Fan-Bill Cheung
Affiliations: | Nuclear Engineering | Pennsylvania State University, State College, PA, United States |
Area:
Nuclear Engineering, Mechanical EngineeringWebsite:
https://www.me.psu.edu/department/directory-detail-g.aspx?q=FXC4Google:
"Fan-Bill Cheung"Bio:
https://ui.adsabs.harvard.edu/abs/1974PhDT........47C/abstract
DOI: 10.1615/IHTC5.1770
Parents
Sign in to add mentor| Victor Wai-Tsu Nee | grad student | 1974 | Notre Dame | |
| (A phenomenological theory of heat transfer in turbulent shear flows) | ||||
Children
Sign in to add trainee| Chittin Tangthieng | grad student | 2002 | Penn State |
| Jeffrey W. Lane | grad student | 2009 | Penn State |
| Michael J. Meholic | grad student | 2011 | Penn State |
BETA: Related publications
See more...
Publications
|
You can help our author matching system! If you notice any publications incorrectly attributed to this author, please sign in and mark matches as correct or incorrect. |
| Jin Y, Cheung F, Shirvan K, et al. (2019) Development of a droplet breakup model for dry spacer grid in the dispersed flow film boiling regime during reflood transients International Journal of Heat and Mass Transfer. 143: 118544 |
| Mohanta L, Cheung F, Bajorek SM. (2016) Stability of coaxial jets confined in a tube with heat and mass transfer Physica a-Statistical Mechanics and Its Applications. 443: 333-346 |
| Meholic MJ, Aumiller DL, Cheung FB. (2015) A comprehensive, mechanistic heat transfer modeling package for dispersed flow film boiling - Part 2 - Implementation and assessment Nuclear Engineering and Design. 291: 302-311 |
| Meholic MJ, Aumiller DL, Cheung FB. (2015) A comprehensive, mechanistic heat transfer modeling package for dispersed flow film boiling - Part 1 - Development Nuclear Engineering and Design. 291: 295-301 |
| Kang H, Cheung F. (2013) Linear Instability Analysis Of A Water Sheet Trailing From A Wet Spacer Grid In A Rod Bundle Nuclear Engineering and Technology. 45: 895-910 |
| Ha KS, Cheung F, Song J, et al. (2013) Prediction of Boiling-Induced Natural-Circulation Flow in Engineered Cooling Channels Nuclear Technology. 181: 196-207 |
| Lane JW, Aumiller DL, Cheung FB, et al. (2010) A self-consistent three-field constitutive model set for predicting co-current annular flow Nuclear Engineering and Design. 240: 3294-3308 |
| Holowach MJ, Hochreiter LE, Cheung F, et al. (2002) Critical Heat Flux During Reflood Transients in Small-Hydraulic-Diameter Geometries Nuclear Technology. 140: 18-27 |
| Cheung F, Haddad KH, Liu YC. (1999) Boundary-Layer-Boiling and Critical-Heat-Flux Phenomena on a Downward-Facing Hemispherical Surface Nuclear Technology. 126: 243-264 |
| Liu YC, Cheung FB. (1998) Boiling-induced two-phase natural convection in an annular channel heated on the downward facing side American Society of Mechanical Engineers, Heat Transfer Division, (Publication) Htd. 361: 29-36 |