Publications by System - 33100 Main Heat Transport System
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expand Title : A Method of Limiting Intermediate Volume Fraction in Iterative Two-Fluid Computations ‎(1)
expand Title : CANDU fuel channel 1-D temperature calculation ‎(1)
expand Title : CANDU Origins and Evolution ‎(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 : 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 : Efficient Integration over Discontinuities in Ordinary Differential Equation Simulation ‎(1)
expand Title : Large LOCA Margins in CANDU Reactors - An Overview of the COG Report ‎(1)
expand Title : MACKSIMA-CHEMIST a Program for Mass Action Kinetics Simulation by Automatic Chemical Equation Manipulation and Integration using Stiff techniques ‎(1)
expand Title : Nuclear Journal of Canada, 1987 Vol 1 No. 2 ‎(2)
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 : Numerical Solution of the Thermalhydraulic  Conservation Equations from Fundamental Concepts to Multidimensional Analysis ‎(1)
expand Title : Power Reactor Safety Comparison - A Limited Review ‎(1)
expand Title : Pseudo-characteristic method of lines solution of first-order hyperbolic equation systems ‎(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 : 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 : 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)