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expandTitle : (1)
expandTitle : * How and Why is CANDU designed the way it is (1)
expandTitle : * The Essential CANDU (1)
expandTitle : A Reactor Cannot Explode Like a Nuclear Bomb (1)
expandTitle : A Short History of the CANDU Nuclear Power System (1)
expandTitle : ACR Presentation given to the US Nuclear Regulatory Commission on September 25-26, 2002 (15)
expandTitle : ACR-1000 Technical Description Summary (1)
expandTitle : AECL Lectures on Nuclear Power Symposium (16)
expandTitle : An Introduction to the CANDU Nuclear Energy Conversion System (11)
expandTitle : Basic Instrumentation and Control Course (9)
expandTitle : Canada's Power Reactor Fuel Bundle Design and Development (1)
expandTitle : CANDU Advanced Plutonium Burner - The Canadian Response to the ALWR (1)
expandTitle : CANDU Fundamentals (47)
expandTitle : CANDU Origins and Evolution (4)
expandTitle : CANDU Primary Heat Transfer System Heat Duty Diagram - analytic solution (1)
expandTitle : Chernobyl – A Canadian Perspective (1)
expandTitle : China Journal of Nuclear Power Engineering, 1999 Vol 20 No. 6 (16)
expandTitle : Concept Maps (1)
expandTitle : Corrosion for Engineers, Course 7.3 (12)
expandTitle : Course 1.1 - Nuclear Physics and Reactor Theory (1)
expandTitle : Course 1.1a - Nuclear Theory I (Statics), or Introduction to Nuclear Technology (1)
expandTitle : Course 1.2 - Nuclear Theory II (Kinetics) (1)
expandTitle : Course 1.3 - Introduction to Nuclear Reactor Kinetics (1)
expandTitle : Course 2.1 - Reactor Thermalhydraulics Design (1)
expandTitle : Course 2.3 - Reactor Thermalhydraulics Analysis (1)
expandTitle : Course 2.3a -Reactor Thermalhydraulics Analysis, Supplementary (1)
expandTitle : Course 3.1 - Introduction to Nuclear Reactor Engineering (1)
expandTitle : Course 3.5 - Nuclear Reactor Containment (1)
expandTitle : Course 3.6 - Reactor Mechanical Design (1)
expandTitle : Course 3.7 - Nuclear Reactor Safety Design, (1)
expandTitle : Course 5.1 - Radioactive Waste Management (1)
expandTitle : Course 5.2 - Natural Analogs for Nuclear Fuel Disposal (1)
expandTitle : Course 5.3 - Engineered Barriers for Fuel Disposal (1)
expandTitle : Course 5.4 - Hydrogeology of Nuclear Fuel Disposal (1)
expandTitle : Course 5.5 - Environmental Issues in Nuclear Fuel Disposal (1)
expandTitle : Course 5.6 - Nuclear Fuel Disposal Performance Assessment (1)
expandTitle : Course 6.1 - Radiation Processing (1)
expandTitle : Course 6.2 - Neutron Activation Analysis (1)
expandTitle : Course 7.2 - Non-Destructive Testing (1)
expandTitle : Course 7.3 - Corrosion for Engineers (1)
expandTitle : Course 7.5 - Welding Technology (1)
expandTitle : Decay Heat Estimates for MNR (1)
expandTitle : Electrical Course (6)
expandTitle : Engineered Barriers for Fuel Disposal, Course 5.3 (6)
expandTitle : Environmental Issues in Nuclear Fuel Disposal, Course 5.5 (5)
expandTitle : Evolution of CANDU Steam Generators – A Historical View (1)
expandTitle : Fluid Mechanics (2)
expandTitle : Fluid Mechanics, Nuclear Training Course 123, April 1978 (6)
expandTitle : Fluid Mechanics, Nuclear Training Course 223, December 1984 (3)
expandTitle : Fluid Mechanics, Nuclear Training Course 223, January 1977 (8)
expandTitle : Fretting Failures in Early Canadian Nuclear Steam Generators (1)
expandTitle : Fretting in Nuclear Steam Generators - A New Approach (1)
expandTitle : Fuel for the Next Millennia (1)
expandTitle : Fundamentals of Power Reactors (7)
expandTitle : Heat and Thermodynamics Course (3)
expandTitle : Heat and Thermodynamics, Course 1-2.5, Nuclear Electric GS Technical Training Course (2)
expandTitle : Heat and Thermodynamics, Course 125, Nuclear Training Centre (19)
expandTitle : Heat and Thermodynamics, Course 1A25, Nuclear Training Course (1)
expandTitle : Heat and Thermodynamics, Course 2-2.5, Nuclear Electric GS Technical Training Course (1)
expandTitle : Heat and Thermodynamics, Course 225, Nuclear Training Centre (10)
expandTitle : Heat and Thermodynamics, Course PI 25, Nuclear Training Centre (11)
expandTitle : Heavy Water Reactors: Status and Projected Development, Technical Report Series No. 407, IAEA, Vienna, Austria, 2002. (5)
expandTitle : Hydrogeology of Nuclear Fuel Disposal, Course 5.4 (3)
expandTitle : Intermediate Reactors, Boilers and Auxiliaries (1)
expandTitle : Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 (6)
expandTitle : Introduction to Nuclear Reactor Engineering, Course 3.1 (2)
expandTitle : Introduction to Nuclear Reactor Kinetics 1.3 (8)
expandTitle : Introduction to Reactor Physics (2)
expandTitle : Lecture Presentations on Heavy Water Reactors at 2010 Frederic Joliot / Otto Hahn Summer School (FJOHSS) on Nuclear Reactors held in Aix-en-Provence, France, August 25 to September 3, 2010 (4)
expandTitle : Materials Course (5)
expandTitle : Materials, Nuclear Training Course 228 (6)
expandTitle : Mathematics,  Nuclear Training Course 121 (12)
expandTitle : Mathematics, Course 221 (21)
expandTitle : Mécanique des Fluides (1)
expandTitle : Mechanical Equipment Course (5)
expandTitle : Mechanical Equipment, Course 23001 (4)
expandTitle : Mechanical Equipment, Course PI 30.1, Nuclear Training Centre (26)
expandTitle : Memories of my Life as a Professional Engineer in the Royal Navy and the Canadian Boiler Industry (1)
expandTitle : Natural Analogs for Nuclear Fuel Disposal, Course 5.2 (10)
expandTitle : NDP Systems - Reactor Boiler Control, Course T.T.0-5.637.1 (1)
expandTitle : Neutron Activation Analysis, Course 6.2 (23)
expandTitle : Non-Destructive Testing, Course 7.2 (7)
expandTitle : NPD Generatig Station Index (1)
expandTitle : Nuclear Fuel Disposal Performance Assessment, Course 5.6 (4)
expandTitle : Nuclear Heated Steam Generators (1)
expandTitle : Nuclear Journal of Canada, 1987 Vol 1 No. 1 (3)
expandTitle : Nuclear Journal of Canada, 1987 Vol 1 No. 2 (3)
expandTitle : Nuclear Journal of Canada, 1987 Vol 1 No. 3 (2)
expandTitle : Nuclear Journal of Canada, 1987 Vol 1 No. 4 (3)
expandTitle : Nuclear Physics and Reactor Theory 1.1 (16)
expandTitle : Nuclear Reactor Containment, Course 3.5 (8)
expandTitle : Nuclear Reactor Safety Design, Course 3.7 (24)
expandTitle : Nuclear Theory I (Statics), or Introduction to Nuclear Technology 1.1a (10)
expandTitle : Nuclear Theory II (Kinetics) 1.2 (13)
expandTitle : Nuclear Theory, Course 127, Nuclear Training Centre (22)
expandTitle : Nuclear Theory, Course 227, Nuclear Training Centre (34)
expandTitle : Nuclear Theory, Course 227, Nuclear Training Centre 20053700 (1)
expandTitle : Nuclear Theory, Course 427, Nuclear Training Centre (15)
expandTitle : Nuclear Theory, Course PI 27 , Nuclear Training Centre (17)
expandTitle : Nuclear Theory, Nuclear Training Course 227 (18)
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