Zhang Kui

TL;DR: In this article, single-phase convective heat transfer and steam-water two-phase flow boiling heat transfer experiments have been carried out with a vertical seven-rod bundle at low flow conditions near atmospheric pressure.

TL;DR: In this paper, a vertical two-phase air-water flow across a horizontal staggered rod bundle under conditions of air quality ranging from 0.001 to 0.3 and mass velocity ranging from 80 to 500 kg/(m 2 ǫ) was analyzed and compared with predictions from existing correlations.

TL;DR: In this article, the effects of relative axial position, wall heat flux and Re number on the heat transfer were discussed, respectively, and new correlations for the friction factor and Nu number calculations were proposed based on the current experimental data.

TL;DR: In this article, an experimental and theoretical research has been carried out for vertically upward two-phase flow of air-water across staggered rod bundles having inclination angles of 0°, 45° and 90°.

TL;DR: In this article, the authors evaluated the reliability of existing friction factor correlations and provided available experimental data to validate the accuracy of the thermal hydraulic codes for the design of the lead-based reactor.