Michael L. Corradini

Nuclear Engineering & Engineering Physics University of Wisconsin, Madison, Madison, WI 
Nuclear Engineering
"Michael Corradini"

Corradini, M. L., Heat transfer and fluid flow aspects of fuel-coolant interactions., Thesis. 1979. Ph.D. cn--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.

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Warren Max Rohsenow grad student 1979 MIT
Neil Emmanuel Todreas grad student 1979 MIT
 (Heat transfer and fluid flow aspects of fuel-coolant interactions.)


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Mark H. Anderson grad student 1998 UW Madison
Alaa E. Hassan grad student 2000 UW Madison
Seunghyun Baik grad student 2001 UW Madison
Tristan T. Utschig grad student 2001 UW Madison
Sherif H. Mohamed grad student 2003 UW Madison
Helge B. Klockow grad student 2004 UW Madison
Rachna Jain grad student 2005 UW Madison
Prashanth R. Prakash grad student 2005 UW Madison
Aya K. Diab grad student 2007 UW Madison
Jeremy R. Licht grad student 2008 UW Madison
Guillaume P. Mignot grad student 2008 UW Madison
Paul W. Humrickhouse grad student 2009 UW Madison
Alan M. Kruizenga grad student 2010 UW Madison
Kevin R. Robb grad student 2011 UW Madison
Thomas A. Carstens grad student 2013 UW Madison
Michael G. Hvasta grad student 2013 UW Madison
Darius D. Lisowski grad student 2013 UW Madison
Geoffrey R. Bull grad student 2014 UW Madison
Lewis J. Lloyd grad student 2014 UW Madison
Juliana Pacheco Duarte grad student 2014-2018 UW Madison (E-Tree)
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Chen R, Wang J, Su GH, et al. (2016) Analysis of KROTOS KS-2 and KS-4 steam explosion experiments with TEXAS-VI Nuclear Engineering and Design. 309: 104-112
Wang J, Wang C, Corradini ML, et al. (2016) PHEBUS FPT-1 simulation by using MELCOR and primary blockage model exploration Nuclear Engineering and Design. 307: 119-129
Wang X, Chang H, Corradini M, et al. (2016) Prediction of falling film evaporation on the AP1000 passive containment cooling system using ANSYS FLUENT code Annals of Nuclear Energy. 95: 168-175
Wang J, Corradini ML, Haskin T, et al. (2015) Comparison of hydrogen generation rate between cora-13 test and MELCOR simulation: Clad solid-phase oxidation models using self-developed code MYCOAC Nuclear Technology. 192: 25-34
Bull GR, Oakley JO, Corradini ML. (2015) Effects of bubble injection on heat transfer from a volumetrically heated water pool Nuclear Science and Engineering. 180: 301-311
Yang J, Greenwood MS, De Angelis M, et al. (2015) Study of critical heat flux in natural convection-cooled TRIGA reactors with single annulus and rod bundle geometries Nuclear Science and Engineering. 180: 141-153
Yeom H, Sridharan K, Corradini ML. (2015) Bubble dynamics in pool boiling on nanoparticle-coated surfaces Heat Transfer Engineering. 36: 1013-1027
Mao K, Wang J, Li L, et al. (2015) Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000 Progress in Nuclear Energy. 85: 352-365
Hamman KD, Tokuhiro AT, Muci MA, et al. (2015) CFD analysis of the 1/4 - Scale air reactor cavity cooling system inlet plenum International Conference On Nuclear Engineering, Proceedings, Icone. 2015
Lisowski DD, Omotowa O, Muci MA, et al. (2014) Influences of boil-off on the behavior of a two-phase natural circulation loop International Journal of Multiphase Flow. 60: 135-148
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