Jump to year -> [1950-01-01] [1965-01-01] [1969-01-02] [1972-05-25] [1975-07-01] [1978-08-01] [1980-04-01] [1981-07-01] [1987-09-01] [1990-01-01] [1995-08-01] [1996-02-01] [1997-01-01] [1998-02-01] [1999-02-23] [2002-09-01] [2004-07-17]
[Topic]: Basic Equations Documents

Documents below are listed chronologically. Use the links on the left or below to filter documents by keyword. Use the links above to jump to a specific year on this page.

Number of files: 153

    1950-01-01---------Jump to [Top]
  1. Simulation Software, by Wm.J. Garland, McMaster University, 1950-01-01. Doc type: Essay.
    Summary: Major endeavours such as a CANDU nuclear power plant involves extensive engineering calculations usually performed using large simulation tools.  However, to aid in conceptual BOE (back of envelope) evaluations and for education and training exercises, simplified and focused calculations are often done.  To aid students and working professional alike, a few such small tools (primarily spreadsheets) are linked below.  Go to Topics: Modelling to see the full list.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor Steam Generators and Auxiliaries [Discipline] General Engineering Mechanical Engineering Nuclear Engineering [Topic] Basic Equations Conceptual Heat Transfer Modelling Process Systems Reactor Physics Thermalhydraulics [Phase] Concept Design Analysis [Audience] College Engineer Grad Technician Ugrad
    - SimulationSoftware.pdf (267 kb)
    2. 1965-01-01---------Jump to [Top]
  2. NDP Systems - Reactor Boiler Control, Course T.T.0-5.637.1, by S.G. Horton, OPG, 1965-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Basic Equations Physical Description Process Systems [Phase] Concept Design Operation [Audience] College Engineer Technician Ugrad
    - Reactor Boiler Regulating System NPD-TT-0-5-637-1-1965.pdf (1542 kb)
    3. 1969-01-02---------Jump to [Top]
  3. The Effect of Bypass Characteristics on Parallel Channel Flow Instabilities, by M.B. Carver, AECL, 1969-01-02. Doc type: Paper.
    Summary: This article is definitive because nobody could figure out why all the instability codes gave stability thresholds well below the measured threshold power in the experiments done at Canadian Westinghouse. The paper determines analytically that this is because the small bypass stabilized the experimental system as it could not maintain a constant pressure drop, which all the codes assumed at step 1.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics Mechanical Engineering [Topic] Basic Equations Collections Conceptual Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Proceedings of the Institution of Mechanical Engineers, Volume 184, 1969 BYPASS PIME_CONF_1969_184_083_02.pdf (703 kb)
    4. 1972-05-25---------Jump to [Top]
  4. An Introduction to the CANDU Nuclear Energy Conversion System, by Archie Harms, McMaster University, 1972-05-25. Doc type: Book.
    Summary:
    Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Nuclear Engineering [Topic] Basic Equations Conceptual Intro and Overview Reactor Physics Thermalhydraulics [Phase] Concept Design Safety [Audience] College Engineer Technician Ugrad
    - Table of Contents and Chapter 1: Introduction 19750101.pdf (622 kb)
    - Chapter 2: Nuclear Processes, by Archie Harms, 19750102.pdf (493 kb)
    - Chapter 3: Neutron Physics, by Archie Harms, 19750103.pdf (567 kb)
    - Chapter 4: Reactor Statics, by Archie Harms, 19750104.pdf (650 kb)
    - Chapter 5: Reactor Dynamics, by Archie Harms, 19750105.pdf (428 kb)
    - Chapter 6: Control and Operations, by Archie Harms, 19750106.pdf (499 kb)
    - Chapter 7: Thermal-hydraulic Analysis, by Archie Harms, 19750107.pdf (439 kb)
    - Chapter 8: Nuclear Reactor Materials, by Archie Harms, 19750108.pdf (781 kb)
    - Chapter 9: Safety Analysis, by Archie Harms, 19750109.pdf (152 kb)
    - Chapter 10: CANDU Reactors part 1, by Archie Harms, 19750110.pdf (764 kb)
    - Chapter 10: CANDU Reactors part 2, by Archie Harms, 19750111.pdf (686 kb)
    5. 1975-07-01---------Jump to [Top]
  5. FORSIM a FORTRAN Oriented Simulation Package for the Automated Solution of Partial and Ordinary partial Differential Equation SYSTEMS, by M.B. Carver, AECL, 1975-07-01. Doc type: Report.
    Summary: FORSIM was Mike's vehicle for all the work he did in PDEs/ODEs including stiff equation solvers, reactor kinetics and mass action chemical kinetics, sparse matrix approximation to the Jacobian, integration over discontinuities, and parameter identification. In about a dozen PPV papers. FORSIM started as just an ODE simulator to replace MIMIC for the AECL Sheridan Park engineers.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries 32000 Moderator System 33000 Primary Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics Mechanical Engineering [Topic] Basic Equations Collections Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - AECL 4608, November 1973 FORSIM_AECL4608.pdf (538 kb)
    6. 1978-08-01---------Jump to [Top]
  6. The method of lines and the advective equation, by M.B. Carver and H.W. Hinds, AECL, 1978-08-01. Doc type: Paper.
    Summary: This article showed that the common approach of first order differencing, used in almost all thermalhydraulic computer programs, would not properly solve the simplest hyperbolic PDE on the market. Despite the errata, it is Carver's most cited publication and laid the foundations for many higher order analyses by others, and Carver's pseudo-characteristic method of lines (PCMOL) solution of the thermalhydraulic conservation equations.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Basic Equations Modelling Process Systems Thermalhydraulics [Phase] Concept Design Analysis Safety Analysis [Audience] Engineer Grad
    - Simulation, August,1978. Also published as AECL 6155 AdvectiveEqn.pdf (804 kb)
    7. 1980-04-01---------Jump to [Top]
  7. Mathematics, Course 221, OPG, 1980-04-01. Doc type: Course.
    Summary: This course proves an introduction to two topics: equipment reliability evaluation, and calculus.
    Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept Operation [Audience] Engineer Manager
    - Full Course 20043000.pdf (3593 kb)
    - 221.00-1 Index and Objectives, 20043001.pdf (124 kb)
    - 221.00-2 Indroduction, 20043002.pdf (132 kb)
    - 421.10-4 Standard Notation, 20043003.pdf (122 kb)
    - 421.20-1 Algebra Fundamentals, 20043004.pdf (239 kb)
    - 421.40-1 Graphs, 20043005.pdf (153 kb)
    - 421.40-2 Graphing Functions, 20043006.pdf (80 kb)
    - 321.10-3 Logarithms and Exponentials, 20043007.pdf (210 kb)
    - 321.10-4 Use of Logarithmic Scaled Graph Paper, 20043008.pdf (347 kb)
    - 221.10-1 Basic Reliability Concepts, 20043009.pdf (154 kb)
    - 221.20-1 The Straight Line, 20043010.pdf (166 kb)
    - 221.20-2 The Derivative, 20043011.pdf (259 kb)
    - 221.20-3 Simple Applications of Derivatives, 20043012.pdf (127 kb)
    - 221.20-4 Differentiating Exponential Functions, 20043013.pdf (193 kb)
    - 221.20-5 The Derivative in Science and Technology, 20043014.pdf (213 kb)
    - 221.30-1 The Integral, 20043015.pdf (194 kb)
    - 221.30-2 Application of the Integral as an Infinite Sum, 20043016.pdf (371 kb)
    - 221.40-1 Appendix 1 : Review Exercises, 20043017.pdf (202 kb)
    - 221.40-2 Appendix 2 : Questions Bearing Directly on Course 221 Content from Recent AECB Nuclear General Examinations, 20043018.pdf (75 kb)
    - 221.40-3 Appendix 3 : Solving Quadratic Equations, 20043019.pdf (84 kb)
    - 221.40-4 Answers to Assignments and Review Exercises, 20043020.pdf (268 kb)
    8. 1981-07-01---------Jump to [Top]
  8. Mathematics, Nuclear Training Course 121, OPG, 1981-07-01. Doc type: Course.
    Summary: Probability and reliability concepts applied to station operation.
    Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept [Audience] Engineer Manager
    - Cover page, Table of contents, Objectives 20040101.pdf (167 kb)
    - Introduction, 20040102.pdf (194 kb)
    - Probability, 20040103.pdf (610 kb)
    - Safety Systems Analysis, 20040104.pdf (404 kb)
    - Safety Systems Analysis - Solutions to Sample Problems, 20040105.pdf (455 kb)
    - The Binomial Distribution and Power System Reliability, 20040106.pdf (302 kb)
    - The Normal Distribution and Applications, 20040107.pdf (193 kb)
    - Basic Reliability Concepts, 20040108.pdf (638 kb)
    - Operation in the Wearout Mode, 20040109.pdf (237 kb)
    - Some Modern Reliability Topics, 20040110.pdf (634 kb)
    - Appendix 1: Confidence Limits, 20040111.pdf (219 kb)
    - Appendix 2: Solutions to Assignments, 20040112.pdf (636 kb)
    9. 1987-09-01---------Jump to [Top]
  9. Nuclear Journal of Canada, 1987 Vol 1 No. 3, by S. Banerjee, CNS-, 1987-09-01. Doc type: Paper.
    Summary: The multifield model, in which separate sets of conservation equations are written for each phase, or clearly identifiable portion of a phase, is derived and explored.
    Keywords: [Concept] Thermalhydraulics [SI] 03000 Engineering Science and Technology [Discipline] Mechanical Engineering [Topic] Basic Equations Modelling Thermalhydraulics [Phase] Design Analysis [Audience] Engineer Grad
    - Multifield Methods for Nuclear Thermalhydraulics Problems NJC-1-3-04.pdf (1030 kb)
    10. 1990-01-01---------Jump to [Top]
  10. Reliability for Management and Professional Staff , Course PI 21, Nuclear Training Centre, OPG, 1990-01-01. Doc type: Course.
    Summary: A six part introductory reliability course for management and professional staff.
    Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept Operation [Audience] Engineer Manager
    - Full Course 20043300.pdf (1585 kb)
    - Course Table of Contents, 20043301.pdf (219 kb)
    - PI 21.00 Intro to the Course, 20043302.pdf (104 kb)
    - PI 21.01 An Introduction to Reliability, 20043303.pdf (166 kb)
    - PI 21.02 Reliability Concepts, 20043304.pdf (384 kb)
    - PI 21.03 Process Systems, 20043305.pdf (185 kb)
    - PI 21.04 Availability of Safety Systems, 20043306.pdf (250 kb)
    - PI 21.05 Modern Reliability Techniques, 20043307.pdf (208 kb)
    - PI 21.06 Reporting and Administration, 20043308.pdf (111 kb)
    11. 1995-08-01---------Jump to [Top]
  11. Numerical Solution of the Thermalhydraulic Conservation Equations from Fundamental Concepts to Multidimensional Analysis, by M.B. Carver, , 1995-08-01. Doc type: Report.
    Summary: This material was presented as part of a short course in Two-Phase Flow and Heat Transfer at McMaster University and is documented in report form for further reference. The discussion briefly establishes some requisite concepts of differential equation theory, and applies these to describe methods for numerical solution of the thennalhydraulic conservation equations in their various forms. The intent is to cover the general methodology without obscuring the principles with details. As a short overview of computational thermalhydraulics, the material provides an introductory foundation, so that those working on the application of thennalhydraulic codes can begin to understand the many intricacies involved without having to locate and read the references given. Those intending to work in code development will need to read and understand all the references.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Basic Equations Collections Conceptual Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Grad
    - AECL-11387, ARD-TD-550, Revision 1 (2017) to the original (1995) Carver AECL-11387[3628]-WithAddendum.pdf (6457 kb)
    12. 1996-02-01---------Jump to [Top]
  12. Introduction to Nuclear Reactor Kinetics 1.3, by Daniel Rozon, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: Predicting the evolution in time of the neutron population in a multiplying medium. Time variation of the reactor power (proportional to the total neutron population) is presented.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Table of Contents 20041800.pdf (31 kb)
    - Chapter 1 - Neutron/Nucleus Interactions and Fission, by Daniel Rozon, 20041801.pdf (1008 kb)
    - Chapter 2 - The Diffusion Equation and the Steady State, by Daniel Rozon, 20041802.pdf (1840 kb)
    - Chapter 3 - The Point Kinetics Equation, by Daniel Rozon, 20041803.pdf (1190 kb)
    - Workbook to Chapter 1 - Neutron/Nucleus Interactions and Fission, by Daniel Rozon, 20041804.pdf (447 kb)
    - Workbook to Chapter 2 - The Diffusion Equation and the Steady State, by Daniel Rozon, 20041805.pdf (709 kb)
    - Workbook to Chapter 3 - The Point Kinetics Equations, by Daniel Rozon, 20041806.pdf (385 kb)
    - Workbook to Chapter 4 - Elementary Solutions to the Kinetics Equations, by Daniel Rozon, 20041807.pdf (398 kb)
    - Workbook to Chapter 5 - Approximate Solutions for Reactivity Ramps, by Daniel Rozon, 20041808.pdf (276 kb)
  13. Reactor Thermalhydraulics Design, Course 2.1, by Wm.J. Garland, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: This course is concerned with the thennalhydraulic design of the process systems that are required to transport heat energy away from the nuclear reactor source and transform this heat energy into useful work (generally electrical energy).
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Basic Equations Important Parameters Process Systems Thermalhydraulics [Phase] Concept Design Design Analysis Design Evolution Design Process [Audience] Engineer Ugrad
    - Title and Table of Contents 20043701.pdf (170 kb)
    - Foreword and Glossary, by Wm.J. Garland, 20043702.pdf (74 kb)
    - Chapter 1 - Introduction, by Wm.J. Garland, 20043703.pdf (130 kb)
    - Chapter 2 - Design Requirements and Engineering Considerations, by Wm.J. Garland, 20043704.pdf (1189 kb)
    - Chapter 3 - Heat Transport System Thermalhydrauilics, by Wm.J. Garland, 20043705.pdf (447 kb)
    - Chapter 4 - Thermodynamics, by Wm.J. Garland, 20043706.pdf (309 kb)
    - Chapter 5 - Fuel Coolant Heat Transfer, by Wm.J. Garland, 20043707.pdf (245 kb)
    - Chapter 6 - Control, by Wm.J. Garland, 20043708.pdf (313 kb)
    - Chapter 7 - The Design Process, by Wm.J. Garland, 20043709.pdf (419 kb)
    - Chapter 8 - Process Design and Optimization, by Wm.J. Garland, 20043710.pdf (441 kb)
    - Appendix 1 - Comparison of Bruce A, B, & Darlington, by Wm.J. Garland, 20043711.pdf (223 kb)
  14. Thermal Study of Nuclear Reactors, Course 2.2, by A. Tapucu, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Design Design Analysis [Audience] Engineer Grad Ugrad
    - Title and Table of Contents 20043801.pdf (96 kb)
    - Chapter 1 - Fundamental Concepts, by A. Tapucu, 20043802.pdf (234 kb)
    - Chapter 2 - Single Phase Fluid Equations, by A. Tapucu, 20043803.pdf (200 kb)
    - Chapter 3 - Principles of Heat Transfer, by A. Tapucu, 20043804.pdf (1061 kb)
    - Chapter 4 - Forced Convection Heat Transfer, by A. Tapucu, 20043805.pdf (1624 kb)
    - Chapter 7 - Heat Removal from Nuclear Reactors, by A. Tapucu, 20043806.pdf (1557 kb)
    - Appendix 1 - Tensors, by A. Tapucu, 20043807.pdf (49 kb)
    - Appendix 2 - Stress in a Fluid, by A. Tapucu, 20043808.pdf (256 kb)
    - Appendix 3 - A Short Summary of Orthogonal Functions Used in Chapter 4, by A. Tapucu, 20043809.pdf (178 kb)
    - Workbook, Chapter 4, by A. Tapucu, 20043810.pdf (2301 kb)
    - Workbook, Chapter 7, by A. Tapucu, 20043811.pdf (2043 kb)
  15. Reactor Thermalhydraulics Analysis, Course 2.3, by Wm.J. Garland, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: Fundamentals of thermalhydraulic analysis (heat transfer and fluid mechanics)of the heat transport system.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Title and Table of Contents 20043901.pdf (144 kb)
  16. Introduction to Nuclear Reactor Engineering, Course 3.1, by J. Koclas, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Nuclear Engineering [Topic] Basic Equations [Phase] Concept Design [Audience] College Manager Technician Ugrad
    - Introduction to Nuclear Engineering 20044101.pdf (1855 kb)
    - A Guidebook to Nuclear Reactors by Anthony V. Nero, by J. Koclas, 20044102.pdf (1874 kb)
    - Miscellaneous CANDU-Related Viewgraphs, by J. Koclas, 20044103.pdf (1045 kb)
    17. 1997-01-01---------Jump to [Top]
  17. Nuclear Theory I (Statics), or Introduction to Nuclear Technology 1.1a, by Robin Chaplin, Chulalongkorn University, 1997-01-01. Doc type: Course.
    Summary: This lecture material is supplementary to Chulalongkorn University Training Program Course # 1.1, Nuclear Physics and Reactor Theory by Ian Cameron (Course 22106), Modules 1 to 7]
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Introduction 20041700.pdf (177 kb)
    - Section 1 - Nuclear Physics, by Robin Chaplin, 20041701.pdf (461 kb)
    - Section 1 - Nuclear Physics (Figures), by Robin Chaplin, 20041702.pdf (346 kb)
    - Section 2 - Nuclear Interactions, by Robin Chaplin, 20041703.pdf (727 kb)
    - Section 2 - Nuclear Interactions (Figures), by Robin Chaplin, 20041704.pdf (775 kb)
    - Section 3 - Neutron Diffusion, by Robin Chaplin, 20041705.pdf (255 kb)
    - Section 4 - Reactor Theory, by Robin Chaplin, 20041706.pdf (534 kb)
    - Section 4 - Reactor Theory (Figures), by Robin Chaplin, 20041707.pdf (456 kb)
    - Section 5 - Reactor Kinetics, by Robin Chaplin, 20041708.pdf (1075 kb)
    - Question Bank, by Robin Chaplin, 20041709.pdf (1095 kb)
    - Reference Data, by Robin Chaplin, 20041710.pdf (537 kb)
    18. 1998-02-01---------Jump to [Top]
  18. Neutronic Analysis of Reactors, Course 1.7, by J. Koclas, Chulalongkorn University, 1998-02-01. Doc type: Course.
    Summary: Covers methods used to solve reactor physics problems in both steady state and transient.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations [Phase] Design [Audience] Engineer Grad Ugrad
    - Chapter 0 - Title and Table of Contents 20043601.pdf (175 kb)
    - Chapter 1 - Introduction, by J. Koclas, 20043602.pdf (102 kb)
    - Chapter 2 - Parameter Definitions, by J. Koclas, 20043603.pdf (144 kb)
    - Chapter 3 - Derivation of the Space-Time Kinetics Equations, by J. Koclas, 20043604.pdf (174 kb)
    - Chapter 4 - Energy Condensation, by J. Koclas, 20043605.pdf (137 kb)
    - Chapter 5 - Matrix Form of Equations, by J. Koclas, 20043606.pdf (60 kb)
    - Chapter 6 - Spatial Mesh Considerations, by J. Koclas, 20043607.pdf (592 kb)
    - Chapter 7 - Statics, by J. Koclas, 20043608.pdf (255 kb)
    - Chapter 8 - Numerical Methods in Reactor Statics, by J. Koclas, 20043609.pdf (420 kb)
    - Chapter 9 - KInetics Methods Classification, by J. Koclas, 20043610.pdf (34 kb)
    - Chapter 10 - Point Kinetics, by J. Koclas, 20043611.pdf (233 kb)
    - Chapter 11 - Elementary Numerical Integration Techniques, by J. Koclas, 20043612.pdf (218 kb)
    - Chapter 12 - Adiabatic Method, by J. Koclas, 20043613.pdf (140 kb)
    - Chapter 13 - Quasistatic Method, by J. Koclas, 20043614.pdf (102 kb)
    - Chapter 14 - Modal Synthesis, by J. Koclas, 20043615.pdf (164 kb)
    - Chapter 15 - Mesh Centered Finite Difference, by J. Koclas, 20043616.pdf (409 kb)
    - Chapter 16 - Time Integration of the Space-Time Kinetics Equations, by J. Koclas, 20043617.pdf (178 kb)
    - Chapter 17 - Comparisons of Spatial Approximations, by J. Koclas, 20043618.pdf (300 kb)
  19. Reactor Thermalhydraulics Analysis, Course 2.3, by Wm.J. Garland, Chulalongkorn University, 1998-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Glossary and Foreword 20043902.pdf (152 kb)
    - Chapter 1 - Course Overview, by Wm.J. Garland, 20043903.pdf (140 kb)
    - Chapter 2 - Basic Equations for Thermalhydraulic Systems Analysis, by Wm.J. Garland, 20043904.pdf (561 kb)
    - Chapter 3 - Nodalization, by Wm.J. Garland, 20043905.pdf (303 kb)
    - Chapter 4 - Equation of State, by Wm.J. Garland, 20043906.pdf (338 kb)
    - Chapter 5 - The Rate Form of the Equation of State, by Wm.J. Garland, 20043907.pdf (512 kb)
    - Chapter 6 - Thermalhydraulic Network Simulation, by Wm.J. Garland, 20043908.pdf (343 kb)
    - Chapter 7 - Empirical Correlations, by Wm.J. Garland, 20043909.pdf (532 kb)
    - Chapter 8 - On Design Tools, by Wm.J. Garland, 20043910.pdf (481 kb)
    - Workbook, Chapter 1, by Wm.J. Garland, 20043911.pdf (151 kb)
    - Workbook Chapter, 2, by Wm.J. Garland, 20043912.pdf (767 kb)
    - Workbook Chapter 3, by Wm.J. Garland, 20043913.pdf (466 kb)
    - Workbook Chapter 4, by Wm.J. Garland, 20043914.pdf (604 kb)
    - Workbook Chapter 5, by Wm.J. Garland, 20043915.pdf (847 kb)
    - Workbook Chapter 6, by Wm.J. Garland, 20043916.pdf (614 kb)
    - Workbook Chapter 7, by Wm.J. Garland, 20043917.pdf (719 kb)
    - Workbook Chapter 8, by Wm.J. Garland, 20043918.pdf (903 kb)
    - Workbook Figures, by Wm.J. Garland, 20043919.pdf (509 kb)
  20. Reactor Thermalhydraulics Analysis, Supplementary, Course 2.3a, by Wm.J. Garland, Chulalongkorn University, 1998-02-01. Doc type: Course.
    Summary: Supplementary info for thermalhydraulic analysis (heat transfer and fluid mechanics)of the heat transport system.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Appendices 1 - 4 1 - Time Derivatives 2 - The Reynolds Transport Theorem 3 - Rearrangement of Independent Variables 4 - Fast Calculation of Light-Water Properties 20044001.pdf (647 kb)
    - Calculation of Water Properties, by Wm.J. Garland, 20044002.pdf (947 kb)
    - THSIM User Manual, by Wm.J. Garland, 20044003.pdf (733 kb)
    - A Pedagogical Look at Fully- and Semi-Implicit Solutions to T-H Eq'ns, by Wm.J. Garland, 20044004.pdf (320 kb)
    - Basic Equations for T-H Systems Analysis, by Wm.J. Garland, 20044005.pdf (590 kb)
    - Miscellaneous Figures and Equations, by Wm.J. Garland, 20044006.pdf (315 kb)
    21. 1999-02-23---------Jump to [Top]
  21. Decay Heat Estimates for MNR, by Wm.J. Garland, McMaster University, 1999-02-23. Doc type: Other.
    Summary: Decay heat removal is essential in preventing fuel overheating and possible fission product release.  This
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Basic Equations Modelling Reactor Physics [Phase] Concept Design Safety Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - decayhe1.xls (521 kb)
    22. 2002-09-01---------Jump to [Top]
  22. Introduction to Reactor Physics, by Ben Rouben, AECL, 2002-09-01. Doc type: Course.
    Summary: This is a descriptive course on the physics of CANDU reactors. The objective is to familiarize you with the basic concepts and ideas, definitions and quantities which are important in the understanding of reactor physics. The discussion will be at a basic level, as this is an introduction to the subject. Very little emphasis is placed on complex equations or difficult mathematics. The desired outcome of this course is that you will be able in the future to understand and follow reactor-physics discussions in meetings, reports or presentations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - 20040501.pdf (369 kb)
    - Presentation, by Ben Rouben, 20040502.pdf (13610 kb)
    23. 2004-07-17---------Jump to [Top]
  23. CANDU Primary Heat Transfer System Heat Duty Diagram - analytic solution, by Wm.J. Garland, McMaster University, 2004-07-17. Doc type: Other.
    Summary: CANDU Primary Heat Transfer System Heat Duty Diagram - simplified analytical calculation.
    Keywords: [Concept] - [SI] 33100 Main Heat Transport Syste 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering [Topic] Basic Equations Heat Transfer Modelling Process Systems [Phase] Concept Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - linear1.xls (333 kb)
  24. CANDU Primary Heat Transfer System Heat Duty Diagram - numeric solution, by Wm.J. Garland, McMaster University, 2004-07-17. Doc type: Other.
    Summary: CANDU Primary Heat Transfer System Heat Duty Diagram simplified numerical calculation .
    Keywords: [Concept] - [SI] 33100 Main Heat Transport Syste 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering [Topic] Basic Equations Heat Transfer Modelling Process Systems [Phase] Concept Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - numeric1.xls (377 kb)
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