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[Author]: Wm.J. Garland 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: 78

    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. 1985-04-24---------Jump to [Top]
  2. CANDU 6 Heat balance, by Wm.J. Garland, McMaster University, 1985-04-24. Doc type: Other.
    Summary: CANDU 6 heat balance / power calculation based on measured temperatures, pressures and flows, with error propagation estimates.
    Keywords: [Concept] - [SI] 30000 Reactor Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Conceptual; #Heat Transfer; #Modelling; #Process Systems [Phase] Concept; #Design [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - CANDU2.xls (88 kb)
    3. 1995-06-25---------Jump to [Top]
  3. Effects Contributing to Positive Coolant Void Reactivity in CANDU, by J. J. Whitlock, Wm.J. Garland, M.S. Milgram, McMaster University, 1995-06-25. Doc type: Paper.
    Summary: The lattice cell properties leading to positive coolant void reactivity in the CANDU reactor are described. The effect is subdivided into spectral, spatial, and isotopic components, and described in terms of criticality factors based on the six-factor fo
    Keywords: [Concept] Reactor Physics [SI] 03000 Engineering Science and Technology 31000 Reactor [Discipline] Nuclear Engineering [Topic] Reactor Physics3 [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Whitlock_ANS_1995.pdf (777 kb)
    4. 1996-02-01---------Jump to [Top]
  4. 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)
  5. 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)
  6. Nuclear Reactor Safety Design, Course 3.7, by Wm.J. Garland, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Concept Design Safety [Audience] Engineer Grad Ugrad
    - Chapter 1 - Introduction 20044701.pdf (421 kb)
    - Chapter 2 - Probability Tools & Techniques, by Wm.J. Garland, 20044702.pdf (441 kb)
    - Chapter 3 - Safety Criteria, by Wm.J. Garland, 20044703.pdf (396 kb)
    - Chapter 4 - Design Basis Accidents, by Wm.J. Garland, 20044704.pdf (131 kb)
    - Chapter 5 - Probabilistic Risk Assessment, by Wm.J. Garland, 20044705.pdf (154 kb)
    - Chapter 6 - Safety Analysis, by Wm.J. Garland, 20044706.pdf (190 kb)
    - Chapter 7 - Safety Systems, by Wm.J. Garland, 20044707.pdf (365 kb)
    - Chapter 8 - Good Design Principles & Practices, by Wm.J. Garland, 20044708.pdf (211 kb)
    - References, by Wm.J. Garland, 20044709.pdf (91 kb)
    - Appendix 1 - NRX Accident, by Wm.J. Garland, 20044710.pdf (308 kb)
    - Appendix 2 - Subcategory A.1 Events, by Wm.J. Garland, 20044711.pdf (135 kb)
    - Appendix 3 - Applicable Codes & Standards, by Wm.J. Garland, 20044712.pdf (99 kb)
    - Appendix 4 - Organization of Licensing Basis Document, by Wm.J. Garland, 20044713.pdf (64 kb)
    - Appendix 5 - Accident Analysis Matrix, by Wm.J. Garland, 20044714.pdf (97 kb)
    - Appendix 6 - Large LOCA, by Wm.J. Garland, 20044715.pdf (193 kb)
    - Appendix 7 - Failure Data, by Wm.J. Garland, 20044716.pdf (157 kb)
    - Appendix 8 - Accident Analysis Overview by R. Holmes, by Wm.J. Garland, 20044717.pdf (287 kb)
    - Workbook, Chapter 1 - Figures, by Wm.J. Garland, 20044718.pdf (638 kb)
    - Workbook, Chapter 2 - Figures, by Wm.J. Garland, 20044719.pdf (772 kb)
    - Workbook, Chapter 3 - Figures, by Wm.J. Garland, 20044720.pdf (656 kb)
    - Workbook, Chapter 4 - Figures, by Wm.J. Garland, 20044721.pdf (215 kb)
    - Workbook, Chapter 5 - Figures, by Wm.J. Garland, 20044722.pdf (266 kb)
    - Workbook, Chapter 6 - Figures, by Wm.J. Garland, 20044723.pdf (294 kb)
    - Workbook, Chapter 7 - Figures, by Wm.J. Garland, 20044724.pdf (600 kb)
    - Workbook, Chapter 8 - Figures, by Wm.J. Garland, 20044725.pdf (389 kb)
    7. 1998-02-01---------Jump to [Top]
  7. 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)
  8. 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)
    9. 1999-02-23---------Jump to [Top]
  9. Single Phase Friction Factors for MNR Thermalhydraulic Modelling, by Wm.J. Garland, McMaster University, 1999-02-23. Doc type: Other.
    Summary: This report documents a review of selected literature to determine the appropriate correlations to use for McMaster Nuclear Reactor safety analysis.  It was found that the standard Moody diagram (which is based on the transcendental Colebrook equation) is sufficiently accurate for pipe flow but problematic to program, whereas simple approximations do not account for pipe wall roughness.  Herein, a very simple function is offered that returns an accurate estimate of f as a function of Reynolds Number, Re, and relative roughness e/D in a non-iterative fashion.  In addition, a simple correction factor for channel flow is offered.
    Keywords: [Concept] - [SI] 03200 Mechanical Engineering; #33000 Primary Heat Transport System [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Modelling [Phase] Concept; #Design [Audience] College; #Engineer; #Grad; #Technician; #Ugrad
    - 1phase1.xls (552 kb)
  10. 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)
    11. 2000-12-01---------Jump to [Top]
  11. How and Why is CANDU designed the way it is, by Wm.J. Garland, CANTEACH, 2000-12-01. Doc type: Paper.
    Summary: Why we need nuclear power; A look at the nuclear reactor in a nutshell; The engineering approach - CANDUs are engineered systems, typified by functional decomposition; A quick overview of CANDU vs PWR vs BWR and others.
    Keywords: [Concept] Overview [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] Concept Design [Audience] High
    - 20000101.pdf (819 kb)
    12. 2003-05-10---------Jump to [Top]
  12. Preserving CANDU Technical Knowledge – The CANTEACH Project, by Wm.J. Garland, Yulia Kosarenko, Malcolm Lightfoot, D.A. Meneley, CANTEACH, 2003-05-10. Doc type: Paper.
    Summary:
    Keywords: [Concept] General [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High K-8 Manager Technician Ugrad Vendor
    - 20031401.pdf (245 kb)
  13. Preservation and Dissemination of CANDU® Technical Knowledge (The CANTEACH Project), by Wm.J. Garland, Yulia Kosarenko, Malcolm Lightfoot, D.A. Meneley, CANTEACH, 2003-05-10. Doc type: Paper.
    Summary:
    Keywords: [Concept] General [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High K-8 Manager Technician Ugrad Vendor
    - 20031501.pdf (299 kb)
    14. 2004-07-17---------Jump to [Top]
  14. 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)
  15. 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)
  16. CANDU fuel channel 1-D temperature calculation, by Wm.J. Garland, McMaster University, 2004-07-17. Doc type: Other.
    Summary: CANDU fuel channel 1-D temperature calculation spreadsheet.
    Keywords: [Concept] - [SI] 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Modelling [Phase] Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - channel1 (511 kb)
  17. Point kinetics simulation, by Wm.J. Garland, McMaster University, 2004-07-17. Doc type: Other.
    Summary: A point kinetics simulation using Excel spreadsheet and VBA. Easy to play with and modify.
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual Modelling Reactor Physics [Phase] Concept Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - pk.xls (465 kb)
    18. 2006-03-01---------Jump to [Top]
  18. Fretting Failures in Early Canadian Nuclear Steam Generators, by J.M. Dyke and Wm.J. Garland, CANTEACH, 2006-03-01. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
    - 20060201.pdf (140 kb)
    19. 2006-04-01---------Jump to [Top]
  19. Evolution of CANDU Steam Generators – A Historical View, by J.M. Dyke and Wm.J. Garland, CANTEACH, 2006-04-01. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
    - 20060101.pdf (702 kb)
    20. 2011-01-01---------Jump to [Top]
  20. Concept Maps, by Wm.J. Garland, CANTEACH, 2011-01-01. Doc type: Other.
    Summary: Illustrated are the overall concepts and topics in the various disciplines involved in the design and operation of CANDU reactors. This provides some guidance for the detailed study of CANDU reactors.
    Keywords: [Concept] Overview [SI] - [Discipline] Nuclear Engineering [Topic] Conceptual Intro and Overview [Phase] Concept [Audience] College Engineer Grad High Manager Technician Ugrad
    - Overview of Concepts and Topics 20110101.pdf (264 kb)
    21. 2015-01-01---------Jump to [Top]
  21. The Essential CANDU, by Wm.J. Garland, Editor-in-Chief, UNENE, 2015-01-01. Doc type: Book.
    Summary: The Essential CANDU is a textbook about nuclear science and engineering pertaining to CANDU reactors using CANDU as the reference design. This distinguishes it from comparable textbooks based on PWR reactors. This is not a product description of CANDU per se. The book emphasizes theory over other aspects of nuclear science. This is a textbook about CANDU nuclear reactor and power plant engineering, not just the reactor physics of the core.
    Keywords: [Concept] General [SI] 30000 Reactor, Steam Generators and Auxiliaries 35000 Fuel Transfer and Storage 36000 Steam Generator Steam and Water Systems 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Chemistry General Engineering Health Physics Nuclear Engineering [Topic] Corrosion Fluid Mechanics Fuel Management Heat Transfer Important Parameters Physical Description Process Systems Radiation Reactor Physics Safety Thermalhydraulics Thermodynamics Waste Handling [Phase] Design Design Analysis Design Description Design Evolution Safety Safety Analysis [Audience] Engineer Grad Ugrad
    - A textbook on the CANDU nuclear power plant technology. press_release-Jan2016.pdf (382 kb)
    22. 2017-02-13---------Jump to [Top]
  22. Xenon and iodine kinetics simulation, by Wm.J. Garland, McMaster University, 2017-02-13. Doc type: Other.
    Summary: Xenon and iodine kinetics simulation using Excel spreadsheet and VBA. Easy to play with and modify.
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual Modelling Reactor Physics [Phase] Concept Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - Xe.xls (91 kb)
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