Michael L. Corradini

Affiliations:

Nuclear Engineering & Engineering Physics

University of Wisconsin, Madison, Madison, WI

Area:

Nuclear Engineering

Google:

Bio:

http://cdn.ans.org/about/presidents/docs/michael-l-corradini-bio.pdf
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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Parents

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

Children

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)

Collaborators

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Publications

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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