Ministry of Transport
-
KOBAYASHI Michiyuki
Nuclear Technology Division, Ship Research Institute, Ministry of Transport
-
Kobayashi Michiyuki
Nuclear Technology Division Ship Research Institute Ministry Of Transport
-
Murata Hiroyuki
Nuclear Technology Division Ship Research Institute Ministry Of Transport
-
KOBAYASHI Michiyuki
Nuclear Ship Division, Ship Research Institute
関連論文
- Experimental Investigation of Natural Convection in a Core of Marine Reactor in Rolling Motion
- Friction pressure drop and heat transfer coefficient of two-phase flow in helically coiled tube once-through steam generator for integrated type marine water reactor.
- Pressure and fluid oscillations in vent system due to steam condensation, (II). High-frequency component of pressure oscillations in vent tubes under at chugging and condensation oscillation.:High-Frequency Component of Pressure Oscillations in Vent Tubes