Karen Vierow

Karen Vierow

Associate Professor, Nuclear Engineering

Date of Appointment: 2006

Office: 130B Zachry Engineering Center
Phone: 979/458-0600
Fax: 979/845-6443
E-mail: vierow@ne.tamu.edu
Website: NHTS

Education

Ph.D., Quantum Engineering and System Sciences, University of Tokyo
M.S., Nuclear Engineering, University of California at Berkeley
B.S., Nuclear Engineering, Purdue University

Courses Taught

NUEN 101: Principles of Nuclear Engineering
NUEN 406: Nuclear Engineering Systems and Design
NUEN 410: Nuclear Reactor Design
NUEN 489: Special Topics: Nuclear Reactor Safety Analysis
NUEN 609: Nuclear Reactor Safety
NUEN 689: Special Topics: Severe Accident Analysis

Hover over the course names to see descriptions. Follow the links to get more details.


Areas of Interest

Curriculum Vita: Click Here to View


Recent Publications

Journal Articles:

  1. N. Brown, S. Oh, S. T. Revankar, K. Vierow, S. Rodriguez, R. Cole Jr., R. O. Gauntt, "Simulation of Sulfur Iodine Thermochemical Hydrogen Production Plant Coupled To High Temperature Heat Source," Nuclear Technology 167(1), 95-106, 2009.
  2. Y. Liao and K. Vierow, "Variable Property Effects on Vapor Condensation with a Noncondensable Gas," Nuclear Technology 167(1), 13-19, 2009.
  3. S. B. Rodriguez, R. O. Gauntt, R. Cole, F. Gelbard, K. McFadden, T. Drennen, B. Martin, D. Louie, L. Archuleta, M. El-Genk, J. M. Tournier, F. Espinoza, S. T. Revankar, and K. Vierow, "Transient Analysis of Sulfur-Iodine Cycle Experiments and Very High Temperature Reactor Simulations Using MELCOR-H2," Nuclear Technology 166(1), 76-85 (2009).
  4. Y. Liao, K. Vierow, A. Dehbi, and S. Guentay, "Transition from Natural Convection for Steam-Gas Flow Condensing along a Vertical Plate ," International Journal of Heat and Mass Transfer 52, 366-375, 2009.
  5. Y. Liao and K. Vierow, "A Generalized Diffusion Layer Model for Condensation of Vapor with Non-condensable Gases," Transactions of the ASME, Journal of Heat Transfer 129, 988-994 (2007).
  6. T. Nagae, M. Murase, T. Chikusa, K. Vierow, and T. Wu, "Reflux Condensation Heat Transfer of Steam-Air Mixture under Turbulent Flow Conditions in a Vertical Tube," Journal of Nuclear Science and Technology 44(2), 171-182 (2007).

Conference Proceedings:

  1. P.V. Tsvetkov, K. Vierow, K.L. Peddicord, J.C. Ragusa, S.M. McDeavitt, J.W. Poston, Sr., L. Shao, and G. Willems,, "Autonomous Multi-purpose Floating Power System with a Compact Static Pebble Bed Reactor," PHYSOR ‘08 – International Conference on the Physics of Reactors, Interlaken, Switzerland, September 14-19 (2008).
  2. K. J. Hogan and K. Vierow, "A New Drift-Flux-Based Approach to Predict Flooding," Proceedings of the U.S. Japan Two Phase Flow Seminar, Santa Monica, CA, Sept. 2008.
  3. M. Solmos, K. J. Hogan, and K. Vierow, "Flooding Experiments and Modeling for Improved Reactor Safety," Proceedings of the U.S. Japan Two Phase Flow Seminar, Santa Monica, CA, Sept. 2008.
  4. Y. Liao, K. Vierow, and J. T. Han , "MELCOR Validation against a PUMA Facility Main Steam Line Break Integral Test ," Proceedings of the International Conference for Advanced Nuclear Power Plants (ICAPP-08), Anaheim, CA, June 2008.  
  5. K. Vierow, F. Best, J. Ford, Y. Hassan, S. McDeavitt, J. Ragusa, W. D. Reece, L. Shao, and P. Tsvetkov, "TAMU Nuclear Safety Curriculum Development for a 21st Century Workforce," Proc. of 2008 ANS Annual Meeting, Annaheim, CA, June 2008.
  6. K. Vierow, "Severe Accident Investigations and Modeling – Recent Progress and Issues ," Proceedings of the New Horizons in Nuclear Reactor Thermal Hydraulics, Bhabha Atomic Research Centre (BARC), Mumbai, Jan 7-8, 2008.  
  7. K. Hogan, H. Alkaabi, S. Revankar, R. K. Cole Jr., R. O. Gauntt, S. B. Rodriguez and K. Vierow, "MELCOR Analysis of High-Temperature Gas-Cooled Nuclear Reactors ," Proceedings of the India Society of Heat and Mass Transfer – American Society of Mechanical Engineers Conference, JNTU Hyderabad, India, Jan. 3-5, 2008.
  8. N. Brown, S. T. Revankar, K. Vierow, S. Rodriguez, R. Cole Jr., R. O. Gauntt , "Thermochemical Hydrogen Pant Coupled to High Temperature Gas Cooled Reactor ," Proceedings of 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), Pittsburgh, PA, Oct., 2007.

Other Publications:

  1. K. Vierow, "Enhancement of Nuclear Power Plant Safety by Condensation-driven passive heat removal systems," Thermal engineering in power systems. edited by R. S. Amano and B. Sunden (WIT Press: Southampton, 2008), pp.141-170.