A study of critical heat flux for low flow of water in vertical round tubes under low pressure
- 2 December 1991
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 132 (2) , 225-237
- https://doi.org/10.1016/0029-5493(91)90267-l
Abstract
No abstract availableKeywords
This publication has 10 references indexed in Scilit:
- Classification of critical heat flux patterns using entropy minimax principleInternational Communications in Heat and Mass Transfer, 1991
- A CHF characteristic for downward flow in a narrow vertical rectangular channel heated from both sidesInternational Journal of Multiphase Flow, 1989
- Experimental studies of critical heat flux for low flow of water in vertical annuli at near atmospheric pressureInternational Journal of Heat and Mass Transfer, 1988
- Effect of channel geometry on critical heat flux for low pressure waterInternational Journal of Heat and Mass Transfer, 1987
- Boiling burnout and flow instabilities for water flowing in a round tube under atmospheric pressureInternational Journal of Heat and Mass Transfer, 1985
- The effect of flow direction and magnitude on CHF for low pressure water in thin rectangular channelsNuclear Engineering and Design, 1985
- Experimental study of differences in DNB heat flux between upflow and downflow in vertical rectangular channel.Journal of Nuclear Science and Technology, 1985
- Boiling and Dryout Behavior in a Liquid-Metal Fast Breeder Reactor Subassembly Bundle Under Low Heat Flux and Low Flow ConditionsNuclear Science and Engineering, 1983
- Effect of density ratio on critical heat flux in closed end vertical tubesInternational Journal of Multiphase Flow, 1981
- The boiling crisis in nuclear reactor safety and performanceInternational Journal of Multiphase Flow, 1980