Publications by Discipline - Mechanical Engineering
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expand Title : A Method of Limiting Intermediate Volume Fraction in Iterative Two-Fluid Computations ‎(1)
expand Title : Canada's Power Reactor Fuel Bundle Design and Development ‎(1)
expand Title : Canadian Power Reactor Fuel ‎(1)
expand Title : CANDU Primary Heat Transfer System Heat Duty Diagram - analytic solution ‎(1)
expand Title : CANDU Primary Heat Transfer System Heat Duty Diagram - numeric solution ‎(1)
expand Title : Carver, M.B. - Selected Papers and Reports ‎(1)
expand Title : Course 2.2 - Thermal Study of Nuclear Reactors ‎(1)
expand Title : Course 2.3 - Reactor Thermalhydraulics Analysis ‎(1)
expand Title : Course 2.3a -Reactor Thermalhydraulics Analysis, Supplementary ‎(1)
expand Title : Course 3.6 - Reactor Mechanical Design ‎(1)
expand Title : Course 7.2 - Non-Destructive Testing  ‎(1)
expand Title : Course 7.5 - Welding Technology ‎(1)
expand Title : Development and Application of a Three-Dimensional Two-Fluid Numerical Algorithm for Simulation of Phase Redistribution by Bends and Obstructions ‎(1)
expand Title : Dyke, J.M. - Selected Works  ‎(1)
expand Title : Efficient Integration over Discontinuities in Ordinary Differential Equation Simulation ‎(1)
expand Title : Evolution of CANDU Steam Generators – A Historical View ‎(1)
expand Title : Fluid Mechanics ‎(2)
expand Title : Fluid Mechanics, Nuclear Training Course 123, April 1978 ‎(6)
expand Title : Fluid Mechanics, Nuclear Training Course 223, December 1984 ‎(3)
expand Title : Fluid Mechanics, Nuclear Training Course 223, January 1977 ‎(8)
expand Title : FORSIM a FORTRAN Oriented Simulation Package for the Automated Solution of Partial and Ordinary partial Differential Equation SYSTEMS ‎(1)
expand Title : Fretting Failures in Early Canadian Nuclear Steam Generators ‎(1)
expand Title : Fretting in Nuclear Steam Generators - A New Approach ‎(1)
expand Title : Heat and Thermodynamics Course ‎(3)
expand Title : Heat and Thermodynamics, Course 1-2.5, Nuclear Electric GS Technical Training Course ‎(2)
expand Title : Heat and Thermodynamics, Course 125, Nuclear Training Centre ‎(19)
expand Title : Heat and Thermodynamics, Course 1A25, Nuclear Training Course  ‎(1)
expand Title : Heat and Thermodynamics, Course 2-2.5, Nuclear Electric GS Technical Training Course ‎(1)
expand Title : Heat and Thermodynamics, Course 225, Nuclear Training Centre ‎(10)
expand Title : Heat and Thermodynamics, Course PI 25, Nuclear Training Centre ‎(11)
expand Title : Mécanique des Fluides ‎(1)
expand Title : Mechanical Equipment Course ‎(5)
expand Title : Mechanical Equipment, Course 23001 ‎(4)
expand Title : Mechanical Equipment, Course PI 30.1, Nuclear Training Centre ‎(26)
expand Title : Memories of my Life as a Professional Engineer in the Royal Navy and the Canadian Boiler Industry ‎(1)
expand Title : NDP-2 Systems - Calandria Assembly, Course T.T.01-312 ‎(1)
expand Title : Non-Destructive Testing, Course 7.2 ‎(7)
expand Title : NPD Systems - Fuel Handling System, Course 053 ‎(1)
expand Title : Nuclear Heated Steam Generators ‎(1)
expand Title : Nuclear Journal of Canada, 1987 Vol 1 No. 2 ‎(1)
expand Title : Nuclear Journal of Canada, 1987 Vol 1 No. 3 ‎(1)
expand Title : Nuclear Journal of Canada, 1987 Vol 1 No. 4 ‎(2)
expand Title : Numerical Solution of the Thermalhydraulic  Conservation Equations from Fundamental Concepts to Multidimensional Analysis ‎(1)
expand Title : Principes de Science et de Fonctionnement des Réacteurs - Chaleur et Thermodynamique ‎(1)
expand Title : Principes de Science et de Fonctionnement des Réacteurs - Équipement Mécanique ‎(1)
expand Title : Pseudo-characteristic method of lines solution of first-order hyperbolic equation systems ‎(1)
expand Title : Reactor Mechanical Design, Course 3.6 ‎(18)
expand Title : Reactor Thermalhydraulics Analysis, Course 2.3 ‎(18)
expand Title : Reactor Thermalhydraulics Analysis, Supplementary, Course 2.3a ‎(5)
expand Title : Simulation Software ‎(1)
expand Title : Single Phase Friction Factors for MNR Thermalhydraulic Modelling ‎(1)
expand Title : Software Quality Assurance: Practical Procedures to Meet CSA Standards ‎(1)
expand Title : Steam Generators for CANDU, Engineering Memoirs ‎(1)
expand Title : The Effect of Bypass Characteristics on Parallel Channel Flow Instabilities ‎(1)
expand Title : The method of lines and the advective equation ‎(1)
expand Title : The Pressurized Water Reactor as a Source of Heat for Steam Power Plants ‎(1)
expand Title : The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators ‎(1)
expand Title : The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators - Associated Presentation ‎(1)
expand Title : Thermal Study of Nuclear Reactors, Course 2.2 ‎(10)
expand Title : Thermal-Hydraulics in Recirculating Steam Generators: Thirst Code User's Manual ‎(1)
expand Title : Turbine and Auxiliaries, Course PI 34 / TIMS Ref. PI 3004, Nuclear Training Centre ‎(22)
expand Title : Turbine and Auxiliaries, Nuclear Training Course 234 ‎(15)
expand Title : Turbine, Generator and Auxiliaries, Course 1-3.4, Nuclear Electric GS Technical Training Course ‎(1)
expand Title : Turbine, Generator and Auxiliaries, Course 134, Nuclear Training Centre ‎(9)
expand Title : Turbine, Generator and Auxiliaries, Course 2-3.4, Nuclear Electric GS Technical Training Course ‎(1)
expand Title : Turbine, Generator and Auxiliaries, Course 3-3.4, Nuclear Electric GS Technical Training Course ‎(1)
expand Title : Turbine, Generator and Auxiliaries, Course 4-3.4, Nuclear Electric GS Technical Training Course ‎(1)
expand Title : Two Dimensional Modelling of the Homogenizing Effects of Flow Obstructions in Two Fluid Flow ‎(1)
expand Title : Two Phase Flow in Rod Bundles, ASSERT-4, Version 1 user's manual ‎(1)
expand Title : Welding Technology, Course 7.5 ‎(34)