Publications by Topic - Thermalhydraulics
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expand Title : * The Essential CANDU ‎(1)
expand Title : A Method of Limiting Intermediate Volume Fraction in Iterative Two-Fluid Computations ‎(1)
expand Title : An Introduction to the CANDU Nuclear Energy Conversion System ‎(11)
expand Title : Canada's Power Reactor Fuel Bundle Design and Development ‎(1)
expand Title : Canadian Power Reactor Fuel ‎(1)
expand Title : Course 2.1 - Reactor Thermalhydraulics Design ‎(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 : 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 : 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 125, Nuclear Training Centre ‎(19)
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 : Memories of my Life as a Professional Engineer in the Royal Navy and the Canadian Boiler Industry ‎(1)
expand Title : Nuclear Heated Steam Generators ‎(1)
expand Title : Nuclear Journal of Canada, 1987 Vol 1 No. 3 ‎(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 : Pseudo-characteristic method of lines solution of first-order hyperbolic equation systems ‎(1)
expand Title : Reactor Boiler and Auxiliaries, Course 233, Nuclear Training ‎(21)
expand Title : Reactor Boiler and Auxiliaries, Course 433, Nuclear Training Centre ‎(10)
expand Title : Reactor Loops at Chalk River ‎(1)
expand Title : Reactor Thermalhydraulics Analysis, Course 2.3 ‎(18)
expand Title : Reactor Thermalhydraulics Analysis, Supplementary, Course 2.3a ‎(5)
expand Title : Reactor Thermalhydraulics Design, Course 2.1 ‎(10)
expand Title : Reactor, Boiler and Accessories, Course 233 ‎(24)
expand Title : Reactor, Boiler and Auxiliaries, Course 133, Nuclear Training Center ‎(29)
expand Title : Reactor, Boilers and Auxiliaries, Nuclear Training Course 133 ‎(13)
expand Title : Simulation Software ‎(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 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 : Two Phase Flow in Rod Bundles, ASSERT-4, Version 1 user's manual ‎(1)