Seungjin Kim
Affiliations: | 2017 | Pennsylvania State University, State College, PA, United States | |
| 2017- | Purdue University, West Lafayette, IN, United States |
Area:
Mechanical and Nuclear EngineeringWebsite:
https://engineering.purdue.edu/Engr/People/NewFaculty/New_Faculty_2017/kim.htmlGoogle:
"Seungjin Kim"Bio:
http://www.mne.psu.edu/amfl/Members/Kim.html
http://docs.lib.purdue.edu/dissertations/AAI3055508/
Parents
Sign in to add mentor| Mamoru Ishii | grad student | 1999 | Purdue | |
| (Interfacial area transport equation and measurement of local interfacial characteristics.) | ||||
Children
Sign in to add trainee| Robert J. Zerr | grad student | 2011 | Penn State (Chemistry Tree) |
| Justin Talley | grad student | 2012 | Penn State |
| Mohan S. Yadav | grad student | 2013 | Penn State |
| Matt Bernard | grad student | 2014 | Penn State |
| Ted Worosz | grad student | 2015 | Penn State |
| Shouxu Qiao | grad student | 2017 | Penn State |
| Ran Kong | grad student | 2018 | Purdue |
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. |
| Kim S, Ishii M, Kong R, et al. (2021) Progress in two-phase flow modeling: Interfacial area transport Nuclear Engineering and Design. 373: 111019 |
| Kim S, Kong R. (2020) Separate-effect experiments and modeling for two-phase flow under geometric restrictions Nuclear Engineering and Design. 367: 110786 |
| Kong R, Kim S, Ishii M. (2020) Review of jet impingement in high-energy piping systems Nuclear Engineering and Design. 357: 110411 |
| Karaman U, Kocar C, Rau A, et al. (2019) Numerical Investigation of Flow Characteristics through Simple Support Grids in a 1 x 3 Rod Bundle Nuclear Engineering and Technology. 51: 1905-1915 |
| Kong R, Rau A, Kim S, et al. (2019) A robust image analysis technique for the study of horizontal air-water plug flow Experimental Thermal and Fluid Science. 102: 245-260 |
| Lee DH, Kim S, Yoon HY, et al. (2018) Assessment of the CUPID Code for Bubbly Flows in Horizontal Pipes Nuclear Technology. 204: 330-342 |
| Lu C, Kong R, Qiao S, et al. (2018) Frictional pressure drop analysis for horizontal and vertical air-water two-phase flows in different pipe sizes Nuclear Engineering and Design. 332: 147-161 |
| Jin Y, Miller DJ, Qiao S, et al. (2018) Uncertainty analysis on droplet size measurement in dispersed flow film boiling regime during reflood using image processing technique Nuclear Engineering and Design. 326: 202-219 |
| Qiao S, Kim S. (2018) On the prediction of two-phase pressure drop across 90° vertical elbows International Journal of Multiphase Flow. 109: 242-258 |
| Kong R, Qiao S, Kim S, et al. (2018) Interfacial area transport models for horizontal air-water bubbly flow in different pipe sizes International Journal of Multiphase Flow. 106: 46-59 |