School: Pennsylvania State University

Began Rickover Fellowship: September 2008

Lab Assignment:

Lab Mentor: Dr. Jack Buchanan

Degree(s):
B.S. Nuclear Engineering, University of Missouri, Rolla
M.S. Nuclear Engineering, Pennsylvania State University

Expected Graduation Date: May 2012

University Advisor: Dr. Seungjin Kim

Field of Study: Two-Phase Flow/ Reactor Thermal-Hydraulics

Email Address: jtalley@psu.edu

Summary of Research:


Publications:

1. Talley, J. D., Kim, S., Guo, T., and Kojasoy, G., “Geometric effects of 45-degree elbow in horizontal air-water bubbly flow,” Nuclear Technology, 167 (1), pp. 2-12, 2009

2. Talley, J. D., Spring, J., Kim, S., and Mahaffy, J. H., “Implementation of One-Group Interfacial Area Transport Equation into TRACE,” 2009 ANS Annual Meeting, June 14-18, 2009, Atlanta, GA, USA.

3. Talley, J. D., Chakraborty, S., Keller, E., Ray, A., and Kim, S., “Objective Classification of Two-Phase Flow Regimes via Ultrasonic Signals,” 2009 ANS Annual Meeting, June 14-18, 2009, Atlanta, GA, USA.
   
4. Mohan, V. R., Yadav, M., Talley, J. D., Dorn, M. G., and Kim, S., “Characterization of a Combinatorial Round Pipe Flow,” 2009 ANS Annual Meeting, June 14-18, 2009, Atlanta, GA, USA.
   
5. Chakraborty, S., Keller, E., Talley, J. D., Srivastav, A., Ray, A., and Kim, S., “Void fraction measurement in two-phase flow processes via symbolic dynamic filtering of ultrasonic signals,” Meas. Sci. Tech., 20 (2), 023001, 2009
   
6. Yadav, M., Buck, R., Talley, J. D., and Kim, S., “Comparison of local interfacial structures around 45 and 90 degree elbows in the horizontal bubbly flow,” 2008 ANS Winter Meeting, November 9-13, 2008, Reno, NV, USA.
   
7. Talley, J. D., Kim, S., and Kojasoy, G., “Interfacial Area Transport in Horizontal Bubbly Flow with Elbow Restrictions,” 2008 International Congress on Advances in Nuclear Power Plants, June 8-12, 2008, Anaheim, CA, USA.
   
8. Talley, J. D., Kim, S., Guo, T., and Kojasoy, G., “Geometric Effects of 45-degree Elbow in Horizontal Air-Water Bubbly Flow,” 12 th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, September 30-October 4, 2007, Pittsburgh, PA, USA.