Publications by Topic - Basic Equations
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expand Title : An Introduction to the CANDU Nuclear Energy Conversion System ‎(11)
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 1.1a - Nuclear Theory I (Statics), or Introduction to Nuclear Technology ‎(1)
expand Title : Course 1.3 - Introduction to Nuclear Reactor Kinetics ‎(1)
expand Title : Course 1.7 - Neutronic Analysis of Reactors ‎(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 : Course 3.1 - Introduction to Nuclear Reactor Engineering ‎(1)
expand Title : Decay Heat Estimates for MNR ‎(1)
expand Title : FORSIM a FORTRAN Oriented Simulation Package for the Automated Solution of Partial and Ordinary partial Differential Equation SYSTEMS ‎(1)
expand Title : Introduction to Nuclear Reactor Engineering, Course 3.1 ‎(2)
expand Title : Introduction to Nuclear Reactor Kinetics 1.3 ‎(8)
expand Title : Introduction to Reactor Physics ‎(2)
expand Title : Mathematics,  Nuclear Training Course 121 ‎(12)
expand Title : Mathematics, Course 221 ‎(21)
expand Title : NDP Systems - Reactor Boiler Control, Course T.T.0-5.637.1 ‎(1)
expand Title : Neutronic Analysis of Reactors, Course 1.7 ‎(17)
expand Title : Nuclear Journal of Canada, 1987 Vol 1 No. 3 ‎(1)
expand Title : Nuclear Theory I (Statics), or Introduction to Nuclear Technology 1.1a ‎(10)
expand Title : Numerical Solution of the Thermalhydraulic  Conservation Equations from Fundamental Concepts to Multidimensional Analysis ‎(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 : Reliability for Management and Professional Staff , Course PI 21, Nuclear Training Centre ‎(9)
expand Title : Simulation Software ‎(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)