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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 : Decay Heat Estimates for MNR ‎(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 : FORSIM a FORTRAN Oriented Simulation Package for the Automated Solution of Partial and Ordinary partial Differential Equation SYSTEMS ‎(1)
expand Title : Large LOCA Margins in CANDU Reactors - An Overview of the COG Report ‎(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 : 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 : 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-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)