Bio: Gordon Hadaller

Gordon Hadaller, M.Sc. M.E. B.Sc. P.Eng.
President: Stern Laboratories
Phone: (905) 548-5300
E-mail: Click Here

Thirty-eight years of experience designing and managing research and development projects for the nuclear industry. Strong background in mechanical design, instrumentation, vibration, acoustics and heat transfer. Designed major hardware for pressure tube sag, multichannel burst test.

Education

  • M.Sc. M.E. (Heat Transfer-Fluid Mechanics) 1979, University of Manitoba.
  • B.Sc. (Mechanical Engineering) 1970, University of Manitoba.

Positions Held

  • President, Stern Laboratories Inc., September 1993 to present.
  • Vice President, Stern Laboratories Inc., April 1988 to September 1993.
  • Manager/Supervisor, Systems Dynamics Section, Contract Engineering, Westinghouse Canada Inc., 1981 to January 1988.
  • Project Engineer, Systems Dynamics Section, Westinghouse Canada Inc., 1972 to 1981.

Publications

  • G.I. Hadaller (Stern Laboratories), “COG Related Experiments at Stern Laboratories”, 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, G.I. Hadaller and P.F. Sandig, “CANDU Fuel Qualification Testing in Coolant Pressure Pulse Conditions”, Fourth International CANDU Fuel Conference, Pembroke, Ontario, October 1995.
  • 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.
  • M. Majed, G. Norback, P. Wiman, G.I. Hadaller, R.C. Hayes and F. Stern, “Experience Using Individually Supplied Heater Rods in Critical Power Testing of Advanced BWR Fuel”, NURETH-7, Saratoga Springs, N.Y., September 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.
  • P.M. Mathew, D.G. Evans, S. Wadsworth, E. Kohn, M. Notley, G.I. Hadaller, “Disassembly Behaviour of CANDU Bundles Under Impact”, Third International Conference on CANDU Fuel, Chalk River, Canada, October 1992.
  • K.E. Locke, F.B.P. Tran, A.P. Muzumdar and G.I. Hadaller, “Thermal Hydraulic and Dynamic Modelling of Reverse Flow Bundle Acceleration Experiments” CNS Conference, Saskatoon, Canada, June 1991.
  • G.I. Hadaller and A.P. Muzumdar, “Full Scale Calandria Tube Burst Tests at Fast Pressurization Rates”, Canadian Nuclear Society Conference, Winnipeg, Manitoba, June 1988.
  • G.I. Hadaller and A.P. Muzumdar, “Progress on an Experimental Program to Determine the Consequences of Pressure Tube Rupture in CANDU Reactors”, Canadian Nuclear Society Conference, Saint John, New Brunswick, June 1987.
  • S.L. Wadsworth, G.I. Hadaller, R.M. Sawala and E. Kohn, “Experimental Investigation of CANDU Fuel Deformation During Severely Degraded Cooling”, presented at the Thermal Reactor Safety Meeting, San Diego, California, February 1986.
  • A.P. Muzumdar, G.I. Hadaller and R. Chase, “Experimental Program to Determine the Consequences of Pressure Tube Rupture in CANDU Reactors”, presented at the Thermal Reactor Safety Meeting, San Diego, California, February 1986.
  • M. Renksizbulut and G.I. Hadaller, “An Experimental Study of Turbulent Flow Through a Square-Array Rod Bundle”, published in Nuclear Engineering & Design, February 1986.
  • H.A. Khater, G.I. Hadaller and F. Stern, “Pressure Tube Rupture in a Closed Tank: Phase I – Feasibility Study”, a research report prepared for the Atomic Energy Control Board, issued as an AECB INFO Report, June 1985.
  • G.E. Gillespie, R.G. Moyer, G.I. Hadaller, and J.G. Hildebrant, “An Experimental Investigation Into the Development of Pressure Tube/Calandria Tube Contact and Associated Heat Transfer under LOCA Conditions”, Canadian Nuclear Society Conference, Ottawa, Ontario, June 1985.
  • E. Kohn, G.I. Hadaller, R.M. Sawala, G.H. Archinoff and S.L. Wadsworth, “CANDU Fuel Development During Severely Degraded Cooling: Experimental Results” Canadian Nuclear Society Conference, Ottawa, Ontario, June 1985.
  • G.I. Hadaller, R.M. Sawala, E. Kohn, G.H. Archinoff, S.L. Wadsworth, “Experiments Investigating the Thermal-Mechanical Behaviour of CANDU Fuel Under Severely Degraded Cooling”, presented at the Fifth International Meeting on Thermal Nuclear Reactor Safety – Karlsruhe, September 1984.
  • G.E. Gillespie, R.G. Moyer and G.I. Hadaller, “An Experimental Investigation of the Creep sag of Pressure Tubes under LOCA Conditions”, Canadian Nuclear Society Conference, Saskatoon, Sask., June 1984.
  • G.I. Hadaller, G.H. Archinoff and E. Kohn, “CANDU Fuel Behaviour During Degraded Cooling Conditions”, Canadian Nuclear Society Conference, Montreal, Quebec, June 1983.
  • G.I. Hadaller, “A Study of Drag Reduction Employing a Laser Doppler Velocimeter”, M.Sc. Thesis, University of Manitoba, 1979.
  • S. Banerjee and G.I. Hadaller, “Longitudinal Laminar Flow Between Cylinders Arranged in a Triangular Array by a Variational Technique”, J. Appl. Mech., Vol. 40, No. 4, December 1973.
  • G.I. Hadaller and S. Banerjee, “Heat Transfer to Superheated Steam in Round Tubes”, AECL, WDI-147, November 1969.