The Faculty of Nuclear and Radiological Engineering Program at UC

Joel Weisman

Professor Emeritus of Nuclear Engineering

Date of initial appointment: September, 1968
Degrees, where and when conferred:
B.Ch.E. City College of New York, 1948
M.S. Columbia University, 1949
Ph.D. University of Pittsburgh, 1968

Phone: (513) 556-2009
Fax: (513) 556-3390

Field of Specialization and Areas of Interest:

Thermal-Hydraulic Analysis of Nuclear Reactors, Critical Heat Flux Predicative Methodology, Reactor Safety

Recent Publications:

• "Two Phase Flow Patterns and Boiling Heat Transfer in Tubes Containing Helical Wire Inserts", Part I - Flow Patterns & Heat Transfer, PArt II, Critical Heat Flux", J. Enhanced Heat Transfer, 4, 283 (1997)
• "Thermal Analysis of Pressurized Water Reactors", J. Weisman & L.S. Tong, ANS Monograph, 3rd edition (1996)"
• A Phenomemological Explanation of the Relationship Between Steady State & Transport CHF at Subcooled & Low-Quality Conditions," J. Weisman, Nuc. Eng. Des., 158, 157 (1995).
• "Two-Phase (Air-Water) Flow Patterns and Pressure Drop in the Presence of Helical Wire Ribs," J. Weisman, P. Disimile, J. Lan, Int. J. Multiphase Flow, 20, 885 (1994).
• "A Phenomenological Model for Boiling Heat Transfer and Critical Heat Flux in Tubes Containing Twisted Tapes," J. Weisman, J.Y. Yang, and S. Usman, Int. J. Heat Mass Transfer, 37, 69 (1994).
• "The Current Status of Theoretically Based Approaches to the Prediction of the Critical Heat Flux in Flow Boiling," J. Weisman, Nuc. Tech., 99, 1 (1992).

Program Responsibility:

• Teaches courses on as-needed basis.
  

Consulting, Industrial Employment, and Other Pertinent Data:

• Joel Weisman & Associates provides consulting services to the nuclear industry
• Fellow, American Nuclear Society
• Reviewer: Int. J. of Multiphase Flow, Nuclear Technology, Nuclear Engineering & Design
• Biographical listings - Who's Who in Midwest, Who's Who in America, Who's Who in Engineering and Science