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Michael L. Corradini

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

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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.)

Children

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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

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Publications

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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
Yeom H, Sridharan K, Corradini ML. (2015) Bubble dynamics in pool boiling on nanoparticle-coated surfaces Heat Transfer Engineering. 36: 1013-1027
Mao K, Zhang Y, Corradini ML. (2014) Development of the code COAC for oxidation during core melting Transactions of the American Nuclear Society. 111: 1515-1516
Lisowski DD, Anderson MH, Corradini ML. (2013) X-ray attenuation method for the measurement of void fraction in a cylindrical test section Transactions of the American Nuclear Society. 109: 280-281
Chen RH, Corradini ML, Su GH, et al. (2013) Analysis of KROTOS steam explosion experiments using the improved fuel-coolant-lnteraction code TEXAS-VI Nuclear Science and Engineering. 174: 46-59
Chen RH, Su GH, Qiu SZ, et al. (2013) Development of a solidification model for TEXAS-VI code and application to FARO L14 analysis Nuclear Science and Engineering. 173: 1-14
Lisowski DD, Haskin TC, Tokuhiro A, et al. (2013) Study on the behavior of an asymmetrically heated reactor cavity cooling system with water in single phase Nuclear Technology. 183: 75-87
Chen RH, Corradini ML. (2012) Fuel-coolant interaction analysis for corium molten materials International Meeting On Severe Accident Assessment and Management 2012: Lessons Learned From Fukushima Dai-Ichi. 121-129
Lisowski DD, Anderson MH, Corradini ML. (2012) Numerical and experimental studies of heat transfer coefficients in a RCCS Transactions of the American Nuclear Society. 106: 103-104
Chen RH, Corradini ML, Su GH. (2012) Simulation of FARO corium coolant interaction experiment with TEXAS-VI Transactions of the American Nuclear Society. 106: 1029-1031
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