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Charles Fraser Forrest

Birth Place:
Citizenship:

 Manitou, Manitoba
Canadian

Education:

M.A.Sc. (Fluid Mechanics) 1969, University of Waterloo.

B.Sc. (Mechanical Engineering) 1966, University of Manitoba.

Post University Training:

"Heavy Water Reactor Design Principles", University of Toronto.

"Directing the Engineering Project", Westinghouse Electric Corp., Pittsburgh, PA.

"Management Forum", Westinghouse Canada Inc., Hamilton.

Positions Held:
  1. Vice President, Stern Laboratories Inc, April 1988 to present.

  2. Manager, Systems Analysis, Contract Engineering, Nuclear Products Dept. Westinghouse Canada Inc., January 1980 to April 1988.

  3. Supervisor, Systems Dynamics Section, Systems Development Laboratory, Westinghouse Canada Inc., February 1974 to December 1979.

  4. Engineer, Systems Dynamics Section, Systems Development Laboratory, Westinghouse Canada Inc., November 1969 to February 1974.

  5. Asst. Shift Supervisor, NRX Operations, Atomic Energy of Canada Limited, November 1967 to September 1968.

  6. Engineer, ORENDA Limited, Malton, Ontario, June 1966 to October 1967.
Publications and Presentations:

Fraser Forrest, Lorne Macdonald and Ahmed Shalabi, “Ballooning Experiments for CANDU Pressure Tubes”, Ninth Intl. Topical Meeting on Nuclear Thermal Hydraulics NURETH 9, Oct. 3-8, 1999.

Greg Rzentkowski and C.F. Forrest, “Experimental Investigation Into Integrity Of Fretted Steam Generator Tubes Under Accident Conditions”, 6th Intl. Conference on Nuclear Engineering ICONE-6, May 10-15, 1998.

C.F. Forrest and F. Stern, “Test Facilities for the Study of Thermofluid Accidents in Fusion Reactors”, Journal of Fusion Energy, Vol 12, Nos. 1/2, 1993.

G.L. Ogram, K.R. Weaver, R.J. Fluke and C.F. Forrest, "On the Aerosol Produced by a Flashing Water Jet in a Large-Scale Experiment", to be presented at the American Association for Aerosol Research 1990 Annual Meeting, Philadelphia, PA, June 18-22, 1990.

R.J. Fluke, K.R. Weaver, W.W. Koziak, G. Ogram and C.F. Forrest, "The Water Aerosol Leakage Experiments: Programme Description and Preliminary Results", to be presented at the Second International Conference on Containment Design and Operation, Toronto, Ontario, October 14-17, 1990.

H.A. Khater, C.F. Forrest, W.I. Midvidy, N.N. Wahba, "Steam Generator Feedline Break Simulation Tests" Eighth Intl. Heat Transfer Conference and Exhibition, San Francisco, Calif., Aug 17-22, 1986.

C.F. Forrest, K.S. Shin, W.I. Midvidy, R.E. Pauls and N. Wahba, "Measurements of Impact Loads and Expansion of Flashing Water Jets", International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Newport, RI, October 1985, also published in Nuclear Engineering and Design 99 (1981) 53-61.

C.F. Forrest and R.A. Fortman, "A Facility for Determining the Heat Transfer Characteristics of Present and Novel CANDU Fuels", CNA Meeting, Ottawa, Ontario, June 1985.

C.F. Forrest, "Pump Behaviour Under Two-phase Flow Conditions", Seminar Presented at McMaster University, Hamilton, Ontario, March 1981.

A.D. Lane, I.E. Oldaker, C.F. Forrest, F. Stern and C. Orpen, "The Measurement and Prediction of Vibration in CANDU PHW Fuel and Channel Assemblies", Presented at B.N.E.S. Conference of Vibration in Nuclear Plants at Keswick, U.K., 1978.

C.F. Forrest and P.J.J. Monti, "Vibration Measurements on a String of CANDU Fuel Bundles in Adiabatic Steam-Water Flow", Paper D3/6 4th SMIRT Conference, San Francisco, U.S.A., August 1977.

C.F. Forrest, "Vibration Response of Vertical Fuel Strings Subjected to Water and Steam-Water Flow", Paper prepared for presentation at a seminar of Vibration of Reactor Fuel and Steam Generator Tubes, Moscow, September 1975.

C.F. Forrest And F. Stern, "Fretting-Wear Studies Pertinent to Power Reactor Fuel Channels", Paper prepared for presentation at a seminar of Vibration of Reactor Fuel and Steam Generator Tubes, Moscow, September 1975.

L.N. Carlucci and C.F. Forrest, "Experimental Determination of Fuel String Dynamic Parameters", Paper prepared for presentation at a seminar on Vibration of Reactor Fuel and Steam Generator Tubes, Moscow, September 1975.

C.F. Forrest, "Vibration Response of Vertical Fuel Strings Subjected to Water and Steam-Water Flow", Paper prepared for presentation at a seminar on Vibration of Reactor Fuel and Steam Generator Tubes, Moscow, September 1975.

C.F. Forrest and G.R. Seiveright, "Fretting-Wear Studies Pertinent to Nuclear Reactor Coolant Circuits", Presented at the Canadian Institute of Mining and Metallurgy 1975 Conference.

I.E. Oldaker, A.D. Lane, M.P. Paidoussis and C.F. Forrest, "An Overview of the Canadian Program to Investigate Vibration and Fretting in Nuclear Fuel Assemblies", presented at the ASME-CSME Fluids Engineering Conference, Montreal, May 1974.

C.F. Forrest and W.T. Hancox, "The Response of a Reactor Fuel String to Flow and Structurally Transmitted Excitation", Paper D3/8, 2nd SMIRT Conference, Berlin, Germany, September 1973.

C.F. Forrest and W.T. Hancox, "Mode Shape Determination of a Vibrating Nuclear Reactor Fuel String", presented at the Fourth Canadian Congress of Applied Mechanics, Montreal, May 28 - June 1, 1973.

W.T. Hancox, C.F. Forrest and A.A. Harms, "Void Determination in Two-Phase Systems Employing Neutron Transmission", A.S.M.E. Paper 72-HT-2, 1972.

A.A. Harms and C.F. Forrest, "Dynamic Effects in Radiation Diagnosis of Fluctuating Voids", Nuclear Science and Engineering 46, 1971.


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