Rick Fortman, B.Eng. P.Eng.
Vice President: Stern Laboratories
Phone: (905) 548-5300
E-mail: Click Here
Over 30 years of experience designing and managing R&D projects for the nuclear industry at Stern Labs. Strong background in design and analysis of systems involving mechanical components, heat transfer and fluid mechanics. Proficient in writing custom software in C++ for machine control and DAS sub-systems. Principal test engineer for many of the experimental programs.
B.Eng. (Mechanical Engineering) 1982, McMaster University.
- Vice President, Stern Laboratories Inc., 2004 to present.
- Senior Engineer, Stern Laboratories Inc., March 1993 to 2004.
- Project Engineer, Stern Laboratories Inc., April 1988 to March 1993.
- Project Engineer, Westinghouse Canada Inc., 1982 to April 1988.
Publications and Presentations
- E. Kohn (OH, Canada) and R.A. Fortman (Stern Laboratories), “Fuel Bowing in Dryout as a result of operational transients – fitness for service after events”, Normal Operating Conditions CANDU Fuel Review Meeting, Ontario Hydro, April 20-21, 1998.
- E. Kohn (OH, Canada), R.H. Hu (HQ, Canada), G.I. Hadaller and R.A. Fortman (Stern Laboratories, Canada), “Understanding CANDU Fuel Bowing in Dryout: An Industry Approach”, Canadian Nuclear Society: Fifth International Conference on CANDU Fuel, September 21-25, 1997, Toronto, Canada.
- R.A. Fortman, G.I. Hadaller, R.C. Hayes, F. Stern (Stern Laboratories Inc.), W.I. Midvidy (Ontario Hydro), “Heat Transfer Studies with CANDU Fuel Simulators”, ICONE5, May 26-30, 1997, Nice, France.
- E. Kohn, J.K. Chan, V.J. Langman, G.I. Hadaller and R.A. Fortman, “CANDU Fuel Compression Tests at Elevated Temperatures”, Fourth International CANDU Fuel Conference, Pembroke, Ontario, October 1995.
- R.A. Fortman, G.I. Hadaller, R.C. Hamilton, R.C. Hayes, K.S. Shin and F.Stern, “A New Facility for the Determination of Critical Heat Flux in Nuclear Fuel Assemblies”, INC93, Toronto, Canada, October 3-6, 1993.
- G.I. Hadaller and R.A. Fortman (Stern Laboratories, Hamilton, Ontario), J. Szymanski and W.I. Midvidy (Ontario Hydro, Toronto, Ontario) and D.J. Train (IDEA Research, Toronto, Ontario) “Frictional Pressure Drop For Staggered and In-line Tube Banks with Large Pitch to Diameter Ratio”, Canadian Nuclear Society: 17th Annual Nuclear Simulation Symposium, Royal Military College of Canada, Kingston, Ontario, August 16-18, 1992.