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expand Title :  ‎(1)
expand Title : * The Essential CANDU ‎(1)
expand Title : A Method of Limiting Intermediate Volume Fraction in Iterative Two-Fluid Computations ‎(1)
expand Title : A Reactor Cannot Explode Like a Nuclear Bomb ‎(1)
expand Title : A Short History of the CANDU Nuclear Power System ‎(1)
expand Title : ACR Presentation given to the US Nuclear Regulatory Commission on September 25-26, 2002 ‎(15)
expand Title : ACR-1000 Technical Description Summary ‎(1)
expand Title : AECL Lectures on Nuclear Power Symposium ‎(16)
expand Title : An Introduction to the CANDU Nuclear Energy Conversion System ‎(11)
expand Title : Basic Course for Radiation Surveyors and Contamination Monitors of the Radiation and Industrial Safety Branch ‎(1)
expand Title : Basic Instrumentation and Control Course ‎(9)
expand Title : Canada's Nuclear Achievement: Technical and Economic Perspectives ‎(1)
expand Title : Canada's Power Reactor Fuel Bundle Design and Development ‎(1)
expand Title : Canadian Power Reactor Fuel ‎(1)
expand Title : CANDU 6 Technical Summary ‎(1)
expand Title : CANDU Advanced Plutonium Burner - The Canadian Response to the ALWR ‎(1)
expand Title : CANDU fuel channel 1-D temperature calculation ‎(1)
expand Title : CANDU Fuel Management Course ‎(19)
expand Title : CANDU Fundamentals ‎(47)
expand Title : CANDU Overiew, Course 3.2 ‎(13)
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 : CANDU Safety - presentations in Shanghai, 1999 ‎(26)
expand Title : CANTEACH Flyer ‎(1)
expand Title : Chemistry Control Requirements for Generic CANDU Power Stations ‎(13)
expand Title : Chemistry, Course PI 24 ‎(30)
expand Title : Chemistry, Nuclear Training Course 224 ‎(6)
expand Title : Chernobyl – A Canadian Perspective ‎(1)
expand Title : China Journal of Nuclear Power Engineering, 1999 Vol 20 No. 6 ‎(16)
expand Title : Commissioning and Operating Experience with Canadian Nuclear Electric Stations ‎(1)
expand Title : Concept Maps ‎(1)
expand Title : Construction of CANDU® in China. A China–Canada Success Story ‎(1)
expand Title : Corrosion for Engineers, Course 7.3 ‎(12)
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 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 3.2 - CANDU Overiew ‎(1)
expand Title : Course 3.3 - Reactor Control & Simulation ‎(1)
expand Title : Course 3.4 - Nuclear Power Plant Control & Simulaion  ‎(1)
expand Title : Course 3.5 - Nuclear Reactor Containment ‎(1)
expand Title : Course 3.6 - Reactor Mechanical Design ‎(1)
expand Title : Course 3.7 - Nuclear Reactor Safety Design,  ‎(1)
expand Title : Course 4.1 - Reactor Licensing & Siting ‎(1)
expand Title : Course 4.2 - Radiation Protection ‎(1)
expand Title : Course 4.3 - Principles of Nuclear Safety ‎(1)
expand Title : Course 4.4 - Operation & Maintenance of a Nuclear Power Plant  ‎(1)
expand Title : Course 4.5 - Peer Evaluation Techniques ‎(1)
expand Title : Course 5.1 - Radioactive Waste Management ‎(1)
expand Title : Course 5.2 - Natural Analogs for Nuclear Fuel Disposal ‎(1)
expand Title : Course 5.3 - Engineered Barriers for Fuel Disposal ‎(1)
expand Title : Course 5.4 - Hydrogeology of Nuclear Fuel Disposal ‎(1)
expand Title : Course 5.5 - Environmental Issues in Nuclear Fuel Disposal ‎(1)
expand Title : Course 5.6 - Nuclear Fuel Disposal Performance Assessment ‎(1)
expand Title : Course 6.1 - Radiation Processing ‎(1)
expand Title : Course 6.2 - Neutron Activation Analysis  ‎(1)
expand Title : Course 7.2 - Non-Destructive Testing  ‎(1)
expand Title : Course 7.3 - Corrosion for Engineers ‎(1)
expand Title : Course 7.4 - Digital Instrumentation & Control ‎(1)
expand Title : Course 7.5 - Welding Technology ‎(1)
expand Title : Decay Heat Estimates for MNR ‎(1)
expand Title : Design and Safety of Canadian Nuclear Reactors ‎(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 : Digital Instrumentation & Control, Course 7.4 ‎(41)
expand Title : Do the Universities Prepare the Type of Engineers that our Nuclear Industry Needs ‎(1)
expand Title : Douglas Point Project ‎(1)
expand Title : Dyke, J.M. - Selected Works  ‎(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 : Electrical Course ‎(6)
expand Title : Electrical Equipment, Course 230.2, Nuclear Training Center ‎(23)
expand Title : Electrical Equipment, Course PI 30.2, Nuclear Training Center ‎(17)
expand Title : Electrical Systems, Course 135, Nuclear Training  Centre ‎(7)
expand Title : Electrical Systems, Course 235 ‎(10)
expand Title : Engineered Barriers for Fuel Disposal, Course 5.3 ‎(6)
expand Title : Environmental Issues in Nuclear Fuel Disposal, Course 5.5 ‎(5)
expand Title : Evolution of CANDU Steam Generators – A Historical View ‎(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 : Fretting Failures in Early Canadian Nuclear Steam Generators ‎(1)
expand Title : Fretting in Nuclear Steam Generators - A New Approach ‎(1)
expand Title : Fuel for the Next Millennia ‎(1)
expand Title : Fundamentals of CANDU Reactor Nuclear Design (TDAI-244) ‎(7)
expand Title : Fundamentals of Power Reactors ‎(7)
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 225, Nuclear Training Centre ‎(10)
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