1. Experimental investigation of local two-phase parameters in a 4 × 4 rod bundle channel under a subcooled boiling flow.
- Author
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Bak, Jinyeong, Moon, Jeongmin, Ko, Youngchang, Jeong, Jae Jun, and Yun, Byongjo
- Subjects
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EBULLITION , *TWO-phase flow , *NUCLEAR reactor cores , *HEAT exchangers , *POROSITY , *HEAT flux - Abstract
Subcooled boiling flow in a rod bundle geometry is an important phenomenon observed in the heat exchanger of heat transfer systems and reactor core of a nuclear power plant. However, experimental data on local two-phase flow parameters of rod bundle geometries in the subcooled boiling conditions are rare. In this study, an experiment was conducted to determine the distributions of the local two-phase parameters of a 4 × 4 rod bundle channel under a subcooled boiling water flow. The flow conditions were a mass flux range of 305 to 390 kg/m2s, a heat flux range of 190 to 274 kW/m2, and an inlet subcooling temperature of 20.5 to 25 °C at an inlet pressure of 200 kPa. The distributions of the void fraction, bubble velocity, interfacial area concentration (IAC), and Sauter mean diameter were measured with a four-sensor optical fiber probe (4S-OFP). The area-averaged bubble parameters were used to evaluate several drift-flux models and IAC correlations to assess their applicability to rod bundle channels. • Experimentally investigated subcooled boiling flow in a 4 × 4 rod bundle channel. • Local bubble parameters are acquired to Mass flux, heat flux, and inlet subcooling. • Area-average bubble parameters are obtained from local bubble parameter data. • Existing interfacial area concentration (IAC) and drift-flux models are evaluated. [ABSTRACT FROM AUTHOR]
- Published
- 2023
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