Publications by Phase - Design
Type
  
Name
  
Subtitle
  
Content Author
  
Published Date
  
Organization
  
Document Type
  
SI
  
Discipline
  
Topic
  
Audience/Level
  
Summary
File Size
  
expand Title :  ‎(1)
expand Title : * How and Why is CANDU designed the way it is ‎(1)
expand Title : * The Essential CANDU ‎(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 Power Reactor Fuel Bundle Design and Development ‎(1)
expand Title : CANDU 6 Technical Summary ‎(1)
expand Title : CANDU Fundamentals ‎(47)
expand Title : CANDU Origins and Evolution ‎(5)
expand Title : CANDU Safety - presentations in Shanghai, 1999 ‎(26)
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 : 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 3.1 - Introduction to Nuclear Reactor Engineering ‎(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 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 7.2 - Non-Destructive Testing  ‎(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 : Digital Instrumentation & Control, Course 7.4 ‎(41)
expand Title : Douglas Point Project ‎(1)
expand Title : Dyke, J.M. - Selected Works  ‎(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 : 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) ‎(5)
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 2-2.5, Nuclear Electric GS Technical Training Course ‎(1)
expand Title : Heat and Thermodynamics, Course 225, Nuclear Training Centre ‎(10)
expand Title : Heat and Thermodynamics, Course PI 25, Nuclear Training Centre ‎(11)
expand Title : Heavy Water Reactors: Status and Projected Development, Technical Report Series No. 407, IAEA, Vienna, Austria, 2002. ‎(5)
expand Title : Hydrogeology of Nuclear Fuel Disposal, Course 5.4 ‎(3)
expand Title : IAEA CANDU Instrumentation & Control Course ‎(10)
expand Title : Instrumentation and Control, Course 136 ‎(6)
expand Title : Intermediate Reactors, Boilers and Auxiliaries ‎(1)
expand Title : Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 ‎(6)
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 : 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)
expand Title : Materials Course ‎(5)
expand Title : Materials, Nuclear Training Course 228 ‎(6)
expand Title : Mécanique des Fluides ‎(1)
expand Title : Mechanical Equipment Course ‎(5)
expand Title : Mechanical Equipment, Course 23001 ‎(4)
expand Title : Mechanical Equipment, Course PI 30.1, Nuclear Training Centre ‎(26)
expand Title : Memories of my Life as a Professional Engineer in the Royal Navy and the Canadian Boiler Industry ‎(1)
expand Title : Monte Carlo Method for Particle Transport Simulation, Course 1.6 ‎(24)
expand Title : Natural Analogs for Nuclear Fuel Disposal, Course 5.2 ‎(10)
expand Title : NDP Systems - I&C General - Annunciation, Course T.T.0-5.603 ‎(1)
expand Title : NDP Systems - Reactor Boiler Control, Course T.T.0-5.637.1 ‎(1)
expand Title : NDP-2 Systems - Calandria Assembly, Course T.T.01-312 ‎(1)
expand Title : NDP-2 Systems - Moderator, Course T.T.4-4.320 ‎(1)
expand Title : NDP-2 Systems - Reactor, Course T.T.4-5.310 ‎(1)
expand Title : Neutronic Analysis of Reactors, Course 1.7 ‎(17)
1 - 100Next