Publications by Phase - Design Analysis
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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 : AECL Lectures on Nuclear Power Symposium ‎(16)
expand Title : CANDU fuel channel 1-D temperature calculation ‎(1)
expand Title : CANDU Fuel Management Course ‎(19)
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 : Course 1.1 - Nuclear Physics and Reactor Theory ‎(1)
expand Title : Course 1.1a - Nuclear Theory I (Statics), or Introduction to Nuclear Technology ‎(1)
expand Title : Course 1.2 - Nuclear Theory II (Kinetics) ‎(1)
expand Title : Course 1.3 - Introduction to Nuclear Reactor Kinetics ‎(1)
expand Title : Course 1.4 - Reactor Physics & Fuelling Strategies ‎(1)
expand Title : Course 1.5 - Reactor Core Analysis & Fuel Management ‎(1)
expand Title : Course 1.6 - Monte Carlo Method for Particle Transport Simulation  ‎(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 : Effects Contributing to Positive Coolant Void Reactivity in CANDU ‎(1)
expand Title : Efficient Integration over Discontinuities in Ordinary Differential Equation Simulation ‎(1)
expand Title : Fast Reactor Kinetics - The QXI Code ‎(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 : Fundamentals of CANDU Reactor Nuclear Design (TDAI-244) ‎(5)
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 : Introduction to Nuclear Reactor Kinetics 1.3 ‎(8)
expand Title : Introduction to Reactor Physics ‎(2)
expand Title : MACKSIMA-CHEMIST a Program for Mass Action Kinetics Simulation by Automatic Chemical Equation Manipulation and Integration using Stiff techniques ‎(1)
expand Title : Mécanique des Fluides ‎(1)
expand Title : Monte Carlo Method for Particle Transport Simulation, Course 1.6 ‎(24)
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 ‎(1)
expand Title : Nuclear Physics and Reactor Theory 1.1 ‎(16)
expand Title : Nuclear Theory I (Statics), or Introduction to Nuclear Technology 1.1a ‎(10)
expand Title : Nuclear Theory II (Kinetics) 1.2 ‎(13)
expand Title : Nuclear Theory, Course 127, Nuclear Training Centre ‎(22)
expand Title : Nuclear Theory, Course 227, Nuclear Training Centre ‎(34)
expand Title : Nuclear Theory, Course 227, Nuclear Training Centre 20053700 ‎(1)
expand Title : Nuclear Theory, Course 427, Nuclear Training Centre ‎(15)
expand Title : Nuclear Theory, Course PI 27 , Nuclear Training Centre ‎(17)
expand Title : Nuclear Theory, Nuclear Training Course 227 ‎(18)
expand Title : Nuclear Theory, Nuclear Training Course 227 20031001 ‎(1)
expand Title : Numerical Solution of the Thermalhydraulic  Conservation Equations from Fundamental Concepts to Multidimensional Analysis ‎(1)
expand Title : Point kinetics simulation ‎(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 Core Analysis & Fuel Management, Course 1.5 ‎(6)
expand Title : Reactor Physics & Fuelling Strategies 1.4 ‎(16)
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 : RFSP Training Course ‎(12)
expand Title : Simulation Software ‎(1)
expand Title : Software Quality Assurance: Practical Procedures to Meet CSA Standards ‎(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 : 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 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 : Xenon and iodine kinetics simulation ‎(1)