Publications by System - 36000 Steam Generator Steam and Water Systems
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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 : 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 : 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 : MACKSIMA-CHEMIST a Program for Mass Action Kinetics Simulation by Automatic Chemical Equation Manipulation and Integration using Stiff techniques ‎(1)
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. 1 ‎(1)
expand Title : Nuclear Journal of Canada, 1987 Vol 1 No. 2 ‎(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 : 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 : Steam Generators for CANDU, Engineering Memoirs ‎(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-Hydraulics in Recirculating Steam Generators: Thirst Code User's Manual ‎(1)