The onset of nucleate boiling (ONB) serves as the thermal-hydraulic operating limit for many research and test reactors. However, boiling incipience under forced convection has not been well-characterized in narrow channel geometries or for oxidized surface conditions. This study presents experimental data for the ONB in vertical upflow of deionized (DI) water in a simulated materials test reactor (MTR) coolant channel. The channel gap thickness and aspect ratio were 1.96 mm and , respectively. Boiling surface conditions were carefully controlled and characterized, with both heavily oxidized and native oxide surfaces tested. Measurements were performed for mass fluxes ranging from 750 to and for subcoolings ranging from 10 to 45°C. ONB was identified using a combination of high-speed visual observation, surface temperature measurements, and channel pressure drop measurements. Surface temperature measurements were found to be most reliable in identifying the ONB. For the nominal (native oxide) surface, results indicate that the correlation of Bergles and Rohsenow, when paired with the appropriate single-phase heat transfer correlation, adequately predicts the ONB heat flux. Incipience on the oxidized surface occurred at a higher heat flux and superheat than on the plain surface.
Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel
Manuscript received July 10, 2015; final manuscript received August 18, 2015; published online February 29, 2016. Assoc. Editor: Igor Pioro.
- Views Icon Views
- Share Icon Share
- Cite Icon Cite
- Search Site
Forrest, E. C., Don, S. M., Hu, L., Buongiorno, J., and McKrell, T. J. (February 29, 2016). "Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel." ASME. ASME J of Nuclear Rad Sci. April 2016; 2(2): 021001. https://doi.org/10.1115/1.4031503
Download citation file:
- Ris (Zotero)
- Reference Manager