|
 Title : A Method of Limiting Intermediate Volume Fraction in Iterative Two-Fluid Computations (1) | | Title : Canada's Power Reactor Fuel Bundle Design and Development (1) | | Title : Canadian Power Reactor Fuel (1) | | Title : CANDU Primary Heat Transfer System Heat Duty Diagram - analytic solution (1) | | Title : CANDU Primary Heat Transfer System Heat Duty Diagram - numeric solution (1) | | Title : Carver, M.B. - Selected Papers and Reports (1) | | Title : Course 2.2 - Thermal Study of Nuclear Reactors (1) | | Title : Course 2.3 - Reactor Thermalhydraulics Analysis (1) | | Title : Course 2.3a -Reactor Thermalhydraulics Analysis, Supplementary (1) | | Title : Course 3.6 - Reactor Mechanical Design (1) | | Title : Course 7.2 - Non-Destructive Testing (1) | | Title : Course 7.5 - Welding Technology (1) | | Title : Development and Application of a Three-Dimensional Two-Fluid Numerical Algorithm for Simulation of Phase Redistribution by Bends and Obstructions (1) | | Title : Dyke, J.M. - Selected Works (1) | | Title : Efficient Integration over Discontinuities in Ordinary Differential Equation Simulation (1) | | Title : Evolution of CANDU Steam Generators – A Historical View (1) | | Title : Fluid Mechanics (2) | | Title : Fluid Mechanics, Nuclear Training Course 123, April 1978 (6) | | Title : Fluid Mechanics, Nuclear Training Course 223, December 1984 (3) | | Title : Fluid Mechanics, Nuclear Training Course 223, January 1977 (8) | | Title : FORSIM a FORTRAN Oriented Simulation Package for the Automated Solution of Partial and Ordinary partial Differential Equation SYSTEMS (1) | | Title : Fretting Failures in Early Canadian Nuclear Steam Generators (1) | | Title : Fretting in Nuclear Steam Generators - A New Approach (1) | | Title : Heat and Thermodynamics Course (3) | | Title : Heat and Thermodynamics, Course 1-2.5, Nuclear Electric GS Technical Training Course (2) | | Title : Heat and Thermodynamics, Course 125, Nuclear Training Centre (19) | | Title : Heat and Thermodynamics, Course 1A25, Nuclear Training Course (1) | | Title : Heat and Thermodynamics, Course 2-2.5, Nuclear Electric GS Technical Training Course (1) | | Title : Heat and Thermodynamics, Course 225, Nuclear Training Centre (10) | | Title : Heat and Thermodynamics, Course PI 25, Nuclear Training Centre (11) | | Title : Mécanique des Fluides (1) | | Title : Mechanical Equipment Course (5) | | Title : Mechanical Equipment, Course 23001 (4) | | Title : Mechanical Equipment, Course PI 30.1, Nuclear Training Centre (26) | | Title : Memories of my Life as a Professional Engineer in the Royal Navy and the Canadian Boiler Industry (1) | | Title : NDP-2 Systems - Calandria Assembly, Course T.T.01-312 (1) | | Title : Non-Destructive Testing, Course 7.2 (7) | | Title : NPD Systems - Fuel Handling System, Course 053 (1) | | Title : Nuclear Heated Steam Generators (1) | | Title : Nuclear Journal of Canada, 1987 Vol 1 No. 2 (1) | | Title : Nuclear Journal of Canada, 1987 Vol 1 No. 3 (1) | | Title : Nuclear Journal of Canada, 1987 Vol 1 No. 4 (2) | | Title : Numerical Solution of the Thermalhydraulic Conservation Equations from Fundamental Concepts to Multidimensional Analysis (1) | | Title : Principes de Science et de Fonctionnement des Réacteurs - Chaleur et Thermodynamique (1) | | Title : Principes de Science et de Fonctionnement des Réacteurs - Équipement Mécanique (1) | | Title : Pseudo-characteristic method of lines solution of first-order hyperbolic equation systems (1) | | Title : Reactor Mechanical Design, Course 3.6 (18) | | Title : Reactor Thermalhydraulics Analysis, Course 2.3 (18) | | Title : Reactor Thermalhydraulics Analysis, Supplementary, Course 2.3a (5) | | Title : Simulation Software (1) | | Title : Single Phase Friction Factors for MNR Thermalhydraulic Modelling (1) | | Title : Software Quality Assurance: Practical Procedures to Meet CSA Standards (1) | | Title : Steam Generators for CANDU, Engineering Memoirs (1) | | Title : The Effect of Bypass Characteristics on Parallel Channel Flow Instabilities (1) | | Title : The method of lines and the advective equation (1) | | Title : The Pressurized Water Reactor as a Source of Heat for Steam Power Plants (1) | | Title : The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators (1) | | Title : The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators - Associated Presentation (1) | | Title : Thermal Study of Nuclear Reactors, Course 2.2 (10) | | Title : Thermal-Hydraulics in Recirculating Steam Generators: Thirst Code User's Manual (1) | | Title : Turbine and Auxiliaries, Course PI 34 / TIMS Ref. PI 3004, Nuclear Training Centre (22) | | Title : Turbine and Auxiliaries, Nuclear Training Course 234 (15) | | Title : Turbine, Generator and Auxiliaries, Course 1-3.4, Nuclear Electric GS Technical Training Course (1) | | Title : Turbine, Generator and Auxiliaries, Course 134, Nuclear Training Centre (9) | | Title : Turbine, Generator and Auxiliaries, Course 2-3.4, Nuclear Electric GS Technical Training Course (1) | | Title : Turbine, Generator and Auxiliaries, Course 3-3.4, Nuclear Electric GS Technical Training Course (1) | | Title : Turbine, Generator and Auxiliaries, Course 4-3.4, Nuclear Electric GS Technical Training Course (1) | | Title : Two Dimensional Modelling of the Homogenizing Effects of Flow Obstructions in Two Fluid Flow (1) | | Title : Two Phase Flow in Rod Bundles, ASSERT-4, Version 1 user's manual (1) | | Title : Welding Technology, Course 7.5 (34) |
|
