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[Phase]: Design 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: 1225

    1950-01-01---------Jump to [Top]
  1. Dyke, J.M. - Selected Works, by J.M. Dyke, Individual Contributions, 1950-01-01. Doc type: Essay.
    Summary: John M. Dyke B.A.Sc., P.Eng: John was involved in steam generator design for 35 years, from 1945 to 1980. He lead the design team for the Pickering A nuclear station in the mid 1960s. They were the first with internal economizer and integral steam drums. The 48 steam generators at this four-reactor station have had exemplary performance. John obtained his B.A.Sc. in Mechanical Engineering from the University of Toronto in 1943 and joined the Royal Canadian Navy Volunteer Reserve as an Engineering Officer posted with the Royal Navy doing convoy duty in the Atlantic and the Mediterranean. When he returned to Canada he worked at the Naval Research Establishment in Halifax developing anti-acoustic torpedo gear. Coincidentally, these were parallel rods that vibrated in water streams. After the war John did steam boiler engineering at several firms and became Chief Engineer of Dominion Bridge’s new boiler department in 1958. Here he attended a special course on nuclear design and submitted bids for early nuclear steam generators and reheaters. In 1964 he joined Babcock and Wilcox Canada, first as a project engineer on fossil-fired boilers and then to head up the new nuclear steam generating section where they developed a new 500 MWe design for Pickering A. He is a registered professional engineer with the province of Ontario. He has been honored by the American Society of Mechanical Engineering as a life member for outstanding lifetime achievement. The Canadian Nuclear Association also honored him with their Outstanding Contribution Award for designing the steam generators used in CANDU stations. John retired from BWC in 1980.
    Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Design Operation [Audience] Engineer Grad Manager Technician Ugrad
    - Introduction Dyke-intro.pdf (291 kb)
  2. 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)
    3. 1956-01-01---------Jump to [Top]
  3. The Pressurized Water Reactor as a Source of Heat for Steam Power Plants, by J.M. Kay and F.J. Hutchinson, IMechE, 1956-01-01. Doc type: Paper.
    Summary: Published in the Proceedings of the Institution of Mechanical Engineers Volume 170 1956 pps 281 - 297
    Keywords: [Concept] - [SI] 09000 Special Studies [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Conceptual Heat Transfer Thermodynamics [Phase] Concept Design Operation [Audience] Engineer Ugrad Vendor
    - Published in the Proceedings of the Institution of Mechanical Engineers Volume 170 1956 pps 281 - 296 20054600.pdf (2333 kb)
    4. 1958-09-01---------Jump to [Top]
  4. NPD-2 Design Description, OPG, 1958-09-01. Doc type: Report.
    Summary: This booklet presents a detailed design description of the NPD-2 station, a joint project of AECL, CGE and the Hydro-Electric Power Commission of Ontario.
    Keywords: [Concept] General [SI] 00000 General Project 30000 Reactor, Steam Generators and Auxiliaries 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Description [Audience] College Engineer High Technician Ugrad
    - Canada's First Nuclear Power Station CGE-NPD-DD-Sept1958.pdf (2766 kb)
    5. 1960-01-01---------Jump to [Top]
  5. Nuclear Power Demonstration, OPG, 1960-01-01. Doc type: Other.
    Summary: Cutaway drawings and a flow diagram of NPD-2. Date unknown.
    Keywords: [Concept] General [SI] 00000 General Project [Discipline] General Engineering [Topic] Layout [Phase] Design [Audience] College High Technician
    - a brochure NPD-brochure.pdf (7439 kb)
    6. 1961-04-01---------Jump to [Top]
  6. NDP-2 Systems - Calandria Assembly, Course T.T.01-312, OPG, 1961-04-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heavy Water Physical Description Process Systems [Phase] Design [Audience] College Engineer Technician Ugrad
    - NPD-TT01-312-1961.pdf (2972 kb)
    7. 1961-05-01---------Jump to [Top]
  7. NDP-2 Systems - Moderator, Course T.T.4-4.320, OPG, 1961-05-01. Doc type: Course.
    Summary:
    Keywords: [Concept] General [SI] 32000 Moderator System [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] Design [Audience] College Engineer Technician Ugrad
    - General description only, 3 pages. NPD-TT4-4-320-1961.pdf (138 kb)
    8. 1961-09-18---------Jump to [Top]
  8. NPD, a Description of, by J.L Olsen, OPG, 1961-09-18. Doc type: Presentation.
    Summary: Nuclear Power Demonstration. An illustrated talk presented at the Seventh AECL Symposium on Atomic Energy, Chalk River, September 18, 1961.
    Keywords: [Concept] General [SI] 00000 General Project 30000 Reactor, Steam Generators and Auxiliaries 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Description [Audience] College Engineer High Technician Ugrad
    - Canada's First Nuclear Power Station CAPD10--Sept1961NPD-Description.pdf (5637 kb)
    9. 1962-09-24---------Jump to [Top]
  9. Douglas Point Project, by D.L.S. Bate, OPG, 1962-09-24. Doc type: Report.
    Summary: Description of the progress in designing and constructing the Douglas Point Project, a 200 MW nuclear power plant.
    Keywords: [Concept] General [SI] 00000 General Project [Discipline] General Engineering [Topic] Intro and Overview [Phase] Construction Design [Audience] Engineer Manager Technician
    - Status Report DP-Status-Sept1962.pdf (2380 kb)
    10. 1962-11-01---------Jump to [Top]
  10. NPD Nucleonics Description, by Nucleonics, OPG, 1962-11-01. Doc type: Other.
    Summary:
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] - [Phase] Design Operation [Audience] College Engineer Grad Manager Technician Ugrad
    - NPD on the Line - a foldout description with layout diagrams and design date. NDP-NucleonicsNov1962.PDF (4922 kb)
    11. 1963-07-01---------Jump to [Top]
  11. NDP-2 Systems - Reactor, Course T.T.4-5.310, OPG, 1963-07-01. Doc type: Course.
    Summary:
    Keywords: [Concept] General [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] Design [Audience] College Engineer Technician Ugrad
    - General description only, 9 pages. NPD-TT4-5-310-1963.pdf (511 kb)
    12. 1964-01-01---------Jump to [Top]
  12. NDP Systems - I&C General - Annunciation, Course T.T.0-5.603, OPG, 1964-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Intro and Overview [Phase] Design [Audience] College Engineer Technician Ugrad
    - NPD-TT-0-5-603-1964.pdf (293 kb)
    13. 1964-08-01---------Jump to [Top]
  13. Heat and Thermodynamics, Course 1-2.5, Nuclear Electric GS Technical Training Course, by D. Dueck, OPG, 1964-08-01. Doc type: Course.
    Summary: Basic concepts of thermodynamics
    Keywords: [Concept] Mechanical [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Full course, sections 1 to 8. NEGS-TT1-2-5-1964.pdf (7809 kb)
  14. Heat and Thermodynamics, Course 2-2.5, Nuclear Electric GS Technical Training Course, by D. Dueck, OPG, 1964-08-01. Doc type: Course.
    Summary: Basic concepts of thermodynamics
    Keywords: [Concept] Mechanical [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Concept Design Design Analysis [Audience] College Ugrad
    - Full course, sections 1 to 10. NEGS-TT2-2-5-1964.pdf (3387 kb)
  15. Heat and Thermodynamics, Course 1-2.5, Nuclear Electric GS Technical Training Course, by D. Dueck, OPG, 1964-08-01. Doc type: Course.
    Summary: Basic concepts of thermodynamics
    Keywords: [Concept] Mechanical [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Full course, sections 1 to 10. NEGS-TT3-2-5-1964.pdf (4826 kb)
    16. 1964-11-01---------Jump to [Top]
  16. Turbine, Generator and Auxiliaries, Course 3-3.4, Nuclear Electric GS Technical Training Course, by D.Dueck, OPG, 1964-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Mechanical [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Full course, sections 1 to 9 NEGS-TT3-3-4-1964.pdf (6102 kb)
  17. Turbine, Generator and Auxiliaries, Course 4-3.4, Nuclear Electric GS Technical Training Course, by D.Dueck, OPG, 1964-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Full course, sections 1 to 7 NEGS-TT4-3-4-1964.pdf (2375 kb)
    18. 1964-12-01---------Jump to [Top]
  18. Turbine, Generator and Auxiliaries, Course 2-3.4, Nuclear Electric GS Technical Training Course, by D.Dueck, OPG, 1964-12-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Full course, sections 1 to 10 NEGS-TT2-3-4-1964.pdf (7516 kb)
    19. 1965-01-01---------Jump to [Top]
  19. Turbine, Generator and Auxiliaries, Course 1-3.4, Nuclear Electric GS Technical Training Course, by Dick Dueck, OPG, 1965-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Mechanical [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Full course, sections 1 to 7 NEGS-TT1-3-4-1965.pdf (4837 kb)
  20. 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)
    21. 1966-07-01---------Jump to [Top]
  21. Heat and Thermodynamics, Course 1A25, Nuclear Training Course , by George Howie, OPG, 1966-07-01. Doc type: Course.
    Summary: Basic concepts of thermodynamics
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Full course, sections 1 to 10. OH-1A25-1966.pdf (5569 kb)
    22. 1966-11-01---------Jump to [Top]
  22. Reactor, Boiler and Auxiliaries, Course 133, Nuclear Training Center, OPG, 1966-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Full Course 20050900.pdf (10930 kb)
    - 133.00-00 Index, 20050901.pdf (252 kb)
    - 133.10-01 The Function of a Reactor, 20050902.pdf (262 kb)
    - 133.10-02 Reactor Classification - Fast and Thermal Reactors, 20050903.pdf (306 kb)
    - 133.10-03 Reactor Classification - Types of Thermal Reactors, 20050904.pdf (791 kb)
    - 133.10-04 Reactor Construction, 20050905.pdf (622 kb)
    - 133.20-01 Moderator Requirements, 20050906.pdf (227 kb)
    - 133.20-02 Moderator Materials Properties and Comparison, 20050907.pdf (459 kb)
    - 133.20-03 Moderator System and Equipment Considerations, 20050908.pdf (930 kb)
    - 133.30-01 Heat Transport Fluid Requirements, 20050909.pdf (401 kb)
    - 133.30-02 Heat Transport Fluid Comparisons, 20050910.pdf (600 kb)
    - 133.30-03 Main Circuit Considerations, 20050911.pdf (845 kb)
    - 133.30-04 Auxiliary Circuits, 20050912.pdf (708 kb)
    - 133.40-01 Reflector Systems, 20050913.pdf (367 kb)
    - 133.40-02 Shield Cooling Systems, 20050914.pdf (318 kb)
    - 133.50-01 Functions of Reactivity Mechanisms, 20050915.pdf (191 kb)
    - 133.50-02 Comparisons of Reactivity Mechanisms, 20050916.pdf (711 kb)
    - 133.62-01 Upgrading Requirements and Processes, 20050917.pdf (170 kb)
    - 133.62-02 Principles of Isotope Separation, 20050918.pdf (126 kb)
    - 133.62-03 The Distillation Upgrading Process, 20050919.pdf (258 kb)
    - 133.62-04 The Electrolytic Process, 20050920.pdf (149 kb)
    - 133.62-05 Common Problems, 20050921.pdf (183 kb)
    - 133.71-01 General Fuel Considerations, 20050922.pdf (190 kb)
    - 133.71-02 Fuel Preparation and Manufacture, 20050923.pdf (233 kb)
    - 133.71-03 Canadian Designs and Their Performance, 20050924.pdf (294 kb)
    - 133.91-01 Safety Standards and Safety Measures, 20050925.pdf (198 kb)
    - 133.91-02 Emergency Injection and Containment Systems, 20050926.pdf (160 kb)
    - 133.91-03 Safety System Performance, 20050927.pdf (199 kb)
    - 133.92-01Chemistry of Water Circuits, 20050928.pdf (940 kb)
    23. 1967-07-01---------Jump to [Top]
  23. Nuclear Theory, Course 227, Nuclear Training Centre, OPG, 1967-07-01. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Full Course 20050400.pdf (2650 kb)
    - 227.00-01 Prompt, Delayed and Photo-Neutron Production, 20050401.pdf (153 kb)
    - 227.00-02 Neutron Balance During Steady Reactor Operation, 20050402.pdf (206 kb)
    - 227.00-03 Neutron Density, Neutron Power and Neutron Flux, 20050403.pdf (103 kb)
    - 227.00-04 Neutron Flux Distribution and its Effect on Power, 20050404.pdf (274 kb)
    - 227.00-05 Meaning of Criticality, Multiplication Factor, Reactivity and Neutron Lifetime, 20050405.pdf (140 kb)
    - 227.00-06 Change of Reactor Power with Reactivity Change, 20050406.pdf (198 kb)
    - 227.00-07 Change of Reactor Power with Time, 20050407.pdf (112 kb)
    - 227.00-08 Effects of Prompt and Delayed Neutrons on Reactor Power Changes, 20050408.pdf (282 kb)
    - 227.00-09 Effect of Photoneutrons on Reactor Power Changes, 20050409.pdf (150 kb)
    - 227.00-10 Methods of Reactor Control, 20050410.pdf (160 kb)
    - 227.00-11 Starting Up a Reactor and Increasing Power, 20050411.pdf (197 kb)
    - 227.00-12 Decreasing Power and Shutting Down a Reactor, 20050412.pdf (146 kb)
    - 227.00-13 Xenon Poison and its Effects on Reactor Operation, 20050413.pdf (241 kb)
    - 227.00-14 Examples of Practical Reactor Behaviour, 20050414.pdf (156 kb)
    24. 1967-08-01---------Jump to [Top]
  24. Site Selection, Nuclear Training Course 131, by J. Krasnoebski, A. Williams, OPG, 1967-08-01. Doc type: Course.
    Summary:
    Keywords: [Concept] General [SI] 10000 Site and Improvements [Discipline] General Engineering [Topic] Intro and Overview [Phase] Design [Audience] College
    - 1 Site Selection Factors, 2 Safety or Environmental Factors, 3 Economic Factors & Social Acceptability NTC-131-1967.pdf (918 kb)
    25. 1968-01-01---------Jump to [Top]
  25. NPD Systems - Fuel Handling System, Course 053, by Staff, OPG, 1968-01-01. Doc type: Course.
    Summary: This manual is issued as an indoctrination course on the N.P.D. Fuel Handling System. The successful completion of the course and examinations will, however, be required as partial N04, NC4 or NM4 qualifications.
    Keywords: [Concept] Mechanical [SI] 35000 Fuel Transfer and Storage [Discipline] Mechanical Engineering [Topic] Fuel Management Physical Description Process Systems [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Reactor Boiler and Auxiliaries Fuel Handling System NPD053-352.pdf (11616 kb)
    26. 1968-04-01---------Jump to [Top]
  26. NPD Systems - Building and Structures, Course 052, by R. Whitney, OPG, 1968-04-01. Doc type: Course.
    Summary: Building and structures for the NPD plant complex, overview.
    Keywords: [Concept] General [SI] 20000 Buildings and Structures [Discipline] General Engineering [Topic] Intro and Overview Physical Description [Phase] Design [Audience] College
    - NPD Systems - Building and Structures NPD052-1968.pdf (1693 kb)
    27. 1968-05-01---------Jump to [Top]
  27. The Performance of Zirconium Alloy Clad UO2 Fuel for Canadian Pressurized and Boiling Water Power Reactors, by R.D. Page and A.D. Lane, AECL, 1968-05-01. Doc type: Report.
    Summary: This paper presents the most recent information (as of 1968) on the performance of CANDU fuel, and goes on to summarize the results of an extensive irradiation program to develop fuels for boiling water cooled reactors.
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Materials Engineering [Topic] Function Performance [Phase] Design Development Operation [Audience] Engineer
    - 19680101.pdf (2338 kb)
    28. 1968-09-01---------Jump to [Top]
  28. Basic Course for Radiation Surveyors and Contamination Monitors of the Radiation and Industrial Safety Branch, by J.H. Fenn and W.R. Bush, AECL, 1968-09-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Design Operation [Audience] Engineer Grad Technician Ugrad
    - 20100200.pdf (6970 kb)
    29. 1968-11-01---------Jump to [Top]
  29. Reactor Boiler and Auxiliaries, Course 433, Nuclear Training Centre, OPG, 1968-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Full Course 20051200.pdf (1786 kb)
    - 433.00-00 Index, 20051201.pdf (241 kb)
    - 433.10-01 Nuclear Power, 20051202.pdf (121 kb)
    - 433.10-02 Power Reactor Construction, 20051203.pdf (179 kb)
    - 433.20-01 Moderator Systems, 20051204.pdf (141 kb)
    - 433.30-01 Heat Transport Systems, 20051205.pdf (239 kb)
    - 433.40-01 Auxiliary Circuits, 20051206.pdf (205 kb)
    - 433.50-01 Fuel, 20051207.pdf (247 kb)
    - 433.50-02 Fuel Handling and Storage, 20051208.pdf (172 kb)
    - 433.60-01 Boiler Steam and Water Systems, 20051209.pdf (291 kb)
    30. 1969-01-01---------Jump to [Top]
  30. Pickering Generating Station Design Description, OPG, 1969-01-01. Doc type: Report.
    Summary:
    Keywords: [Concept] Overview [SI] 00000 General Project 10000 Site and Improvements 20000 Buildings and Structures 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries 50000 Electric Power Systems 60000 Instrumentation and Control [Discipline] General Engineering Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Operation Safety [Audience] College Engineer Technician Ugrad
    - OH-PickeringDD1969.pdf (23589 kb)
    31. 1969-01-02---------Jump to [Top]
  31. 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)
    32. 1970-03-09---------Jump to [Top]
  32. Nuclear Heated Steam Generators, by D. J. Stelliga and J.M. Dyke, Babcock & Wilcox Canada, 1970-03-09. 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
    - Presented to the Canadian Electrical Association, Toronto, Ontario, March 9-12, 1970 20053900.pdf (928 kb)
    33. 1971-03-01---------Jump to [Top]
  33. Fast Reactor Kinetics - The QXI Code, by D.A. Meneley, K.O. Ott and E.S. Wiener, Individual Contributions, 1971-03-01. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Modelling [Phase] Design Analysis Safety Analysis [Audience] Grad Ugrad
    - 20070100.pdf (7793 kb)
    34. 1972-05-25---------Jump to [Top]
  34. AECL Lectures on Nuclear Power Symposium, by G.A. Pon, AECL, 1972-05-25. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems [Phase] Concept Design Design Analysis Safety Safety Analysis [Audience] College Engineer Ugrad
    - Lecture 1 - Introduction 19720101.pdf (1091 kb)
    - Lecture 2 - Radiation, by G. Cowper, 19720102.pdf (1025 kb)
    - Lecture 3 - Power Reactor Types, by Gordon L. Brooks, 19720103.pdf (3378 kb)
    - Lecture 4 - Reactor Physics, by E. Critoph, 19720104.pdf (1755 kb)
    - Lecture 5 - Canadian Reactor Fuel, by R.D. Page, 19720105.pdf (3924 kb)
    - Lecture 8 - System Analysis, by D.B. Primeau, 19720108.pdf (1770 kb)
    - Lecture 9 - Reactor and Station Control, by E.M. Yaremy, 19720109.pdf (2715 kb)
    - Lecture 10 - Plant Layout, by R.B.V. Simmons, 19720110.pdf (3190 kb)
    - Lecture 11 - Accident Analysis, by J.D. Sainsbury, 19720111.pdf (1418 kb)
    - Lecture 12 - Licensing, by L. Pease, 19720112.pdf (1755 kb)
    - Lecture 13 - Training, by G.R. Howey, 19720113.pdf (1432 kb)
    - Lecture 14 - Canadian Power Reactor Fuel. See AECL 5609 doc#19760101 for an updated version., by R.D. Page, 19720114.pdf (2844 kb)
    - Lecture 15 - Construction, by V.A. Harrison, 19720115.pdf (3542 kb)
    - Lecture 16 - Costs, by D.L.S. Bate, 19720116.pdf (764 kb)
    - Lecture 17 - Development Potential, by W.B. Lewis, 19720117.pdf (1390 kb)
    - Lectures 6 and 7 - Heat Transport and Auxiliary Systems, by R.H. Renshaw, 19720167.pdf (2431 kb)
  35. 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)
    36. 1974-07-01---------Jump to [Top]
  36. Nuclear Theory, Course 127, Nuclear Training Centre, OPG, 1974-07-01. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Full Course 20050300.pdf (5869 kb)
    - 127.00-00 Index and Objectives, 20050301.pdf (244 kb)
    - 127.10-01 Nuclear Structure, 20050302.pdf (571 kb)
    - 127.10-02 Neutron Reactions, 20050303.pdf (156 kb)
    - 127.10-03 Fission, 20050304.pdf (264 kb)
    - 127.10-04 Neutron Cross Sections and Neutron Flux, 20050305.pdf (305 kb)
    - 127.10-05 The Chain Reaction, 20050306.pdf (240 kb)
    - 127.10-06 Moderator Properties, 20050307.pdf (296 kb)
    - 127.10-05b Neutron Balance and the Four Factor Formula, 20050308.pdf (270 kb)
    - 127.10-06b Effect of Enrichment, Fuel Arrangement and Fuel Burnup on the Four Factor Formula, 20050309.pdf (287 kb)
    - 127.10-07 Flux Distribution and Critical Size, 20050310.pdf (203 kb)
    - 127.10-08 Function and Properties of the Reflector, 20050311.pdf (219 kb)
    - 127.20-01 Review of Terms, 20050312.pdf (201 kb)
    - 127.20-02 Low Power Considerations, 20050313.pdf (341 kb)
    - 127.20-03 Effects Due to Temperature Changes and Void Formation, 20050314.pdf (330 kb)
    - 127.20-04 Effects Due to Fission Product Accumulation, 20050315.pdf (295 kb)
    - 127.20-05 Effects Due to Fuel Burnup, 20050316.pdf (245 kb)
    - 127.20-06 Reactor Control, 20050317.pdf (303 kb)
    - 127.20-07 The Approach to Critical and the Raising of Power, 20050318.pdf (534 kb)
    - 127.20-08 Examples of Practical Reactor Behaviour, 20050319.pdf (262 kb)
    - 127.20-09 Reactor Stability, 20050320.pdf (135 kb)
    - 127.20-10 Safety Considerations, 20050321.pdf (308 kb)
    37. 1975-07-01---------Jump to [Top]
  37. 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)
    38. 1976-03-01---------Jump to [Top]
  38. Canadian Power Reactor Fuel, by R.D. Page, AECL, 1976-03-01. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 37000 Fuel [Discipline] Materials Engineering Mechanical Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Design Description [Audience] College Engineer Technician Ugrad
    - AECL 5609, updated version of Lecture 14 of the 1974 Nuclear Power Symposium Series, doc#19720114 19760101.pdf (8580 kb)
    39. 1976-09-01---------Jump to [Top]
  39. Turbine, Generator and Auxiliaries, Course 134, Nuclear Training Centre, OPG, 1976-09-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Full Course 20051100.pdf (3779 kb)
    - 134.00-00 Index and Objectives, 20051101.pdf (355 kb)
    - 134.00-01 Turbine Theory, 20051102.pdf (793 kb)
    - 134.00-02 Turbine Operational Performance, 20051103.pdf (534 kb)
    - 134.00-03 Turbine Operational Problems, 20051104.pdf (554 kb)
    - 134.00-04 Turbine Start-Up, 20051105.pdf (365 kb)
    - 134.00-05 Factors Limiting Startup and Rates of Loading, 20051106.pdf (561 kb)
    - 134.00-06 Reliability and Testing Requirements, 20051107.pdf (253 kb)
    - 134.00-07 Maintenance, 20051108.pdf (404 kb)
    40. 1977-01-01---------Jump to [Top]
  40. Fluid Mechanics, Nuclear Training Course 223, January 1977, OPG, 1977-01-01. Doc type: Course.
    Summary: Basic fluid mechanics concepts (viscosity, friction, water hammer, pipe flow, lubrication).
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Course Objectives 20040300.pdf (82 kb)
    - Force - Momentum, 20040306.pdf (90 kb)
    - Water Hammer, 20040307.pdf (226 kb)
    41. 1977-04-01---------Jump to [Top]
  41. Reactor, Boilers and Auxiliaries, Nuclear Training Course 133, OPG, 1977-04-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Cover Page, Table of Contents, Basic Moderator Requirements 20041301.pdf (194 kb)
    - Moderator System & Equipment, 20041302.pdf (911 kb)
    - Basic Heat Transport Fluid Requirements, 20041303.pdf (274 kb)
    - Main Heat Transport Circuit Considerations, 20041304.pdf (1476 kb)
    - Auxiliary PHT System Features, 20041305.pdf (477 kb)
    - Shield Systems, 20041306.pdf (446 kb)
    - Annulus Gas System, 20041307.pdf (97 kb)
    - Containment Systems, 20041308.pdf (522 kb)
    - Reactivity Mechanisms, 20041309.pdf (233 kb)
    - Practical Reactivity Mechanisms, 20041310.pdf (161 kb)
    - Choice of Reactivity Mechanisms, 20041311.pdf (855 kb)
    - Fuel - Design and Manufacturing Features, 20041312.pdf (447 kb)
    - Fuel Performance and Operating Experience, 20041313.pdf (213 kb)
    42. 1978-01-01---------Jump to [Top]
  42. Efficient Integration over Discontinuities in Ordinary Differential Equation Simulation, by M.B. Carver, AECL, 1978-01-01. Doc type: Paper.
    Summary: Efficient integration algorithms for ordinary differential equations take integration steps that are as large as the error control criteria permit. Events or discontinuities in equation definition are often implicitly defined to occur when a variable reaches a critical value, for example a fuel rod surface reaching saturation temperature, and this requires the integrator to basically restart the calculation precisely at the point of change. Instead integrators will "hunt" for the discontinuity wasting a lot of computer time, and will eventually "step over" the discontinuity using integration points either side of the event. This paper shows that if the discontinuity is defined and monitored as an additional part of the equation set, such a restart can be optimized, thus ensuring that the event will be defined as an integration restart point.
    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] Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Mathematics and Computers in Simulation, XX, 1978 efficient-integration-over-discontinuities-in-ordinary-differential-equation.pdf (467 kb)
    43. 1978-04-01---------Jump to [Top]
  43. Fluid Mechanics, Nuclear Training Course 123, April 1978, OPG, 1978-04-01. Doc type: Course.
    Summary: Basic fluid mechanics concepts (viscosity, friction, water hammer, pipe flow, lubrication).  Note: Doc# 20040201 through to 20040205 are identical to OPG 223.00-1, rev January 1977 (see Doc# 20040301 through to 20040305
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Course Objectives 20040200.pdf (87 kb)
    - Parallel Pipe Flow, 20040206.pdf (202 kb)
    - Compressible Flow, 20040207.pdf (285 kb)
    - Water Hammer, 20040208.pdf (265 kb)
    - Hydrodynamic Film Lubrication, 20040209.pdf (562 kb)
  44. Fluid Mechanics, Nuclear Training Course 223, January 1977, OPG, 1978-04-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Viscosity 20040301.pdf (147 kb)
    - Reynolds' Number, 20040302.pdf (105 kb)
    - Friction in Fluid Flow, 20040303.pdf (301 kb)
    - Minor Losses, 20040304.pdf (213 kb)
    - Pipe Flow Problems, 20040305.pdf (132 kb)
    - Appendix, 20040308.pdf (489 kb)
    45. 1978-08-01---------Jump to [Top]
  45. 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)
    46. 1980-01-01---------Jump to [Top]
  46. Fundamentals of CANDU Reactor Nuclear Design (TDAI-244), by A.A. Pasanen, AECL, 1980-01-01. Doc type: Report.
    Summary: A Lecture Series given at Trieste 22 January - 28 March 1980, TDAI-244 1980 August
    Keywords: [Concept] - [SI] 31000 Reactor 37000 Fuel [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Manager Ugrad
    - Title and Table of Contents 20042000.pdf (176 kb)
    - Chapter 1 - Introduction, by A.A. Pasanen, 20042001.pdf (35 kb)
    - Chapter 2 - Physical Description of the CANDU-600, by A.A. Pasanen, 20042002.pdf (672 kb)
    - Chapter 3 - Methodology for Reactor Physics Analysis In Core Design, by A.A. Pasanen, 20042003.pdf (1922 kb)
    - Bibliography, by A.A. Pasanen, 20042006.pdf (111 kb)
  47. Pseudo-characteristic method of lines solution of first-order hyperbolic equation systems, by M.B. Carver, AECL, 1980-01-01. Doc type: Paper.
    Summary: This paper introduced a new concept, pseudo-characteristics, which allows the directionality dictated by the method of characteristics to be applied on a fixed grid basis. This is the method that N.P. Kolev Nuclear Institute of Bulgaria and M. B. Carver used to apply to the EVUT form of the thermalhydraulic conservation equations at the OECD/CSNI conference on two phase flow, Pasedena, 1981. In this MACS paper, discretization of the PDEs is discussed, using higher order upwind biased derivatives of each of the Lagrange polynomials and the Hermite polynomials. Results are shown for incompressible flow in a hydraulic jump and for compressible flow in the EVET 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] Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Mathematics and Computers in Simulation, 22, 1980 pseudo-characteristic-method-of-lines-solution-of-first-order-hyperbolic-equation.pdf (455 kb)
    48. 1980-08-01---------Jump to [Top]
  48. Nuclear Theory, Course 227, Nuclear Training Centre 20053700, by J.E. Crist, J. U. Burnham, A. Broughton, D. Winfield, OPG, 1980-08-01. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Full Course 20053700.pdf (8430 kb)
    - 227.00-00 Index and Objectives, by J. Crist, 20053701.pdf (443 kb)
    - 227.00-01 Nuclear Structure, by J. U. Burnham, J.E. Crist, A. Broughton, 20053702.pdf (274 kb)
    - 227.00-02 Neutron Reactions, by J. U. Burnham, J.E. Crist, 20053703.pdf (662 kb)
    - 227.00-03 Neutron Cross Sections, Neutron Density and Neutron Flux, by J. U. Burnham, J.E. Crist, A. Broughton, 20053704.pdf (318 kb)
    - 227.00-04 Thermal Reactors (Basic Design), by J.E. Crist, A. Broughton, 20053705.pdf (342 kb)
    - 227.00-05 Neutron Multiplication Factor and Reactivity, by J.E. Crist, 20053706.pdf (196 kb)
    - 227.00-06 Neutron Flux Distribution, by J.E. Crist, 20053707.pdf (324 kb)
    - 227.00-07 Effect of Fuel Burnup, by J.E. Crist, 20053708.pdf (361 kb)
    - 227.00-08 Changes in Reactor Power with Time, by J.E. Crist, 20053709.pdf (328 kb)
    - 227.00-09 Source Neuron Effects, by J.E. Crist, A. Broughton, 20053710.pdf (217 kb)
    - 227.00-10 Power and Power Measurement, by J.E. Crist, A. Broughton, 20053711.pdf (356 kb)
    - 227.00-11 Fission Product Poisoning, by J. U. Burnham, J.E. Crist, 20053712.pdf (866 kb)
    - 227.00-12 Reactivity Effects Due to Temperature Changes, by J.E. Crist, 20053713.pdf (454 kb)
    - 227.00-13 Reactivity Control, by J.E. Crist, A. Broughton, 20053714.pdf (875 kb)
    - 227.00-14 The Approach to Critical, by J.E. Crist, A. Broughton, 20053715.pdf (148 kb)
    - 227.00-15 Failed Fuel Monitoring, by D. Winfield, A. Broughton, 20053716.pdf (322 kb)
    - 227 Appendix A Symbols, 20053717.pdf (22 kb)
    - 227 Appendix B Properties of Elements and Certain Molecules, 20053718.pdf (120 kb)
    - 227 Appendix C Nuclides and Isotopes, 20053719.pdf (1921 kb)
    49. 1980-11-01---------Jump to [Top]
  49. Electrical Systems, Course 135, Nuclear Training Centre, OPG, 1980-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Full Course 20051300.pdf (1710 kb)
    - 135.00-00 Index and Objectives, 20051301.pdf (279 kb)
    - 135.01-01 Introduction to Symmetrical Components and Unbalanced Current, 20051302.pdf (185 kb)
    - 135.02-01 Unbalanced Currents: Their Effects, 20051303.pdf (252 kb)
    - 135.03-01 Further Examples of Electrical Protective Relays, 20051304.pdf (418 kb)
    - 135.04-01 Composite Electrical Protective Schemes: Part 1, 20051305.pdf (344 kb)
    - 135.05-01 Composite Electrical Protective Schemes: Part 2, 20051306.pdf (257 kb)
    50. 1981-01-01---------Jump to [Top]
  50. Memories of my Life as a Professional Engineer in the Royal Navy and the Canadian Boiler Industry, by J.M. Dyke, Individual Contributions, 1981-01-01. 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
    - Fran Gregory, Ed 20054000.pdf (2139 kb)
    51. 1981-04-01---------Jump to [Top]
  51. Thermal-Hydraulics in Recirculating Steam Generators: Thirst Code User's Manual, by M.B. Carver, AECL, 1981-04-01. Doc type: Report.
    Summary: THIRST is for modeling ThermalHydraulics In Recirculating Steam generators. This manual gives complete details of the mathematical derivation and numerical solution of the 3D, 2Phase thermalhydraulic equilibrium conservation equations inside a reactor boiler and also explains the many constitutive correlations required. Finally the manual fully defines the immense amount of input detail required to model the primary side heat transfer and the secondary side water boiling and recirculating in the complex tube-in-shell geometry of a prototypical CANDU steam generator.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - AECL 7254, April 1981 THIRSTusersR43667.pdf (2290 kb)
    52. 1981-11-01---------Jump to [Top]
  52. Heat and Thermodynamics, Course 125, Nuclear Training Centre, OPG, 1981-11-01. Doc type: Course.
    Summary: Basic concepts of heat and thermodynamics: steam tables, Mollier diagrams, turbine, feedheater, condenser, steam generator, reactor.
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Full Course 20050100.pdf (6328 kb)
    - Module B.7 Course Procedures, 20050101.pdf (302 kb)
    - Module B.6 Basics, 20050102.pdf (339 kb)
    - Module B.5 Steam Tables, 20050103.pdf (740 kb)
    - Module B.4.2 Entropy, Throttling and Molier Diagram, 20050104.pdf (904 kb)
    - Module B.4.1 Turbine With Reheat, 20050105.pdf (684 kb)
    - Module B.3.2 Feedheater Operation, 20050106.pdf (569 kb)
    - Module B.3.1 Condenser Performance, 20050107.pdf (594 kb)
    - Module B.2 Steam Generator, 20050108.pdf (477 kb)
    - Module B.1 Reactor, 20050109.pdf (826 kb)
    - B.6 Self Evaluation, 20050110.pdf (87 kb)
    - B.5 Self Evaluation, 20050111.pdf (69 kb)
    - B.4.2 Self Evaluation, 20050112.pdf (118 kb)
    - B.4.1 Self Evaluation, 20050113.pdf (103 kb)
    - B.3.2 Self Evaluation, 20050114.pdf (121 kb)
    - B.3.1 Self Evaluation, 20050115.pdf (118 kb)
    - B.2 Self Evaluation, 20050116.pdf (137 kb)
    - B.1 Self Evaluation, 20050117.pdf (102 kb)
    - Criterion Tests, 20050118.pdf (134 kb)
    53. 1982-01-01---------Jump to [Top]
  53. Electrical Equipment, Course 230.2, Nuclear Training Center, OPG, 1982-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Module 230.00 Introduction and Table of Contents 20050801.pdf (250 kb)
    - Module 230.21-1 Station Batteries and Battery Charges, 20050802.pdf (348 kb)
    - Module 230.22-1 Switchgear - Busbars and Cables, 20050803.pdf (188 kb)
    - Module 230.22-2 Switchgear - Motor Control Centres, 20050804.pdf (217 kb)
    - Module 230.22-3 Switchgear - Air Circuit Breakers, 20050805.pdf (203 kb)
    - Module 230.22-4 Switchgear - Vacuum Contactors, 20050806.pdf (80 kb)
    - Module 230.22-5 Switchgear - Disconnect Switches, Ground Switches and G.T.D's, 20050807.pdf (257 kb)
    - Module 230.22-6 Switchgear - Oil and Air Blast Breakers, 20050808.pdf (266 kb)
    - Module 230.22-7 Switchgear - Circuit Breaker Control, 20050809.pdf (241 kb)
    - Module 230.23-1 Transformers - Ratings, 20050810.pdf (206 kb)
    - Module 230.23-2 Transformers - Operating Procedures, 20050811.pdf (246 kb)
    - Module 230.24-1 Electrical Metering - Voltage and Circtuit Transformers, 20050812.pdf (200 kb)
    - Module 230.24-2 Electrical Metering - Voltage Couplers and Meters, 20050813.pdf (121 kb)
    - Module 230.25-1 Generators - Electrical and Magnetic Effects, 20050814.pdf (139 kb)
    - Module 230.25-2 Generators - Equivalent Circuits, 20050815.pdf (214 kb)
    - Module 230.25-3 Generators - Excitation Systems, 20050816.pdf (204 kb)
    - Module 230.25-4 Generators - Paralleling and Synchronizing, 20050817.pdf (176 kb)
    - Module 230.25-5 Generators - Infinite Bus Operation, 20050818.pdf (129 kb)
    - Module 230.25-6 Generators - Non-Infinite Bus Operation, 20050819.pdf (151 kb)
    - Module 230.25-7 Generators - Overfluxing, 20050820.pdf (120 kb)
    - Module 230.25-8 Generators - Loading, 20050821.pdf (272 kb)
    - Module 230.25-9 Generators - Operating Limitations, 20050822.pdf (168 kb)
    - Module 230.25-10 Generators - Laboratory AC Generator Project, 20050823.pdf (181 kb)
  54. A Method of Limiting Intermediate Volume Fraction in Iterative Two-Fluid Computations, by M.B. Carver, AECL, 1982-01-01. Doc type: Paper.
    Summary: This is seminal and the core contribution in Carver's thesis. The ICE guys, Harlow & Amsden and the IPSA guys, Spalding & Patankar had not got it quite right for air/water conditions where the water totally dominates the pressure field calculation when it is based on mass flux balance, as this is dominated by the water component and neglects continuity of the air. Herein, a volumetric balance fixes that and the calculation also converges better with the constraint mentioned in the title.
    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] Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Journal of Mechanical Engineering Science, Vol. 24, No. 2, 1982 limiting_volume_fraction_JMES_JOUR_1982.pdf (374 kb)
    55. 1982-02-01---------Jump to [Top]
  55. Instrumentation and Control, Course 136, OPG, 1982-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Course Index and Objectives 20042300.pdf (64 kb)
    - 136.00-12 Control Equipment Review, 20042301.pdf (229 kb)
    - 136.00-2 Control Theory Review, 20042302.pdf (491 kb)
    - 136.00-3 Control Mode Settings, 20042303.pdf (224 kb)
    - 136.00-4 Introduction to Frequency Response, 20042304.pdf (628 kb)
    - 136.00-5 Direct Digital Control of Processes, 20042305.pdf (249 kb)
    56. 1982-06-01---------Jump to [Top]
  56. Chemistry, Course PI 24, OPG, 1982-06-01. Doc type: Course.
    Summary: Heavy water production, water composition and treatment, moderator water and cover gas chemistry, heat transport system aspects, heavy water leakage, environmental monitoring and control, chemical cleaning, chemical analysis.
    Keywords: [Concept] Chemistry and Corrosion [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Chemistry [Topic] Corrosion Heavy Water Purification Radiation [Phase] Design Operation [Audience] College Engineer Ugrad
    - 24.00-0 Course Index and Checkout 20042700.pdf (62 kb)
    - 24.11-1 Isotopic Separation - General, 20042701.pdf (58 kb)
    - 24.11-2 Isotopic Separation - Deuterium and Hydrogen, 20042702.pdf (71 kb)
    - 24.11-3 Fractional Distillation, 20042703.pdf (102 kb)
    - 24.12-0 Heavy Water Production - Enriching, 20042704.pdf (24 kb)
    - 24.13-0 Heavy Water Production - Finishing Process, 20042705.pdf (23 kb)
    - 24.21-2 Chemical Additives and Blowdown, 20042706.pdf (166 kb)
    - 24.21-3 Make-Up Water Treatment Plant, 20042707.pdf (227 kb)
    - 24.21-4 Secondary System Materials, 20042708.pdf (21 kb)
    - 24.22-1 Moderator Cover Gas System - System Materials, 20042709.pdf (22 kb)
    - 24.22-2 Moderator Water Chemistry, 20042710.pdf (52 kb)
    - 24.22-3 Moderator Water - Purification, 20042711.pdf (37 kb)
    - 24.22-4 Cover Gas - Purity, 20042712.pdf (96 kb)
    - 24.23-1 Primary Heat Transport System - Materials, 20042713.pdf (18 kb)
    - 24.23-2 Comissioning (chemical conditioning) of the Primary Heat Transport System, 20042714.pdf (96 kb)
    - 24.23-3 Primary Heat Transport System Chemical and Impurity Control, 20042715.pdf (154 kb)
    - 24.23-4 Transport of Radioactivity in Nuclear Reactors, 20042716.pdf (265 kb)
    - 24.41-1 Heavy Water Leakage - Detection, 20042717.pdf (92 kb)
    - 24.42-1Heavy Water Leakage - Recovery by Molecular Sieves, 20042718.pdf (42 kb)
    - 24.30-1 Radioactive Materials - Management, 20042719.pdf (321 kb)
    - 24.51-1 Environmental Monitoring - Radiological Emissions, 20042720.pdf (182 kb)
    - 24.51-2 Environmental Monitoring - Radiological Emission Measurement, 20042721.pdf (69 kb)
    - 24.52-1 Environmental Monitoring and Control - BHWP, 20042722.pdf (36 kb)
    - 24.52-2 Environmental Monitoring and Control - General, 20042723.pdf (40 kb)
    - 24.60-1 Chemical Cleaning of Fouled Equipment, 20042724.pdf (132 kb)
    - 24.61-1 Chemical Cleaning - NGD experience, 20042725.pdf (21 kb)
    - 24.61-1AI Decontamination of Douglas Pt. Reactor by CAN-DECON process, 20042726.pdf (313 kb)
    - 24.61-1AII H.E. Fouling and Cleaning Experience in Ontario Hydro's Nuclear Generating Divisions, 20042727.pdf (278 kb)
    - 24.61-1AIII Reference #3, 20042728.pdf (349 kb)
    - 24.70-0 Chemical Analysis - General, 20042729.pdf (190 kb)
    57. 1984-03-01---------Jump to [Top]
  57. Heat and Thermodynamics, Course PI 25, Nuclear Training Centre, OPG, 1984-03-01. Doc type: Course.
    Summary: Basic concepts of heat and thermodynamics: expansion and contraction, heat transfer, pressure control, Mollier diagrams, efficiency, the CANDU cycle.
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Full Course 20050200.pdf (3028 kb)
    - 25-0 Introduction and Course Procedures, 20050201.pdf (336 kb)
    - 25-1 Basics, 20050202.pdf (471 kb)
    - 25-2 Expansion and Contraction, 20050203.pdf (351 kb)
    - 25-3 Heat Transfer Calculations, 20050204.pdf (183 kb)
    - 25-4 Pressure Control, 20050205.pdf (200 kb)
    - 25-5 Mechanisms of Heat Transfer, 20050206.pdf (144 kb)
    - 25-6 Mollier Diagrams and The Turbine Process, 20050207.pdf (679 kb)
    - 25-7 Efficiency and The CANDU Cycle, 20050208.pdf (298 kb)
    - 25-8 Criterion Tests, 20050209.pdf (105 kb)
    - 25-9 Self Evaluation Answer Sheet, 20050210.pdf (309 kb)
    58. 1984-12-01---------Jump to [Top]
  58. Fluid Mechanics, Nuclear Training Course 223, December 1984, OPG, 1984-12-01. Doc type: Course.
    Summary: These sections provide definitions and sample calculations for basic concepts such as pressure, density, flowrate, etc. and are NOT the same as the corresponding sections in the January 1977 version of 223.
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fuel Management [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Course Objectives 20040400.pdf (29 kb)
    - Fluid Mechanics, 20040401.pdf (599 kb)
    - Answer Section, 20040402.pdf (407 kb)
  59. Two Dimensional Modelling of the Homogenizing Effects of Flow Obstructions in Two Fluid Flow, by M.B. Carver and M. E. Salcudean, AECL, 1984-12-01. Doc type: Paper.
    Summary: It is well known that obstructions in two fluid flow have the effect of homogenizing the two fluid mixture, resulting not only in a more uniform phase distribution, but also in a significant reduction of the ratio of fluid velocities. This paper describes a 2D, 2Fluid computer program written by the first author to do proof of principal studies of 2fluid redistribution around bends and past obstacles. The details necessary for modelling air/water flows in these geometries have been introduced here before extending the work to 3D. The paper shows that these phase redistribution effects can be modelled using the two fluid computer program, and compares results to those obtained in a recent experiment on flow past obstructions.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Mathematics and Computers in Simulation 26(6):pp 475–484, December 1984 two-dimensional-modelling-of-the-homogenizing-effects-of-flow-obstructions.pdf (1202 kb)
    60. 1985-04-24---------Jump to [Top]
  60. 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)
    61. 1987-03-01---------Jump to [Top]
  61. Nuclear Journal of Canada, 1987 Vol 1 No. 1, by W.G. Morison, W. J. Penn, K. Hassmann, J.D. Stevenson, K. Elisson, CNS-, 1987-03-01. Doc type: Paper.
    Summary: This paper provides a summary of the designs and capabilities of principal containment systems associated with BWR, PWR, and PHWR reactors in operation and under construction in the United States, Canada, West Germany, and Sweden. The many conceptual differences in design and modes of operation following accidents are briefly described, with commentary on their evolution and alternatives considered.
    Keywords: [Concept] Component Design Details [SI] 20000 Buildings and Structures [Discipline] Civil Engineering Nuclear Engineering [Topic] Conceptual [Phase] Concept Construction Design [Audience] College Engineer Grad Ugrad
    - Containment Systems Capability NJC-1-1-08.pdf (1131 kb)
    62. 1987-04-01---------Jump to [Top]
  62. Development and Application of a Three-Dimensional Two-Fluid Numerical Algorithm for Simulation of Phase Redistribution by Bends and Obstructions, by M.B. Carver, AECL, 1987-04-01. Doc type: Other.
    Summary: Mike completed his Ph.D in parallel to his full time position at AECL as branch head of Applied Mathematics at CRNL. Upon completion he was appointed adjunct professor at McMaster and was co-supervisor of two degrees.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics#Mechanical Engineering [Topic] Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Ph.D Thesis, Department of Mechanical Engineering, University of Ottawa, April 1987 ThesisNL56352.pdf (4350 kb)
    63. 1987-06-01---------Jump to [Top]
  63. Nuclear Journal of Canada, 1987 Vol 1 No. 2, by M.B. Carver, R.A. Judd, J.E. Kiteley, and A. Tahir, CNS-, 1987-06-01. Doc type: Paper.
    Summary: The ASSERT subchannel code has been developed specifically to model flow and phase distributions within CANDU fuel bundles. ASSERT uses a drift-flux model that permits the phases to have unequal velocities, and can thus model phase separation tendencies that may occur in horizontal flow. The basic principles of ASSERT are outlined, and computed results are compared against data from various experiments for validation purposes. The paper concludes with an example of the use of the code to predict critical heat flux in CANDU geometries.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Fluid Mechanics [Phase] Design Analysis [Audience] Engineer Grad Ugrad
    - The Drift Flux Model in the ASSERTSubchannel Code NJC-1-2-08.pdf (742 kb)
    64. 1987-09-01---------Jump to [Top]
  64. Nuclear Journal of Canada, 1987 Vol 1 No. 3, by S.A. Usmani, CNS-, 1987-09-01. Doc type: Paper.
    Summary: CANDU-PHW nuclear power plants, whether in Canada or abroad, are thoroughly qualified to resist potential earthquakes because of the great emphasis placed on nuclear safety. CANDU Plants have been seismically qualified dynamically since the mid-1960s, with ever-increasing requirements for each new plant. The approach now employed in Canada for seismic qualification of CANDU equipment and systems is described in this paper.
    Keywords: [Concept] Component Design Details [SI] 20000 Buildings and Structures [Discipline] Civil Engineering [Topic] - [Phase] Design [Audience] College Engineer Grad Ugrad
    - Seismic Qualification of CANDU-PHW Nuclear Power Plant Equipment NJC-1-3-03.pdf (660 kb)
    - Multifield Methods for Nuclear Thermalhydraulics Problems, by S. Banerjee, NJC-1-3-04.pdf (1030 kb)
    65. 1987-12-01---------Jump to [Top]
  65. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by J.F. Lafortune, C.A. McDevitt and S. Poolpol, CNS-, 1987-12-01. Doc type: Paper.
    Summary: CANDU reactor containment buildings are checked for integrity every five years. An on-line test could be performed more often, thereby reducing long-term unavailability of the containment system. A test procedure which accounts for operational factors is proposed.
    Keywords: [Concept] Component Design Details [SI] 20000 Buildings and Structures [Discipline] Civil Engineering Nuclear Engineering [Topic] Conceptual [Phase] Concept Construction Design [Audience] College Engineer Grad Ugrad
    - Suitability Study of On-Line Leak Tests for CANDU Single-Unit Containment Buildings NJC-1-4-05.pdf (846 kb)
    - Trivac: A Modular Diffusion Code for Fuel Management and Design Applications, by Alain Hebert, NJC-1-4-06.pdf (472 kb)
    - Fuel for Thought, by J.A.L. Robertson, NJC-1-4-07.pdf (876 kb)
    66. 1988-04-01---------Jump to [Top]
  66. Heat and Thermodynamics, Course 225, Nuclear Training Centre, OPG, 1988-04-01. Doc type: Course.
    Summary: Basic concepts of heat and thermodynamics: steam tables, Mollier diagrams, turbine with reheat, feedheater, condenser, steam generator, reactor.
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Full Course 20043100.pdf (4667 kb)
    - Index, 20043101.pdf (208 kb)
    - Module 1 Basics, 20043102.pdf (404 kb)
    - Module 2 Steam Tables, 20043103.pdf (636 kb)
    - Module 3 Entropy, Throttling and Mollier Diagrams, 20043104.pdf (701 kb)
    - Module 4 Turbine with Reheat, 20043105.pdf (611 kb)
    - Module 5 Feedheater Operation, 20043106.pdf (511 kb)
    - Module 6 Condenser Performance, 20043107.pdf (546 kb)
    - Module 7 Steam Generator, 20043108.pdf (382 kb)
    - Module 8 Reactor, 20043109.pdf (710 kb)
    67. 1990-01-01---------Jump to [Top]
  67. Mechanical Equipment, Course PI 30.1, Nuclear Training Centre, OPG, 1990-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03200 Mechanical Engineering [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Operation [Audience] College Engineer Technician Ugrad
    - Full Course 20043200.pdf (5736 kb)
    - PI 30.10-0 Introduction and Objectives, 20043201.pdf (392 kb)
    - 430.10-0 Identification and Coding of Mechanical Equipment, 20043202.pdf (251 kb)
    - 430.10-1 Centrifugal Pumps, 20043203.pdf (379 kb)
    - 330.10-1 Centrifugal Pumps, 20043204.pdf (795 kb)
    - 430.10-2 Positive Displacement Pumps, 20043205.pdf (168 kb)
    - 430.10-3 Compressonrs - Dynamic and Positive Displacement, 20043206.pdf (270 kb)
    - 430.10-4 Air System, 20043207.pdf (82 kb)
    - 430.10-5 Fans, 20043208.pdf (57 kb)
    - 430.10-6 Vacuum Pumps, 20043209.pdf (185 kb)
    - 230.11-1 Compressors, 20043210.pdf (226 kb)
    - 330.11-1 Heat Exchangers, 20043211.pdf (218 kb)
    - 430.12-1 Piping and Tubes, 20043212.pdf (271 kb)
    - 430.13-1 Valves, 20043213.pdf (513 kb)
    - 430.14-1 Lubrification, 20043214.pdf (143 kb)
    - 430.14-2 Unit 1 Bearings, 20043215.pdf (68 kb)
    - 430.14-2 Unit 2 Lubrification Methods, 20043216.pdf (62 kb)
    - 430.14-2 Unit 3 Bearing Design and Installation, 20043217.pdf (81 kb)
    - 230.12-1 Lubrification, 20043218.pdf (250 kb)
    - 430.15-1 Sealing Devices, 20043219.pdf (181 kb)
    - 330.14-1 Axial Mechanical Seals, 20043220.pdf (190 kb)
    - 230.13-1 Shaft Couplings, 20043221.pdf (204 kb)
    - 230.13-2 Belt Drives, 20043222.pdf (247 kb)
    - 230.13-3 Chain Drives, 20043223.pdf (115 kb)
    - 230.13-4 Gears and Gearing, 20043224.pdf (250 kb)
    - 230.16-1 Gas Turbines, 20043225.pdf (289 kb)
  68. Nuclear Theory, Course PI 27 , Nuclear Training Centre, OPG, 1990-01-01. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Full Course 20050600.pdf (6624 kb)
    - PI 27.00-00 Index and Objectives, 20050601.pdf (389 kb)
    - 427.00-02 Radioactivity - Spontaneous Nuclear Processes, 20050602.pdf (282 kb)
    - 227.00-01 Nuclear Structure, 20050603.pdf (217 kb)
    - 227.00-02 Neutron Reactions, 20050604.pdf (559 kb)
    - 227.00-03 Neutron Cross Sections, Neutron Density and Neutron Flux, 20050605.pdf (300 kb)
    - 227.00-04 Thermal Reactors (Basic Design), 20050606.pdf (338 kb)
    - 227.00-05 Neutron Multiplication Factor and Reactivity, 20050607.pdf (193 kb)
    - 227.00-06 Neutron Flux Distribution, 20050608.pdf (314 kb)
    - 227.00-07 Effect of Fuel Burnup, 20050609.pdf (467 kb)
    - 227.00-08 Changes in Reactor Power with Time, 20050610.pdf (357 kb)
    - 227.00-09 Source Neutron Effects, 20050611.pdf (294 kb)
    - 227.00-10 Reactor and Power Measurement, 20050612.pdf (509 kb)
    - 227.00-11 Fission Product Poisoning, 20050613.pdf (999 kb)
    - 227.00-12 Reactivity Effects Due to Temperature Changes, 20050614.pdf (409 kb)
    - 227.00-13 Reactivity Control, 20050615.pdf (782 kb)
    - 227.00-14 The Approach to Critical, 20050616.pdf (295 kb)
  69. Electrical Equipment, Course PI 30.2, Nuclear Training Center, OPG, 1990-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Full Course 20050700.pdf (4615 kb)
    - Table of Contents, 20050701.pdf (234 kb)
    - PI 26.34-1 Impedance, 20050702.pdf (159 kb)
    - PI 26.35-1 Three Phase Systems, 20050703.pdf (282 kb)
    - PI 26.35-2 Power and Power Factor, 20050704.pdf (190 kb)
    - PI 30.20-1 The CANDU Generating Station, 20050705.pdf (150 kb)
    - PI 30.21-1 Conductors, 20050706.pdf (379 kb)
    - PI 30.21-2 Insulation, 20050707.pdf (221 kb)
    - PI 30.21-3 Fuses, 20050708.pdf (323 kb)
    - PI 30.21-4 Disconnect Switches and Circuit Breakers, 20050709.pdf (506 kb)
    - PI 30.22-1 Transformers, 20050710.pdf (360 kb)
    - PI 30.23-1 AC Generators, 20050711.pdf (357 kb)
    - PI 30.23-2 Generator Auxiliary Systems, 20050712.pdf (404 kb)
    - PI 30.24-1 Motors, 20050713.pdf (327 kb)
    - PI 30.24 Appendix A, 20050714.pdf (77 kb)
    - PI 30.25-1 Motor Control, 20050715.pdf (361 kb)
    - PI 30.26-1 Batteries, 20050716.pdf (361 kb)
  70. Turbine and Auxiliaries, Course PI 34 / TIMS Ref. PI 3004, Nuclear Training Centre, OPG, 1990-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Full Course 20051000.pdf (11938 kb)
    - PI 34.00-00 Index and Objectives, 20051001.pdf (619 kb)
    - 334.00-01 The Steam Turbine, 20051002.pdf (676 kb)
    - 234.00-01 Turbine Construction, 20051003.pdf (1037 kb)
    - 334.00-03 The Steam System, 20051004.pdf (517 kb)
    - 234.00-02 Steam Control to the Turbine, 20051005.pdf (514 kb)
    - 334.00-07 The Condenser, 20051006.pdf (476 kb)
    - PI 25-06 The Mollier Diagram and the Turbine Processes, 20051007.pdf (1214 kb)
    - 334.00-08 Feedwater Heating System -1, 20051008.pdf (212 kb)
    - 334.00-09 Feedwater Heating System -2, 20051009.pdf (307 kb)
    - 234.00-07 Feedwater Control and Operation, 20051010.pdf (586 kb)
    - PI 24.21-01 Secondary Heat Transport System - Impurities, 20051011.pdf (230 kb)
    - PI 24.21-02 Chemical Additives and Blowdown, 20051012.pdf (274 kb)
    - PI 25-07 Efficiency of the CANDU Turbine Cycle, 20051013.pdf (513 kb)
    - 234.00-03 Steam Valve Hydraulic Control, 20051014.pdf (255 kb)
    - 234.00-04 Governor Operation, 20051015.pdf (516 kb)
    - 234.00-05 Turbine Governors, 20051016.pdf (677 kb)
    - 334.00-10 The Lubricating Oil System, 20051017.pdf (275 kb)
    - 334.00-11 The Turning Gear, 20051018.pdf (113 kb)
    - 234.00-06 Turbine Operational Problems, 20051019.pdf (568 kb)
    - 234.00-08 Factors Limiting Startup and Rates of Loading, 20051020.pdf (887 kb)
    - 334.00-13 appendix 1 Ontario Hydro Nuclear Turbine Types, 20051021.pdf (245 kb)
    71. 1990-07-01---------Jump to [Top]
  71. Nuclear Theory, Course 427, Nuclear Training Centre, OPG, 1990-07-01. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Full Course 20050500.pdf (2088 kb)
    - 427.00-00 Index and Objectives, 20050501.pdf (246 kb)
    - 427.00-01 Atomic Structures, 20050502.pdf (108 kb)
    - 427.00-02 Radioactivity, 20050503.pdf (212 kb)
    - 427.00-03 Nuclear Stability and Instability, 20050504.pdf (150 kb)
    - 427.00-04 Activity, 20050505.pdf (117 kb)
    - 427.00-05 Neutrons and Neutron Interactions, 20050506.pdf (107 kb)
    - 427.00-06 Fission, 20050507.pdf (220 kb)
    - 427.00-07 Fuel, Moderator and Reactor Arrangement, 20050508.pdf (141 kb)
    - 427.00-08 Neutron Life Cycle, 20050509.pdf (101 kb)
    - 427.00-09 Criticality and Neutron Multiplication, 20050510.pdf (183 kb)
    - 427.00-10 Changes in Reactor Power with Time, 20050511.pdf (149 kb)
    - 427.00-11 Xenon : A Fission Product Poison, 20050512.pdf (124 kb)
    - 427.00-12 Reactivity Effects Due to Temperature Changes, 20050513.pdf (133 kb)
    - 427.00-13 Neutron Flux Control, 20050514.pdf (156 kb)
    72. 1991-08-01---------Jump to [Top]
  72. Chernobyl – A Canadian Perspective, by V.G. Snell and J.Q. Howieson, AECL, 1991-08-01. Doc type: Report.
    Summary: This brochure looks at the Canadian CANDU (CANada Deuterium Uranium) reactor to see how it stacks up in its ability to tolerate the sorts of mistakes that were made at Chernobyl.
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Concept Design Operation Safety [Audience] Engineer Manager Vendor
    - 19910101.pdf (398 kb)
    73. 1992-06-01---------Jump to [Top]
  73. Reactor Boiler and Auxiliaries, Course 233, Nuclear Training, OPG, 1992-06-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Full Course 20053800.pdf (13185 kb)
    - Abstract and Table of Contents, 20053801.pdf (162 kb)
    - Module 0 - Introduction, 20053802.pdf (269 kb)
    - Module 1 - Moderator Heavy Water, 20053803.pdf (359 kb)
    - Module 2 - Moderator Circulation System, 20053804.pdf (418 kb)
    - Module 3 - Moderator Cover Gas System, 20053805.pdf (387 kb)
    - Module 4 - The Moderator Liquid Poison System, 20053806.pdf (578 kb)
    - Module 5 - The Moderator Purification System, 20053807.pdf (486 kb)
    - Module 6 - HTS Heat Sources and Heat Transfer Paths, 20053808.pdf (362 kb)
    - Module 7 - HTS Pressure and Inventory Control, 20053809.pdf (1482 kb)
    - Module 8 - Heat Transport System Shutdown Operation, 20053810.pdf (609 kb)
    - Module 9 - HTS Heavy Water, 20053811.pdf (602 kb)
    - Module 10 - Heat Transport System Auxiliaries, 20053812.pdf (755 kb)
    - Module 11 - Shutdown Systems, 20053813.pdf (704 kb)
    - Module 12 - Emergency Coolant Injection, 20053814.pdf (663 kb)
    - Module 13 - Containment, 20053815.pdf (1004 kb)
    - Module 14 - Annulus Gas System, 20053816.pdf (407 kb)
    - Module 15 - Shield Cooling Systems, 20053817.pdf (528 kb)
    - Module 16 - Fuel Performance, 20053818.pdf (751 kb)
    - Module 17 - Fuel Handling, 20053819.pdf (616 kb)
    - Module 18 - Unit Upsets, 20053820.pdf (1950 kb)
    74. 1992-07-01---------Jump to [Top]
  74. Electrical Systems, Course 235, OPG, 1992-07-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Module 235.00 Introduction 20042900.pdf (114 kb)
    - Module 235.01 Unit Service Power, 20042901.pdf (305 kb)
    - Module 235.02 Ring Bus Configuration, 20042902.pdf (103 kb)
    - Module 235.03 Electrical Protection Schemes, 20042903.pdf (87 kb)
    - Module 235.04 Application of Electrical Protection Schemes in the Power Station, 20042904.pdf (189 kb)
    - Module 235.05 Electric Motor Protection, 20042905.pdf (420 kb)
    - Module 235.06 Power Transformer Protection, 20042906.pdf (253 kb)
    - Module 235.07 Generator Protection, 20042907.pdf (374 kb)
    - Module 235.08 Generator and Transmission Line Stability, 20042908.pdf (682 kb)
    - Appendix A Power Transfer Equation, 20042909.pdf (48 kb)
    75. 1992-08-01---------Jump to [Top]
  75. Nuclear Theory, Nuclear Training Course 227 20031001, OPG, 1992-08-01. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations. Revised by N. Ritter.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Cover pages and table of contents 20031001.pdf (76 kb)
    - Objectives, 20031002.pdf (164 kb)
    - Chapter 1: Nuclear Structure, 20031003.pdf (213 kb)
    - Chapter 2: Neutron Reactions, 20031004.pdf (631 kb)
    - Chapter 3: Neutron Cross Sections, Neutron Density and Neutron Flux, 20031005.pdf (289 kb)
    - Chapter 4: Thermal Reactors (Basic Design), 20031006.pdf (317 kb)
    - Chapter 5: Neutron Multiplication Factor and Reactivity, 20031007.pdf (184 kb)
    - Chapter 6: Neutron Flux Distribution, 20031008.pdf (321 kb)
    - Chapter 7: Effect of Fuel Burnup, 20031009.pdf (395 kb)
    - Chapter 8: Changes in Reactor Power with Time, 20031010.pdf (314 kb)
    - Chapter 9: Source Neutron Effects, 20031011.pdf (307 kb)
    - Chapter 10: Power and Power Measurements, 20031012.pdf (356 kb)
    - Chapter 11: Fission Product Measurement, 20031013.pdf (838 kb)
    - Chapter 12: Reactivity Effects due to Temperature Changes, 20031014.pdf (406 kb)
    - Chapter 13: Reactivity Control, 20031015.pdf (732 kb)
    - Chapter 14: The Approach to Critical, 20031016.pdf (384 kb)
    - Appendix: A: Symbols, 20031017.pdf (23 kb)
    - Appendix: B: Properties of Elements and Certain Molecules, 20031018.pdf (105 kb)
    - Appendix: C: Nuclides and Isotopes, 20031019.pdf (1547 kb)
    76. 1992-10-01---------Jump to [Top]
  76. Chemistry, Nuclear Training Course 224, OPG, 1992-10-01. Doc type: Course.
    Summary: Reviews the chemical technology fundamentals and addresses the chemistry-realated concerns of the condensate, feedwater and boiler system, the moderator system, the heat trnsport system, the liquid zone control system and the irradiated fuel bay.
    Keywords: [Concept] Chemistry and Corrosion [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Chemistry [Topic] Corrosion Heavy Water Purification Radiation [Phase] Design Operation [Audience] College Engineer Ugrad
    - Cover page, Table of contents, Introduction 20040800.pdf (382 kb)
    - A Review of 424, 20040801.pdf (753 kb)
    - The Condensate, Feedwater and Boiler System, 20040802.pdf (967 kb)
    - The Moderator and Auxiliary Systems, 20040803.pdf (1005 kb)
    - The Heat Transport and Auxiliary Systems, 20040804.pdf (511 kb)
    - Auxiliary Systems: Liquid Zone Control, Irradiated Fuel Bay, 20040805.pdf (447 kb)
    77. 1993-01-01---------Jump to [Top]
  77. Principes de Science et de Fonctionnement des Réacteurs - 20070500, CNSC, 1993-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] - [Phase] Concept Design [Audience] College Engineer Manager Technician Ugrad
    - Réacteurs à Neutrons Intermédiaires et Auxiliaires 20070500.pdf (2850 kb)
    - Réacteurs à Neutrons Intermédiaires et Auxiliaires - Systèmes Spéciaux de Sûreté, 20070501.pdf (237 kb)
    - Réacteurs à Neutrons Intermédiaires et Auxiliaires - Combustible, 20070502.pdf (280 kb)
    - Réacteurs à Neutrons Intermédiaires et Auxiliaires - CC, 20070503.pdf (1500 kb)
    - Réacteurs à Neutrons Intermédiaires et Auxiliaires - Réacteurs à Neutrons Intermédiaires et Auxiliaires, 20070504.pdf (961 kb)
    - Réacteurs à Neutrons Intermédiaires et Auxiliaires - Circuits du Réacteur, 20070505.pdf (421 kb)
  78. Principes de Science et de Fonctionnement des Réacteurs, CNSC, 1993-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design [Audience] Engineer Ugrad
    - Physique du Réacteur 20070800.pdf (1388 kb)
  79. Principes de Science et de Fonctionnement des Réacteurs - Chaleur et Thermodynamique, CNSC, 1993-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Chaleur et Thermodynamique 20070900.pdf (850 kb)
    80. 1993-02-01---------Jump to [Top]
  80. A Short History of the CANDU Nuclear Power System, by Gordon L. Brooks, AECL, 1993-02-01. Doc type: Paper.
    Summary: This paper provides a short historical summary of the evolution of the CANDU nuclear power system with emphasis on the roles played by Ontario Hydro and private sector companies in Ontario in collaboration with Atomic Energy of Canada Limited (AECL).
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Operation [Audience] College Engineer Manager Ugrad
    - 19930101.pdf (214 kb)
  81. Reactor, Boiler and Accessories, Course 233, OPG, 1993-02-01. Doc type: Course.
    Summary: Table of contents and Objectives for Course 233, Reactor, Boiler, and Auxiliaries.
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Table of Contents and Objectives 20042200.pdf (640 kb)
    - 233.20-1 Moderator and Main Moderator System, 20042201.pdf (485 kb)
    - 233.20-2 Moderator Purification, 20042202.pdf (241 kb)
    - 233.20-3 Moderator Cover Gas System, 20042203.pdf (202 kb)
    - 233.20-4 Moderator D2O Collection, 20042204.pdf (117 kb)
    - 233.20-5 Moderator Liquid Poison System, 20042205.pdf (343 kb)
    - 233.30-1 Heat Transport D2O and Heat Transport Main System, 20042206.pdf (284 kb)
    - 233.30-2 Heat Transport Pressurizing System, 20042207.pdf (277 kb)
    - 233.30-3 Heat Transport Purification, 20042208.pdf (235 kb)
    - 233.30-4 Heat Transport Gland Seal Circuit, 20042209.pdf (165 kb)
    - 233.30-5 Heat Transport Shutdown Cooling, 20042210.pdf (144 kb)
    - 233.30-6 Heat Transport Maintenance Cooling System, 20042211.pdf (56 kb)
    - 233.30-7 Heat Transport H2 Addition, 20042212.pdf (132 kb)
    - 233.30-8 Heat Transport Pressure Relief, 20042213.pdf (204 kb)
    - 233.30-9 Heat Transport D2O Collection, 20042214.pdf (100 kb)
    - 233.30-10 Heat Transport D2O Recovery, 20042215.pdf (113 kb)
    - 233.30-11 Emergency Coolant Injection System, 20042216.pdf (197 kb)
    - 233.30-12 Heat Sources and Transfer Paths, 20042217.pdf (271 kb)
    - 233.40-1 Shield Cooling Systems, 20042218.pdf (250 kb)
    - 233.40-2 Containment System, 20042219.pdf (462 kb)
    - 233.40-3 Annulus Gas System, 20042220.pdf (95 kb)
    - 233.60-1 Steam Supply System, 20042221.pdf (383 kb)
    - 233.70-1 Fuel Design and Manufacturing Features, 20042222.pdf (377 kb)
    - 233.70-2 Fuel Performance and Operating Features, 20042223.pdf (521 kb)
    82. 1993-06-01---------Jump to [Top]
  82. Materials, Nuclear Training Course 228, OPG, 1993-06-01. Doc type: Course.
    Summary: General material properties and the approach to material selection for CANDU reactors. Failure modes of materials, both mechanical and radiation induced. Pressure tube problems.
    Keywords: [Concept] Materials [SI] 31000 Reactor [Discipline] Materials Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Material Properties and Selection: Cover page, Table of contents, Introduction 20040900.pdf (140 kb)
    - Material Properties and Selection: Basic Material Properties and How They Can Be Altered, 20040901.pdf (553 kb)
    - Material Properties and Selection: Common Mechanical-Based Failure Modes, 20040902.pdf (870 kb)
    - Material Properties and Selection: Selection and Specification of Materials for Nuclear Applications, 20040903.pdf (514 kb)
    - Effect of Radiation on Materials: Radiation Damage to Materials, 20040904.pdf (547 kb)
    - Effect of Radiation on Materials: Problems with Pressure Tubes, 20040905.pdf (612 kb)
    83. 1994-07-01---------Jump to [Top]
  83. Turbine and Auxiliaries, Nuclear Training Course 234, OPG, 1994-07-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Module 234-00 Introduction to the Course 20042400.pdf (182 kb)
    - Module 234-01 The Steam Turbine, 20042401.pdf (760 kb)
    - Module 234-02 The Boiler, 20042402.pdf (851 kb)
    - Module 234-03 The Main Steam System, 20042403.pdf (1399 kb)
    - Module 234-04 Auxiliary Steam Systems, 20042404.pdf (684 kb)
    - Module 234-05 The Condenser and its Auxiliary Systems, 20042405.pdf (1091 kb)
    - Module 234-06 The Condensate, the Boiler Feed and Their Auxiliary Systems, 20042406.pdf (1736 kb)
    - Module 234-07 The Turbine Governing System, 20042407.pdf (724 kb)
    - Module 234-08 The Turbine Supervisory System, 20042408.pdf (273 kb)
    - Module 234-09 The Turning Gear, 20042409.pdf (305 kb)
    - Module 234-10 The Turbine Lubricating System, 20042410.pdf (503 kb)
    - Module 234-11 Startup and Loading, 20042411.pdf (1220 kb)
    - Module 234-12 Unloading and Shutdown, 20042412.pdf (333 kb)
    - Module 234-13 Special Modes of Operation and Accidents, 20042413.pdf (895 kb)
    - Module 234-14 Turbine Operational Problems, 20042414.pdf (850 kb)
    84. 1994-09-01---------Jump to [Top]
  84. Mechanical Equipment, Course 23001, OPG, 1994-09-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03200 Mechanical Engineering [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Operation [Audience] College Engineer Technician Ugrad
    - Full Course 20042800.pdf (1261 kb)
    - Intro and Table of Contents, 20042801.pdf (44 kb)
    - Module 1 Centrifugal Pumps and Systems, 20042802.pdf (1034 kb)
    - Module 2 Positive Displacement Compressor Operation, 20042803.pdf (194 kb)
    85. 1995-06-25---------Jump to [Top]
  85. 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)
    86. 1995-08-01---------Jump to [Top]
  86. 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)
    87. 1995-09-11---------Jump to [Top]
  87. Synergistic Nuclear Fuel Cycles of the Future, by D.A. Meneley, A.R. Dastur, P.J. Fehrenbach and K.H. Talbot, AECL, 1995-09-11. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Fuel Management [Phase] Concept Design Operation [Audience] Engineer Manager
    - Global 1995, International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France 20054701.pdf (504 kb)
    - Global 1995, International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France, by D.A. Meneley, A.R. Dastur, P.J. Fehrenbach and K.H. Talbot, 20054702.pdf (443 kb)
    88. 1996-01-01---------Jump to [Top]
  88. Reactor Physics & Fuelling Strategies 1.4, by R.D. Page, Chulalongkorn University, 1996-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Reference to Lecture 10 - Canadian Power Reactor Fuel 20042115.pdf (2381 kb)
    - Reference to Lecture 12 - Results of a Survey on Accident and Safety Analysis Codes, Benchmarks. Verification and Validation Methods, by A.G. Lee and G.B. Wilkin, 20042117.pdf (482 kb)
    89. 1996-02-01---------Jump to [Top]
  89. Nuclear Physics and Reactor Theory 1.1, by Ian Cameron, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Title and Table of Contents 20041100.pdf (132 kb)
    - Module 1 - Nuclear Structure, by Ian Cameron, 20041101.pdf (451 kb)
    - Module 2 - Neutron Reactions, by Ian Cameron, 20041102.pdf (783 kb)
    - Module 3 - Neutron Cross-Sections, Neutron Density and Neutron Flux, by Ian Cameron, 20041103.pdf (488 kb)
    - Module 4 - Thermal Reactors (Basic Design), by Ian Cameron, 20041104.pdf (413 kb)
    - Module 5 - Neutron Multiplication Factor and Reactivity, by Ian Cameron, 20041105.pdf (384 kb)
    - Module 6 - Neutron Flux Distribution, by Ian Cameron, 20041106.pdf (313 kb)
    - Module 7 - Effects of Fuel Burnup, by Ian Cameron, 20041107.pdf (472 kb)
    - Module 8 - Reactor Power Response to Changes in Reactivity, by Ian Cameron, 20041108.pdf (574 kb)
    - Module 9 - Source Neutron Effects, by Ian Cameron, 20041109.pdf (278 kb)
    - Module 10 - Power and Power Measurement, by Ian Cameron, 20041110.pdf (421 kb)
    - Module 11 - Fission Product Poisoning, by Ian Cameron, 20041111.pdf (695 kb)
    - Module 12 - Reactivity Effects Due to Temperature Changes and Coolant Voiding, by Ian Cameron, 20041112.pdf (678 kb)
    - Module 13 - Reactivity Control, by Ian Cameron, 20041113.pdf (678 kb)
    - Module 14 - The Approach To Critical, by Ian Cameron, 20041114.pdf (315 kb)
    - Module 15 - Neutron Detectors And Reactor Instrumentation, by Ian Cameron, 20041115.pdf (639 kb)
    - Appendix A, by Ian Cameron, 20041116.pdf (72 kb)
  90. Nuclear Theory II (Kinetics) 1.2, by John L. Groh, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Supplement to Chapter 8 20041201.pdf (428 kb)
    - Supplement to Chapter 9, by John L. Groh, 20041202.pdf (218 kb)
    - Supplement to Chapter 10, by John L. Groh, 20041203.pdf (147 kb)
    - Supplement to Chapter 11, by John L. Groh, 20041204.pdf (263 kb)
    - Supplement to Chapter 12, by John L. Groh, 20041205.pdf (96 kb)
    - Supplement to Chapter 13, by John L. Groh, 20041206.pdf (139 kb)
    - Supplement to Chapter 14, by John L. Groh, 20041207.pdf (147 kb)
    - Workbook, Chapter 8, by John L. Groh, 20041208.pdf (449 kb)
    - Workbook, Chapter 9, by John L. Groh, 20041209.pdf (183 kb)
    - Workbook, Chapter 10, by John L. Groh, 20041210.pdf (128 kb)
    - Workbook, Chapter 11, by John L. Groh, 20041211.pdf (403 kb)
    - Workbook, Chapter 12, by John L. Groh, 20041212.pdf (525 kb)
    - Workbook, Chapter 13, by John L. Groh, 20041213.pdf (128 kb)
    - Workbook, Chapter 14, by John L. Groh, 20041214.pdf (301 kb)
  91. 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)
  92. Reactor Physics & Fuelling Strategies 1.4, by John Brenciaglia, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: Descriptive reactor physics associated with fuel management. Simulation, flux mapping. Reference text used: Fundamentals of CANDU Reactor Nuclear Design (TDAI-244) (AECL)
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Lecture 1 - Reactor Design Philosophies 20042101.pdf (665 kb)
    - Lecture 2 - Use of Reactor Design Codes, by John Brenciaglia, 20042102.pdf (137 kb)
    - Lecture 3 - Lattice Parameter Calculations, by John Brenciaglia, 20042103.pdf (531 kb)
    - Lecture 4 - Core Design Analysis, by John Brenciaglia, 20042104.pdf (332 kb)
    - Lecture 5 - Time Dependence Simulation, by John Brenciaglia, 20042105.pdf (600 kb)
    - Lecture 6 - Initial Fuel Load, by John Brenciaglia, 20042106.pdf (253 kb)
    - Lecture 7 - Startup Physics Tests, by John Brenciaglia, 20042107.pdf (531 kb)
    - Lecture 8 - Power Distribution Control, by John Brenciaglia, 20042108.pdf (720 kb)
    - Lecture 9 - Safety Analysis Requirements, by John Brenciaglia, 20042109.pdf (392 kb)
    - Chapter 10 - Fuel Design Analysis, by John Brenciaglia, 20042110.pdf (187 kb)
    - Lecture 11 - Fueling Strategies and Cycles, by John Brenciaglia, 20042111.pdf (745 kb)
    - Lecture 12 - Research Reactors Requirements, by John Brenciaglia, 20042112.pdf (138 kb)
    - Reference to Lecture 8 - In-Core Fuel Management, by D.A. Jenkins, 20042113.pdf (1105 kb)
    - Reference to Lecture 9 - Role of Physics Analysis in Safety and Licensing, by H.C. Chow, 20042114.pdf (1389 kb)
    - Reference to Lecture 11 - Fuel Management & Reactor Operation - Review of Operating Experience, by G.M. Frescura and A.L. Wight, 20042116.pdf (1501 kb)
  93. 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)
  94. 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)
  95. 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)
  96. 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)
  97. Nuclear Power Plant Control & Simulaion, Course 3.4, by G. Bereznai, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Workbook, Chapter 1 - Modules A & B 20044401.pdf (644 kb)
    - Workbook, Chapter 2 - Modules A to F, by G. Bereznai, 20044402.pdf (3512 kb)
    - Workbook, Chapter 3 - Modules A to I, by G. Bereznai, 20044403.pdf (4141 kb)
    - Workbook, Chapter 4 - Modules A to D, by G. Bereznai, 20044404.pdf (2750 kb)
    - Workbook, Chapter 5 - Modules A to C, by G. Bereznai, 20044405.pdf (1554 kb)
  98. Nuclear Reactor Containment, Course 3.5, by J. Daams, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 20000 Buildings and Structures [Discipline] Civil Engineering [Topic] Conceptual Modelling [Phase] Concept Design [Audience] Engineer Grad Ugrad
    - Reference 1 - Requirements for Containment Systems for Nuclear Power Plants - Doc R7 20044501.pdf (2064 kb)
    - Reference 2 - Real Time Simulation of the Containment by A. Hodhod, L. Vindigni, H. Dana, by J. Daams, 20044502.pdf (1353 kb)
    - Reference 3 - ANSI 3.5, by J. Daams, 20044503.pdf (591 kb)
    - Reference 4 - Recent Advances in Concrete Containment Vessels in Japan by T.Koroda, T.Ebine, S.Sato, M. Kato, by J. Daams, 20044504.pdf (1353 kb)
    - Workbook, Chapter 0 - Title, Objectives, by J. Daams, 20044505.pdf (38 kb)
    - Workbook, Chapter 1 - Modules A to D, by J. Daams, 20044506.pdf (1317 kb)
    - Workbook, Chapter 2 - Modules A to C, by J. Daams, 20044507.pdf (1045 kb)
    - Workbook, Chapter 3 - Modules Ato E, by J. Daams, 20044508.pdf (1723 kb)
    - Workbook, Chapter 4 - Modules A to F, by J. Daams, 20044509.pdf (1628 kb)
  99. 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)
  100. Natural Analogs for Nuclear Fuel Disposal, Course 5.2, by J. Cramer, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Workbook 00 - Introduction to Natural Analogs 20052101.pdf (102 kb)
    - Workbook 01 - Copper Corrosion, by J. Cramer, 20052102.pdf (396 kb)
    - Workbook 02 - Clay Sealing, by J. Cramer, 20052103.pdf (249 kb)
    - Workbook 03 - Clay Sealing 2, by J. Cramer, 20052104.pdf (268 kb)
    - Workbook 04 - Clay Sealing - Avonlea Bentonite, by J. Cramer, 20052105.pdf (230 kb)
    - Workbook 05 - Concrete Stability, by J. Cramer, 20052106.pdf (99 kb)
    - Workbook 06 - Concrete & Ground Water, by J. Cramer, 20052107.pdf (48 kb)
    - Workbook 07 - Radionuclide Migration in Soils, by J. Cramer, 20052108.pdf (228 kb)
    - Workbook 08 - Natural Nuclear Reactor, by J. Cramer, 20052109.pdf (479 kb)
    - Workbook 09 - Disposal System Analog, by J. Cramer, 20052110.pdf (1381 kb)
    - Workbook 10 - Summary, by J. Cramer, 20052111.pdf (50 kb)
  101. Hydrogeology of Nuclear Fuel Disposal, Course 5.4, by D. Stevenson, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Workbook 01 - Hydrogeology 20052301.pdf (1408 kb)
    - Workbook 02 - Structural Geology & Borehole Studies, by D. Stevenson, 20052302.pdf (1036 kb)
    - Workbook 03 - Groundwater Sampling, by D. Stevenson, 20052303.pdf (1231 kb)
    - Workbook 04 - Candidate Site Characterization, by D. Stevenson, 20052304.pdf (734 kb)
  102. Environmental Issues in Nuclear Fuel Disposal, Course 5.5, by S. Sheppard, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Workbook 01 - Environmental Issues in Waste Management 20052401.pdf (2604 kb)
    - Workbook 02 - Lakes and Rivers, by S. Sheppard, 20052402.pdf (1445 kb)
    - Workbook 03 - Atmosphere, by S. Sheppard, 20052403.pdf (815 kb)
    - Workbook 04 - Natural Realm, by S. Sheppard, 20052404.pdf (906 kb)
    - Workbook 05 - Sensitivity Analysis, by S. Sheppard, 20052405.pdf (1734 kb)
    - Workbook 06 - Monte Carlo Models, by S. Sheppard, 20052406.pdf (1234 kb)
  103. Nuclear Fuel Disposal Performance Assessment, Course 5.6, by J. Cramer, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Workbook 00 - Performance Assessment Modeling 20052501.pdf (65 kb)
    - Workbook 01 - Introduction & System Variability Analysis, by J. Cramer, 20052502.pdf (2055 kb)
    - Workbook 02 - I/O and Systems Model Interfaces, by J. Cramer, 20052503.pdf (1567 kb)
    - Workbook 03 - Complex & Large System Models, by J. Cramer, 20052504.pdf (412 kb)
    - Workbook 04 - Sensitivity Analysis & SYVAC3 Applications, by J. Cramer, 20052505.pdf (592 kb)
    - Workbook 05 - Canadian System Model & SYVAC3-CC3, by J. Cramer, 20052506.pdf (880 kb)
  104. Radiation Processing, Course 6.1, by A. Sigh and H. Singh, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Workbook 01 - Basics, Current & Emerging Applications 20052701.pdf (360 kb)
    - Workbook 02 - Potential Concerns Associated with Irradiated Foods, by A. Sigh and H. Singh, 20052702.pdf (598 kb)
    - Workbook 03 - Irradiated Foods (cont'd), by A. Sigh and H. Singh, 20052703.pdf (392 kb)
    - Workbook 04 - Sterilization of Medical Products, by A. Sigh and H. Singh, 20052704.pdf (494 kb)
    - Workbook 05 - Dosimetry, by A. Sigh and H. Singh, 20052705.pdf (223 kb)
    - Workbook 06 - Radiation Polymerization - Coatins & Links, by A. Sigh and H. Singh, 20052706.pdf (111 kb)
    - Workbook 07 - Radiation Polymerization - Grafting, by A. Sigh and H. Singh, 20052707.pdf (110 kb)
    - Workbook 08 - Radiation Polymerization - Bioengineering, by A. Sigh and H. Singh, 20052708.pdf (188 kb)
    - Workbook 09 - Polymerization - Material Composites, by A. Sigh and H. Singh, 20052709.pdf (93 kb)
    - Workbook 10 - Radiation Protection, by A. Sigh and H. Singh, 20052710.pdf (100 kb)
    - Workbook 11 - Dose Rate Effect in Food Irradiation, by A. Sigh and H. Singh, 20052711.pdf (1661 kb)
    - Workbook 12 - Radiation Processing - Basic Aspects, by A. Sigh and H. Singh, 20052712.pdf (691 kb)
    - Workbook 13 - Industrial Irradiators, by A. Sigh and H. Singh, 20052713.pdf (628 kb)
    - Workbook 14 - The Environment, by A. Sigh and H. Singh, 20052714.pdf (66 kb)
    - Workbook 15 - Chemical Wastes - PCBs, by A. Sigh and H. Singh, 20052715.pdf (62 kb)
    - Workbook 16 - Radiation Processing of Sewage, by A. Sigh and H. Singh, 20052716.pdf (194 kb)
    - Workbook 17 - Radiation Processing of Flue Gases, by A. Sigh and H. Singh, 20052717.pdf (91 kb)
    - Workbook 18 - Electron Processing in the Pulping Industry, by A. Sigh and H. Singh, 20052718.pdf (360 kb)
    - Workbook 19 - Chemical Effects, by A. Sigh and H. Singh, 20052719.pdf (274 kb)
    - Workbook 20 - Manufacturing of Chemicals, by A. Sigh and H. Singh, 20052720.pdf (50 kb)
    - Workbook 21 - Food Irradiation - Dose Rate Effect, by A. Sigh and H. Singh, 20052721.pdf (301 kb)
    - Workbook 22 - Electron Processing - Composites, by A. Sigh and H. Singh, 20052722.pdf (887 kb)
    - Workbook 23 - Dosimetry Procedures in Electron Processing, by A. Sigh and H. Singh, 20052723.pdf (248 kb)
    - Workbook 24 - Safety in Industrial Accelerator Facility, by A. Sigh and H. Singh, 20052724.pdf (467 kb)
    - Workbook 25 - Effects on Polymeric Systems - Polymerization, by A. Sigh and H. Singh, 20052725.pdf (68 kb)
    - Workbook 26 - Effects on Polymeric Systems - Crosslinking and Scission, by A. Sigh and H. Singh, 20052726.pdf (232 kb)
    - Workbook 27 - Effects on Polymeric Systems - Polyethylene Crosslinking, by A. Sigh and H. Singh, 20052727.pdf (91 kb)
    - Workbook 28 - Effects on Polymeric Systems - Elastomers, by A. Sigh and H. Singh, 20052728.pdf (138 kb)
    - Workbook 29 - Spices, Herbs, Other Vegetable Seasonings, by A. Sigh and H. Singh, 20052729.pdf (236 kb)
    - Workbook 30 - Successful Applications in Food Irradiation, by A. Sigh and H. Singh, 20052730.pdf (316 kb)
    - Workbook 31 - Irradiation of Fresh Fruits, by A. Sigh and H. Singh, 20052731.pdf (273 kb)
    - Workbook 32 - Radiation Processing of Advanced Composites, by A. Sigh and H. Singh, 20052732.pdf (670 kb)
    - Workbook 33 - Micronutrients, by A. Sigh and H. Singh, 20052733.pdf (210 kb)
    - Workbook 34 - Irradiation of Red Meats, by A. Sigh and H. Singh, 20052734.pdf (157 kb)
  105. Intermediate Reactors, Boilers and Auxiliaries, CNSC, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] - [Phase] Concept Design [Audience] College Engineer Manager Technician Ugrad
    - 20052900.pdf (14193 kb)
  106. Digital Instrumentation & Control, Course 7.4, by M. MacBeth, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Chapter 01 - CANDU DCC Features 20053301.pdf (237 kb)
    - Chapter 02 - Digital Control Concepts, by M. MacBeth, 20053302.pdf (317 kb)
    - Chapter 03 - Computer I/O Subsystems, by M. MacBeth, 20053303.pdf (423 kb)
    - Chapter 04 - Digital Ctrl Program Concepts, by M. MacBeth, 20053304.pdf (492 kb)
    - Chapter 05 - PHT P&IC Control Program, by M. MacBeth, 20053305.pdf (906 kb)
    - Chapter 06 - Steam Generator Level Control, by M. MacBeth, 20053306.pdf (727 kb)
    - Chapter 07 - Computerized Shutdown System, by M. MacBeth, 20053307.pdf (250 kb)
    - Chapter 08 - S/W Categorization Methods, by M. MacBeth, 20053308.pdf (233 kb)
    - Chapter 09 - General Display Requirements, by M. MacBeth, 20053309.pdf (349 kb)
    - Chapter 10 - Human Interface Design (HFE), by M. MacBeth, 20053310.pdf (1014 kb)
    - Chapter 11 - HFE Methods, by M. MacBeth, 20053311.pdf (365 kb)
    - Chapter 12 - Work Assignment, by M. MacBeth, 20053312.pdf (173 kb)
    - Chapter 13 - Typical Design Guide Features, by M. MacBeth, 20053313.pdf (376 kb)
    - Chapter 14 - Typical HFE Eng. Program, by M. MacBeth, 20053314.pdf (421 kb)
    - Workbook 01 Module 01 - Introduction to Instrumentation, by M. MacBeth, 20053315.pdf (182 kb)
    - Workbook 01 Module 02 - ISA Symbols, by M. MacBeth, 20053316.pdf (94 kb)
    - Workbook 01 Module 03 - Pressure Instrumentation, by M. MacBeth, 20053317.pdf (122 kb)
    - Workbook 01 Module 04 - Level Instrumentation, by M. MacBeth, 20053318.pdf (249 kb)
    - Workbook 01 Module 05 - Flow Instrumentation, by M. MacBeth, 20053319.pdf (267 kb)
    - Workbook 01 Module 06 - Temperature Instrumentation, by M. MacBeth, 20053320.pdf (235 kb)
    - Workbook 01 Module 07 - Digital Computer Control, by M. MacBeth, 20053321.pdf (237 kb)
    - Workbook 01 Module 08 - Control Valves, Accessories, by M. MacBeth, 20053322.pdf (931 kb)
    - Workbook 02 Module 01 - Control Concepts, by M. MacBeth, 20053323.pdf (588 kb)
    - Workbook 02 Module 02 - Control Equipment, by M. MacBeth, 20053324.pdf (414 kb)
    - Workbook 02 Module 03 - Control and Process Considerations, by M. MacBeth, 20053325.pdf (371 kb)
    - Workbook 03 Module 01 - Level Control, by M. MacBeth, 20053326.pdf (566 kb)
    - Workbook 03 Module 02 - Pressure Control, by M. MacBeth, 20053327.pdf (203 kb)
    - Workbook 04 Module 01 - Log and Linear Ranges, by M. MacBeth, 20053328.pdf (96 kb)
    - Workbook 04 Module 02 - Log range detectors, by M. MacBeth, 20053329.pdf (126 kb)
    - Workbook 04 Module 03 - Linear Range Detectors, by M. MacBeth, 20053330.pdf (119 kb)
    - Workbook 05 Module 01 - Zone Level Control, by M. MacBeth, 20053331.pdf (216 kb)
    - Workbook 05 Module 02 - Reactor Regulating System, by M. MacBeth, 20053332.pdf (228 kb)
    - Workbook 05 Module 03 - Reactor Shutdown Systems, by M. MacBeth, 20053333.pdf (625 kb)
    - Workbook 05 Module 04 - Recovery from a Poison Outage, by M. MacBeth, 20053334.pdf (79 kb)
    - Workbook 06 Module 01 - Feed and Bleed Pressure Control, by M. MacBeth, 20053335.pdf (206 kb)
    - Workbook 06 Module 02 - Pressure Control by Pressurizer, by M. MacBeth, 20053336.pdf (111 kb)
    - Workbook 06 Module 03 - Heat Transport Bleed Control, by M. MacBeth, 20053337.pdf (245 kb)
    - Workbook 07 Module 01 - Unit Control Concepts, by M. MacBeth, 20053338.pdf (173 kb)
    - Workbook 07 Module 02 - Boiler Pressure Control, by M. MacBeth, 20053339.pdf (255 kb)
    - Workbook 07 Module 03 - Unit Startup, by M. MacBeth, 20053340.pdf (380 kb)
    - Workbook 08 Module 01 - Controller Tuning, by M. MacBeth, 20053341.pdf (189 kb)
    - Workbook 09 Module 01 - CANDU 9 Plant Control, by M. MacBeth, 20053342.pdf (182 kb)
  107. Welding Technology, Course 7.5, by I. Grant, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: Appreciation of metal joining techniques: wleding, welding processes, weldment quality, symbols on drawings, nondestructive examination, and codes and standards.
    Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Chapter 01 - Introduction 20053401.pdf (1359 kb)
    - Chapter 02 - Specification – Covered Carbon Steel Electrodes, by I. Grant, 20053402.pdf (2022 kb)
    - Chapter 03 - Submerged Arc Welding, by I. Grant, 20053403.pdf (1118 kb)
    - Chapter 04 - Gas Metal Arc Welding, by I. Grant, 20053404.pdf (949 kb)
    - Chapter 05 - Plasma Welding, by I. Grant, 20053405.pdf (119 kb)
    - Chapter 06 - Electrical Power Sources, by I. Grant, 20053406.pdf (551 kb)
    - Chapter 07 - Welding Stainless Steel Tubing, by I. Grant, 20053407.pdf (473 kb)
    - Chapter 08 - Thermal Efficiency of Arc Welding Processes, by I. Grant, 20053408.pdf (737 kb)
    - Chapter 09 - Solidification Structures & Properties of Fusion Welds, by I. Grant, 20053409.pdf (3163 kb)
    - Chapter 10 - Prediction of Welding Distortion, by I. Grant, 20053410.pdf (618 kb)
    - Chapter 11 - Material & Fabrication Considerations for CANDU Heat Transport Systems, by I. Grant, 20053411.pdf (1808 kb)
    - Chapter 13 - Fitness for Purpose, by I. Grant, 20053413.pdf (858 kb)
    - Chapter 14 - Welding Variables Procedure Specs, by I. Grant, 20053414.pdf (965 kb)
    - Chapter 17 - Calculating Force/Unit Length on Welds, by I. Grant, 20053417.pdf (773 kb)
    - Chapter 18 - Design for Welding, by I. Grant, 20053418.pdf (569 kb)
    - Chapter 19 - Design and Construction Methods for Welded Steel Merchant Vessels, by I. Grant, 20053419.pdf (313 kb)
    - Workbook 01 - Welding Technologyes), by I. Grant, 20053420.pdf (240 kb)
    - Workbook 02 - Flux Shielded Welding Processes, by I. Grant, 20053421.pdf (549 kb)
    - Workbook 03 - Submerged Arc Welding, by I. Grant, 20053422.pdf (636 kb)
    - Workbook 04 - Gas Metal Arc Welding, by I. Grant, 20053423.pdf (497 kb)
    - Workbook 05 - Plasma Arc Welding, by I. Grant, 20053424.pdf (169 kb)
    - Workbook 06 - Welding Power Supplies & Controls, by I. Grant, 20053425.pdf (262 kb)
    - Workbook 07 - Arc Physics and Weld Pool Behaviour, by I. Grant, 20053426.pdf (281 kb)
    - Workbook 08 - Heat Flow in Welding, by I. Grant, 20053427.pdf (262 kb)
    - Workbook 09 - Metallurgical Effects of the Weld Thermal Cycle, by I. Grant, 20053428.pdf (1172 kb)
    - Workbook 10 - Distortion, Residual Stress & Post-Weld Heat Treatment, by I. Grant, 20053429.pdf (361 kb)
    - Workbook 11 - Weldability of Structural Steels, by I. Grant, 20053430.pdf (535 kb)
    - Workbook 12 - Weld Discontinuities, by I. Grant, 20053431.pdf (923 kb)
    - Workbook 13 - Inspection & Testing, by I. Grant, 20053432.pdf (327 kb)
    - Workbook 14 - Welding Qualification & Certification, by I. Grant, 20053433.pdf (480 kb)
    - Workbook 15 - Design for Welding, by I. Grant, 20053434.pdf (605 kb)
    - Workbook 16 - Weld Symbols on Drawings, by I. Grant, 20053435.pdf (531 kb)
    - Workbook 17 Static Strength of Welded Joints, by I. Grant, 20053436.pdf (443 kb)
    - Workbook 18 - Fatigue Failure of Welded Joints, by I. Grant, 20053437.pdf (557 kb)
    - Workbook 19 - Fracture of Welded Structures, by I. Grant, 20053438.pdf (539 kb)
    108. 1996-08-01---------Jump to [Top]
  108. Reactor Control & Simulation, Course 3.3, by J. Koclas, Chulalongkorn University, 1996-08-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Chapter 0 - Title and Table of Contents 20044301.pdf (67 kb)
    - Chapter 1 - Point Kinetics, by J. Koclas, 20044302.pdf (490 kb)
    - Chapter 2 - General Concepts, by J. Koclas, 20044303.pdf (262 kb)
    - Chapter 3 - Power Measurement & Calibration, by J. Koclas, 20044304.pdf (211 kb)
    - Chapter 4 - Power Error, by J. Koclas, 20044305.pdf (193 kb)
    - Chapter 5 - Liquid Zone Control, by J. Koclas, 20044306.pdf (134 kb)
    - Chapter 6 - Adjuster Rod Control, by J. Koclas, 20044307.pdf (109 kb)
    - Chapter 7 - MCA Control, by J. Koclas, 20044308.pdf (90 kb)
    - Chapter 8 - Shutoff Rods Extraction, by J. Koclas, 20044309.pdf (35 kb)
    - Chapter 9 - Modal Flux Synthesis, by J. Koclas, 20044310.pdf (83 kb)
    - Chapter 10 - Reactor Setback Program, by J. Koclas, 20044311.pdf (66 kb)
    - Chapter 11 - Reactor Stepback, by J. Koclas, 20044312.pdf (62 kb)
    - Chapter 12 - Shutdown Systems: SDS1 and SDS2, by J. Koclas, 20044313.pdf (173 kb)
    - Chapter XX - Supplementary Materials, by J. Koclas, 20044314.pdf (531 kb)
    - Workbook, Chapter 2 - General Concepts, by J. Koclas, 20044315.pdf (331 kb)
    - Workbook, Chapter 3 - Power Measurement & Calibration, by J. Koclas, 20044316.pdf (263 kb)
    - Workbook, Chapter 4 - Power Error, by J. Koclas, 20044317.pdf (254 kb)
    - Workbook, Chapter 5 - Liquid Zone Control, by J. Koclas, 20044318.pdf (159 kb)
    - Workbook, Chapter 6 - Adjuster Rod Control, by J. Koclas, 20044319.pdf (125 kb)
    - Workbook, Chapter 7 - Mechanical Control Absorbers, by J. Koclas, 20044320.pdf (94 kb)
    - Workbook, Chapter 8 - Shutoff Rods Extraction, by J. Koclas, 20044321.pdf (46 kb)
    - Workbook, Chapter 9 - Modal Flux Synthesis, by J. Koclas, 20044322.pdf (103 kb)
    - Workbook, Chapter 10 - Reactor Setback Program, by J. Koclas, 20044323.pdf (85 kb)
    - Workbook, Chapter 11 - Reactor Stepback, by J. Koclas, 20044324.pdf (80 kb)
    - Workbook, Chapter 12 - Shutdown Systems: SDS1 and SDS2, by J. Koclas, 20044325.pdf (209 kb)
    109. 1996-12-05---------Jump to [Top]
  109. Non-Destructive Testing, Course 7.2, by E. Hussein, Chulalongkorn University, 1996-12-05. Doc type: Course.
    Summary: Nondestructive testing including ultrasonics, magnetic flux leakage, eddy current, radiography, acoustic emission, and microwaves.
    Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Chapter 00 - Table of Contents 20053101.pdf (162 kb)
    - Chapter 01 - Introduction, by E. Hussein, 20053102.pdf (220 kb)
    - Chapter 02 - Ultrasonics, by E. Hussein, 20053103.pdf (670 kb)
    - Chapter 03 - Magnetic Flux Leakage, by E. Hussein, 20053104.pdf (301 kb)
    - Chapter 04 - Eddy Current (pdf 340 kb, 20 pages), by E. Hussein, 20053105.pdf (369 kb)
    - Chapter 05 - Radiography, by E. Hussein, 20053106.pdf (409 kb)
    - Chapter 06 - Acoustic Emission, by E. Hussein, 20053107.pdf (305 kb)
    - Chapter 07 - Microwaves, by E. Hussein, 20053108.pdf (145 kb)
    110. 1997-01-01---------Jump to [Top]
  110. 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)
  111. Radioactive Waste Management, Course 5.1, by L. Zikovsky, Chulalongkorn University, 1997-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Chapter 00 - Table of Contents 20052001.pdf (312 kb)
    - Chapter 01 - Introduction, by L. Zikovsky, 20052002.pdf (1537 kb)
    - Chapter 02 - Gaseous Waste, by L. Zikovsky, 20052003.pdf (1137 kb)
    - Chapter 03 - Liquid and Wet Waste, by L. Zikovsky, 20052004.pdf (2459 kb)
    - Chapter 04 - Solid Medium & Low Level, by L. Zikovsky, 20052005.pdf (2018 kb)
    - Chapter 05 - Transport, by L. Zikovsky, 20052006.pdf (542 kb)
    - Chapter 06 - Solid High Level Waste, by L. Zikovsky, 20052007.pdf (846 kb)
    - Chapter 07 - Disposal of High Level Waste, by L. Zikovsky, 20052008.pdf (3282 kb)
    - Chapter 08 - Management of Radioactive Waste in Canada, by L. Zikovsky, 20052009.pdf (2503 kb)
    - Workbook 01 - Radioactive Waste Management, by L. Zikovsky, 20052010.pdf (374 kb)
    - Workbook 02 - Gaseous Radwaste, by L. Zikovsky, 20052011.pdf (378 kb)
    - Workbook 03 - Liquid Radwaste, by L. Zikovsky, 20052012.pdf (642 kb)
    - Workbook 04 - Solid LLW, by L. Zikovsky, 20052013.pdf (720 kb)
    - Workbook 05 - Transport, by L. Zikovsky, 20052014.pdf (193 kb)
    - Workbook 06 - Solid HLW, by L. Zikovsky, 20052015.pdf (350 kb)
    - Workbook 07 - Disposal Principles, by L. Zikovsky, 20052016.pdf (1066 kb)
    - Workbook 08 - Canada's Radwaste, by L. Zikovsky, 20052017.pdf (1015 kb)
    112. 1997-03-18---------Jump to [Top]
  112. Engineered Barriers for Fuel Disposal, Course 5.3, by L.H. Johnson, Chulalongkorn University, 1997-03-18. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Workbook 01 - Introduction 20052201.pdf (1579 kb)
    - Workbook 02 - Detailed Chemistry Considerations, by L.H. Johnson, 20052202.pdf (700 kb)
    - Workbook 03 - Container Failure Predictions, by L.H. Johnson, 20052203.pdf (924 kb)
    - Workbook 04 - Container Design Considerations, by L.H. Johnson, 20052204.pdf (829 kb)
    - Workbook 05 - Seal Materials, Design, & Performance, by L.H. Johnson, 20052205.pdf (757 kb)
    - Workbook 06 - Large Scale In Situ Testing, by L.H. Johnson, 20052206.pdf (1582 kb)
    - Workbook 07 - Vault Model, by L.H. Johnson, 20052207.pdf (322 kb)
    113. 1997-04-01---------Jump to [Top]
  113. Software Quality Assurance: Practical Procedures to Meet CSA Standards, by M.B. Carver, CNSC, 1997-04-01. Doc type: Report.
    Summary: In the Canadian nuclear industry at the time, only the ASSERT code team and the NUCIRC team used definitive SQA (Software Quality Assurance), which identifies exactly what version of the computer code is being used for a given application, and every component used to build that version. A drive to apply such standards to all computer programs started in the 1990s, and Mike co-authored the 1995 AECL Reactor Development SQA manual. Upon his retirement, representatives of the then AECB (now CNSC) asked him to write a SQA guide for the industry that would bring all computer codes teams in line with CSA standards ( N286.7 & Q936).This report is CNSC-info-0669, 1997. To date the ASSERT-PV development team has followed these standards, the CATHENA team has not. Source attribution: Archived in the public domain at http://www.nuclearsafety.gc.ca/eng/about/past/timeline-dev/resources/documents/infohistorical/info-0669.pdf .
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Atomic Energy Control Board, Report INFO-0699, April 1997, http://www.nuclearsafety.gc.ca info-0669.pdf (3262 kb)
    114. 1997-04-08---------Jump to [Top]
  114. Monte Carlo Method for Particle Transport Simulation, Course 1.6, by E. Hussein, Chulalongkorn University, 1997-04-08. Doc type: Course.
    Summary: A brief introduction to the basics of the Monte Carlo method, how the Boltzmann particle transport equation lends itself to solution by the Monte Carlo method, specific aspects of the MCNP code.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Modelling Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Chapter 0 - Table of Contents 20043501.pdf (59 kb)
    - Chapter 1 - Introduction, by E. Hussein, 20043502.pdf (30 kb)
    - Chapter 2 - Monte Carlo Method, by E. Hussein, 20043503.pdf (283 kb)
    - Chapter 3 - Boltzmann Transport Equation, by E. Hussein, 20043504.pdf (79 kb)
    - Chapter 4 - MCNP Input Structure, by E. Hussein, 20043505.pdf (29 kb)
    - Chapter 5 - Geometry in MCNP, by E. Hussein, 20043506.pdf (105 kb)
    - Chapter 6 - MCNP Source Parameters, by E. Hussein, 20043507.pdf (173 kb)
    - Chapter 7 - Physics & Material Cross-Sections, by E. Hussein, 20043508.pdf (67 kb)
    - Chapter 8 - Termination Parameters, by E. Hussein, 20043509.pdf (30 kb)
    - Chapter 9 - Importance Sampling, by E. Hussein, 20043510.pdf (122 kb)
    - Chapter 10 - Tallying, by E. Hussein, 20043511.pdf (163 kb)
    - Chapter 11 - Uncertainty Analysis, by E. Hussein, 20043512.pdf (177 kb)
    - Chapter 12 - Criticality in MCNP, by E. Hussein, 20043513.pdf (42 kb)
    - Workbook, Chapter 1, by E. Hussein, 20043514.pdf (60 kb)
    - Workbook, Chapter 2, by E. Hussein, 20043515.pdf (460 kb)
    - Workbook, Chapter 3, by E. Hussein, 20043516.pdf (103 kb)
    - Workbook, Chapter 4, by E. Hussein, 20043517.pdf (45 kb)
    - Workbook, Chapter 5, by E. Hussein, 20043518.pdf (167 kb)
    - Workbook, Chapter 6, by E. Hussein, 20043519.pdf (270 kb)
    - Workbook, Chapter 7, by E. Hussein, 20043520.pdf (95 kb)
    - Workbook, Chapter 8, by E. Hussein, 20043521.pdf (41 kb)
    - Workbook, Chapter 9, by E. Hussein, 20043522.pdf (195 kb)
    - Workbook, Chapter 10, by E. Hussein, 20043523.pdf (265 kb)
    - Workbook, Chapter 11, by E. Hussein, 20043524.pdf (281 kb)
    - Workbook, Chapter 12, by E. Hussein, 20043525.pdf (68 kb)
    115. 1997-06-01---------Jump to [Top]
  115. Steam Generators for CANDU, Engineering Memoirs, by J.M. Dyke, Individual Contributions, 1997-06-01. Doc type: Essay.
    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
    - 20054100.pdf (19 kb)
    116. 1997-08-01---------Jump to [Top]
  116. Reactor Core Analysis & Fuel Management, Course 1.5, by D. Rozon, Chulalongkorn University, 1997-08-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Chapter 5 - SLOWKIN: A Simplified Model for the Stimulation of Transients in a SLOWPOKE-2 Reactor 20043405.pdf (1297 kb)
    117. 1997-10-01---------Jump to [Top]
  117. Reactor Mechanical Design, Course 3.6, by R.S. Porter, Chulalongkorn University, 1997-10-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Mechanical Engineering [Topic] Conceptual Physical Description [Phase] Concept Design [Audience] Engineer Grad Ugrad
    - Section 0 - Title, Table of Contents 20044601.pdf (99 kb)
    - Section 1 - Overview, Reg. Req’ts, Codes & Standards, by R.S. Porter, 20044602.pdf (531 kb)
    - Section 2 - Design Philosophy, Rationale, Key Operating Parameters, by R.S. Porter, 20044603.pdf (481 kb)
    - Section 3 - Stress Analysis of Reactor Structures, by R.S. Porter, 20044604.pdf (253 kb)
    - Section 4 - Excitation Spectra Etc., by R.S. Porter, 20044605.pdf (374 kb)
    - Section 5 - Design of Fuel Channels, by R.S. Porter, 20044606.pdf (622 kb)
    - Section 6 - Design of Reactivity Control Units, by R.S. Porter, 20044607.pdf (1181 kb)
    - Section 7 - Design of Fuel Handling System, by R.S. Porter, 20044608.pdf (1121 kb)
    - Appendix 1 - Design Loads and Load Cases for CANDU 6, by R.S. Porter, 20044609.pdf (174 kb)
    - Appendix 2 - Stresses for Design Cases, by R.S. Porter, 20044610.pdf (316 kb)
    - Appendix 3 - Finite Element Analysis, by R.S. Porter, 20044611.pdf (96 kb)
    - Appendix 4 - Seismic Behaviour of CANDU 6, by R.S. Porter, 20044612.pdf (168 kb)
    - Workbook, Chapter 1 - Figures, by R.S. Porter, 20044613.pdf (208 kb)
    - Workbook, Chapter 2 - Figures, by R.S. Porter, 20044614.pdf (778 kb)
    - Workbook, Chapter 3 - Figures, by R.S. Porter, 20044615.pdf (355 kb)
    - Workbook, Chapter 4 - Figures, by R.S. Porter, 20044616.pdf (455 kb)
    - Workbook, Chapter 5 - Figures, by R.S. Porter, 20044617.pdf (150 kb)
    - Workbook, Chapter 6 - Figures, by R.S. Porter, 20044618.pdf (964 kb)
    - Workbook, Chapter 7 - Figures, by R.S. Porter, 20044619.pdf (1006 kb)
    118. 1997-12-01---------Jump to [Top]
  118. Reactor Core Analysis & Fuel Management, Course 1.5, by B. Rouben, Chulalongkorn University, 1997-12-01. Doc type: Course.
    Summary: A coupled neutronics-thermalhydraulics analysis of a loss-of-coolants accident (LOCA) in CANDU is presented. The calculation is performed with the CERBERUS (spatial-kinetics) module of the finite-core code RFSP, coupled to the thermalhydraulics code FIREBIRD. The power pulse which results fiom the hypothetical LOCA is assumed terminated by Shutdown System 1 (SDSl). The calculational methodology and the physics model used in the LOCA analysis are detailed. The significant parameters which govern the results of the calculation are discussed.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Chapter 1 - Coupled Neutronics-Thermalhydaulics LOCA Analysis 20043401.pdf (970 kb)
    - Chapter 2 - Core Physics Aspects of Safety Analysis, by B. Rouben, 20043402.pdf (1188 kb)
    - Chapter 4 - Fuel Management in CANDU, by B. Rouben, 20043404.pdf (1542 kb)
    - Workbook, Chapter 1 - Neutronics-Thermalhydraulics Overheads, by B. Rouben, 20043406.pdf (330 kb)
    - Workbook, Chapter 2 - Core Physics Overheads, by B. Rouben, 20043407.pdf (567 kb)
    - Chapter 3 - Fuel Management and Advanced Fuel Cycles, by D. Rozon, 20043403.pdf (1436 kb)
    119. 1998-02-01---------Jump to [Top]
  119. 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)
  120. 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)
  121. 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)
    122. 1998-09-18---------Jump to [Top]
  122. IAEA CANDU Instrumentation & Control Course, by Mike MacBeth, IAEA, 1998-09-18. Doc type: Course.
    Summary: IAEA CANDU Instrumentation & Control Course, by Dr. Mike MacBeth (AECL), September 13 - 18, 1998, SNERDI, Shanghai
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Instrumentation Equipment 20041601.pdf (2847 kb)
    - Electronic Control, by Mike MacBeth, 20041602.pdf (1680 kb)
    - Controller Tuning, by Mike MacBeth, 20041603.pdf (510 kb)
    - Computer Input/Output Subsystems, by Mike MacBeth, 20041604.pdf (484 kb)
    - Control Programs, by Mike MacBeth, 20041605.pdf (810 kb)
    - Nuclear Instrumentation, by Mike MacBeth, 20041606.pdf (518 kb)
    - Reactor Control and Protection, by Mike MacBeth, 20041607.pdf (627 kb)
    - Heat Transport Control Systems, by Mike MacBeth, 20041608.pdf (1415 kb)
    - Reactor Protection, by Mike MacBeth, 20041609.pdf (712 kb)
    - Overall Unit Control, by Mike MacBeth, 20041610.pdf (693 kb)
    123. 1998-09-22---------Jump to [Top]
  123. Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25, by D.A. Meneley and Y.Q. Ruan, AECL, 1998-09-22. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems [Phase] Concept Design Safety [Audience] College Engineer Ugrad
    - Comparison of PHWR and PWR 19980101.pdf (1874 kb)
    - Reactor and Fuel Handling, by D.A. Meneley and Y.Q. Ruan, 19980102.pdf (2650 kb)
    - Moderator, HTS, Heavy Water, by D.A. Meneley and Y.Q. Ruan, 19980103.pdf (2454 kb)
    - Main Steam & T/G Systems, by D.A. Meneley and Y.Q. Ruan, 19980104.pdf (2626 kb)
    - Special Safety Systems, by D.A. Meneley and Y.Q. Ruan, 19980105.pdf (949 kb)
    - CANDU Reactor Control, by D.A. Meneley and Y.Q. Ruan, 19980106.pdf (1038 kb)
    124. 1999-02-23---------Jump to [Top]
  124. 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)
  125. 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)
    126. 1999-03-01---------Jump to [Top]
  126. CANDU Fuel Management Course, by Ben Rouben, AECL, 1999-03-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
    - Cover Page 20031100.pdf (91 kb)
    - Complete Course, by Ben Rouben, 20031101.pdf (286 kb)
    - Basic Characteristics of the CANDU Lattice, by Ben Rouben, 20031111.pdf (186 kb)
    - The CANDU Reactivity Devices, by Ben Rouben, 20031112.pdf (147 kb)
    - Detector Systems, by Ben Rouben, 20031113.pdf (141 kb)
    - Computational Scheme for CANDU Neutronics, by Ben Rouben, 20031114.pdf (182 kb)
    - General Discussion on CANDU Fuel Management, by Ben Rouben, 20031115.pdf (125 kb)
    - Equilibrium-Core Design, by Ben Rouben, 20031116.pdf (217 kb)
    - Ongoing Reactor Operation with Channel Refuellings, by Ben Rouben, 20031117.pdf (252 kb)
    - Effects of 135Xe, by Ben Rouben, 20031118.pdf (151 kb)
    - Summary, by Ben Rouben, 20031119.pdf (61 kb)
    - Basic Characteristics of the CANDU Lattice - Figures, by Ben Rouben, 20031121.pdf (324 kb)
    - The CANDU Reactivity Devices - Figures, by Ben Rouben, 20031122.pdf (404 kb)
    - Detector Systems - Figures, by Ben Rouben, 20031123.pdf (418 kb)
    - Computational Scheme for CANDU Neutronics - Figures, by Ben Rouben, 20031124.pdf (83 kb)
    - General Discussion on CANDU Fuel Management - Figures, by Ben Rouben, 20031125.pdf (78 kb)
    - Equilibrium-Core Design - Figures, by Ben Rouben, 20031126.pdf (309 kb)
    - Ongoing Reactor Operation with Channel Refuellings - Figures, by Ben Rouben, 20031127.pdf (323 kb)
    - Effects of 135Xe - Figures, by Ben Rouben, 20031128.pdf (99 kb)
    127. 1999-06-21---------Jump to [Top]
  127. CANDU Safety - presentations in Shanghai, 1999, by V. Snell, AECL, 1999-06-21. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual [Phase] Design Safety [Audience] Engineer Manager
    - CANDU Nuclear Power Plant Design 19990101.pdf (1646 kb)
    - Risk from Nuclear Power Plants, by V. Snell, 19990102.pdf (84 kb)
    - Nuclear Safety Characteristics, by V. Snell, 19990103.pdf (286 kb)
    - Thermalhydraulic Safety Characteristics of CANDU Reactors, by F.J. Doria, 19990104.pdf (1183 kb)
    - Safety Functions - Shutdown Systems, by V. Snell, 19990105.pdf (517 kb)
    - Heat Removal, by V. Snell, 19990106.pdf (767 kb)
    - Emergency Core Cooling, by V. Snell, 19990107.pdf (1182 kb)
    - Containment, by V. Snell, 19990108.pdf (699 kb)
    - Grouping and Separation, by V. Snell, 19990109.pdf (65 kb)
    - Design and Analysis Process, by F.J. Doria, 19990110.pdf (524 kb)
    - Reactivity Control, by V. Snell, 19990111.pdf (412 kb)
    - Large Loss of Coolant Accident, by F.J. Doria, 19990112.pdf (578 kb)
    - Small Loss of Coolant Accident, by F.J. Doria, 19990113.pdf (651 kb)
    - Loss of Heat Sink, by V. Snell, 19990114.pdf (199 kb)
    - Loss of Forced Circulation, by V. Snell, 19990115.pdf (1517 kb)
    - Large Loss of Coolant Accident with Coincident Loss of Emergency Core Cooling, by F.J. Doria, 19990116.pdf (554 kb)
    - Severe Core Damage Accidents, by V. Snell, 19990117.pdf (478 kb)
    - Safety Research and Development, by V. Snell, 19990118.pdf (1851 kb)
    - Safety Research and Development Programs, by F.J. Doria, 19990119.pdf (903 kb)
    - Safety Analysis Tools, by F.J. Doria, 19990120.pdf (608 kb)
    - Probabilistic Safety Analysis, by V.G. Snell and R. Jaitly, 19990121.pdf (81 kb)
    - Regulation of CANDU, by V. Snell, 19990122.pdf (1223 kb)
    - Regulatory Requirements for Design, by V. Snell, 19990123.pdf (162 kb)
    - Regulatory Requirements for Accident Analysis, by V. Snell, 19990124.pdf (60 kb)
    - CANDU 9 Design Overview, by V. Snell, 19990125.pdf (630 kb)
    - CANDU 9 Safety and Licensability, by V. Snell, 19990126.pdf (580 kb)
    128. 1999-10-01---------Jump to [Top]
  128. China Journal of Nuclear Power Engineering, 1999 Vol 20 No. 6, by Xu Jijun and K.R. Hedges, AECL, 1999-10-01. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - Paper 01 - The Development of CANDU 20054401.pdf (2187 kb)
    - Paper 02 - Introduction to the Qinshan Phase III CANDU Nuclear Power Plant, by Zhang Yanfa and B.A. Shalaby, 20054402.pdf (3387 kb)
    - Paper 03 - Reactor Core Structure of Qinshan Phase III CANDU Nuclear Power Plant, by Qiu Suizheng and Norman C. Johnston, 20054403.pdf (1893 kb)
    - Paper 04 - Moderator, Heat Transport, and Steam Systems of Qinshan Phase III Nuclear Power Plant, by Gong Hongqi and R.S. Hart, 20054404.pdf (353 kb)
    - Paper 05 - Fuel Handling System for Qinshan Phase III Nuclear Power Plant, by Lin Chuanqing and D.C. Hancock, 20054405.pdf (649 kb)
    - Paper 06 - Control System of Qinshan Phase III Nuclear Power Plant, by Zhang Jianmin and R.A. Olmstead, by Jianmin Zhang and R.A. Olmstead, 20054406.pdf (427 kb)
    - Paper 07 - Main Electric Power and Balance of Plant Systems and Equipment for Qinshan Phase III Nuclear Power Plant, by Ji Yan, Jin Wanggui, He Ping and Surya Varanasi, 20054407.pdf (2543 kb)
    - Paper 08 - Safety Systems and Safety Analysis of Qinshan Phase III Nuclear Power Plant, by Cai Jianping, Shen Sen and Nick Barkman, 20054408.pdf (197 kb)
    - Paper 09 - Design and Performance of Fuel for Qinshan Phase III Nuclear Power Plant, by Song Wenhui and A.M. Manzer, 20054409.pdf (168 kb)
    - Paper 10 - Computer-Aided Engineering for Qinshan CANDU Projects, by Huang Zhizhang and David Goland, 20054410.pdf (366 kb)
    - Paper 11 - Fuel Management of CANDU Reactors, by Shao-hong Zhang and and B. Rouben, 20054411.pdf (252 kb)
    - Paper 12 - Physics Codes and Methods for CANDU Reactors, by Zhu XingGuan, Cai Jianping and H.C. Chow, 20054412.pdf (240 kb)
    - Paper 13 - Thermalhydraulic Design Methods and Computer Codes for CANDU Reactors, by Xu Jijun, V.S. Krishnan, P.J. Ingham, B.N. Hanna and J.R. Buell, 20054413.pdf (577 kb)
    - Paper 14 - Operational Characteristics and Management of the Qinshan Phase III CANDU Nuclear Power Plant, by Zhu Jizhou, Shan Jianqiang and Dennis McQuade, 20054414.pdf (201 kb)
    - Paper 15 - Advanced CANDU Fuel Cycle Vision, by Xie Zhonsheng and P.G. Boczar, 20054415.pdf (80 kb)
    - Paper 16 - A Brief Introduction to CANDU9 – A New Generation of Pressurized Heavy Water Reactors, by Zhang Zhenhua and K.R. Hedges, 20054416.pdf (189 kb)
    129. 2000-03-29---------Jump to [Top]
  129. RFSP Training Course, by Benoit Arsenault, AECL, 2000-03-29. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
    - Chapter 01 - Course Agenda 20054301.pdf (106 kb)
    - Chapter 02 - General Intro to Methods of Physics Analysis & Physics Computer Codes, by Benoit Arsenault, 20054302.pdf (381 kb)
    - Chapter 03 - The RFSP Direct-Access File, by Benoit Arsenault, 20054303.pdf (274 kb)
    - Chapter 04 - RFSP Model, by Benoit Arsenault, 20054304.pdf (400 kb)
    - Chapter 05 - Time-Average Model, by Benoit Arsenault, 20054305.pdf (322 kb)
    - Chapter 06 - Spatial Kinetics, by Benoit Arsenault, 20054306.pdf (272 kb)
    - Chapter 07 - Powderpufs-V, by Benoit Arsenault, 20054307.pdf (348 kb)
    - Chapter 08 - *Simulate and *Intrep, by Benoit Arsenault, 20054308.pdf (494 kb)
    - Chapter 09 - Flux and Power Mapping in RFSP, by Benoit Arsenault, 20054309.pdf (375 kb)
    - Chapter 10 - RRS Modelling in RFSP, by Benoit Arsenault, 20054310.pdf (275 kb)
    - Chapter 11 - *INSTANTAN, by Benoit Arsenault, 20054311.pdf (127 kb)
    - Chapter 12 - RFSP Code Development, by Benoit Arsenault, 20054312.pdf (336 kb)
    130. 2000-06-01---------Jump to [Top]
  130. Radiation Monitoring Notebook, by James T. Voss, Individual Contributions, 2000-06-01. Doc type: Reference.
    Summary: LA-UR-00-2584 James T. (Tom) Voss, NRRPT, CHP June 2000 (Feb. 2001 Update)
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Design Operation [Audience] Engineer Grad Technician Ugrad
    - 20041901.pdf (191 kb)
    131. 2000-09-13---------Jump to [Top]
  131. Safety Analysis Technology: Evolution, Revolution and the Drive to Re-Establish Margins, by John C Luxat, OPG, 2000-09-13. Doc type: Presentation.
    Summary: A historical perspective of the evolution of safety analysis technology at OPG is presented below. The key elements of the new safety analysis methodology are then described together with its relationship to other components of Canadian nuclear safety technology. This development is placed in context with similar work being conducted in the international Light Water Reactor (LWR) community.
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Performance [Phase] Commissioning Design Operation Safety [Audience] Engineer Technician
    - 20000301.pdf (256 kb)
    132. 2000-11-01---------Jump to [Top]
  132. A Reactor Cannot Explode Like a Nuclear Bomb, by Dan Meneley, Individual Contributions, 2000-11-01. Doc type: Lecture.
    Summary:
    Keywords: [Concept] - [SI] 03600 Nuclear Safety (Reactor) [Discipline] Nuclear Engineering [Topic] Conceptual Performance [Phase] Concept Design Operation Safety [Audience] College Engineer Manager Technician Vendor
    - 20000201.pdf (237 kb)
    133. 2000-12-01---------Jump to [Top]
  133. 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)
    134. 2001-01-03---------Jump to [Top]
  134. Why a Chernobyl-type accident cannot happen in CANDU reactors, AECL, 2001-01-03. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Concept Design Operation Safety [Audience] Engineer Manager Vendor
    - 20010701.pdf (1026 kb)
    135. 2001-02-01---------Jump to [Top]
  135. CANDU Origins and Evolution, by Gordon L. Brooks and John S. Foster, AECL, 2001-02-01. Doc type: Paper.
    Summary: While the name 'CANDU' was not adopted until the 1960's, the CANDU program can be considered to have started in early 1954. At that time, a team, called the Nuclear Power Group, was established to undertake studies intended to identify a potential Canadian nuclear power system. While the team operated under the auspices of AECL and was located in Building 456 at AECL's Chalk River Laboratory, its membership was drawn from a cross-section of Canadian utility and industrial organizations supported, as required, with "nuclear" expertise provided by AECL staff.
    Keywords: [Concept] Overview [SI] 03000 Engineering Science and Technology 31000 Reactor [Discipline] General Engineering Nuclear Engineering [Topic] Conceptual Important Parameters Intro and Overview [Phase] Concept Design Design Evolution [Audience] Manager
    - Overview 20010301.pdf (132 kb)
    - Why CANDU, by Gordon L. Brooks, 20010302.pdf (99 kb)
    - Figure of 8, by Gordon L. Brooks, 20010303.pdf (111 kb)
    - Emergency Core Cooling System, by Gordon L. Brooks, 20010304.pdf (107 kb)
    - The Origin and Evolution of the Second Shutdown System, by Gordon L. Brooks, 20010305.pdf (101 kb)
    136. 2001-03-06---------Jump to [Top]
  136. Fuel for the Next Millennia, by D.A. Meneley, AECL, 2001-03-06. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Fuel Management [Phase] Concept Design Operation [Audience] Engineer Manager
    - 20010201.pdf (906 kb)
    137. 2001-06-01---------Jump to [Top]
  137. Radiation Protection ("Green Book"), by Jan Burnham, NB Power, 2001-06-01. Doc type: Book.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Design Operation [Audience] Engineer Grad Technician Ugrad
    - Cover Page 20031300.pdf (98 kb)
    - Chapter 1 - Atomic Structure, by Jan Burnham, 20031301.pdf (898 kb)
    - Chapter 2 - Radiation Theory, by Jan Burnham, 20031302.pdf (1729 kb)
    - Chapter 3 - Radiation Dose, by Jan Burnham, 20031303.pdf (2016 kb)
    - Chapter 4 - Biological Effects Of Radiation, by Jan Burnham, 20031304.pdf (1341 kb)
    - Chapter 5 - Dose Limits And Risk, by Jan Burnham, 20031305.pdf (1929 kb)
    - Chapter 6 - Instruments, by Jan Burnham, 20031306.pdf (8721 kb)
    - Chapter 7 - Protection From External Exposures, by Jan Burnham, 20031307.pdf (3122 kb)
    - Chapter 8 - Internal Dose, by Jan Burnham, 20031308.pdf (1414 kb)
    - Chapter 9 - Contamination Control, by Jan Burnham, 20031309.pdf (9704 kb)
    - Chapter 10 - Dose Records, by Jan Burnham, 20031310.pdf (1925 kb)
    - Chapter 11 - Waste Management, by Jan Burnham, 20031311.pdf (4460 kb)
    - Chapter 12 - Work Planning, by Jan Burnham, 20031312.pdf (2171 kb)
    - Chapter 13 - Emergency Planning, by Jan Burnham, 20031313.pdf (2632 kb)
    - Answers to Problems, by Jan Burnham, 20031314.pdf (1093 kb)
    - Index, by Jan Burnham, 20031315.pdf (1210 kb)
    138. 2002-01-01---------Jump to [Top]
  138. Reactor Physics Course, CNSC, 2002-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design [Audience] Engineer Ugrad
    - Cover Page 20030100.pdf (87 kb)
    - , 20030101.pdf (1468 kb)
    - Review questions (English), 20030102.pdf (138 kb)
    - Review questions (French), 20030103.pdf (142 kb)
  139. Mechanical Equipment Course, CNSC, 2002-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Cover Page 20030200.pdf (86 kb)
    - , 20030201.pdf (1463 kb)
    - Vibrations, 20030202.pdf (1123 kb)
    - Valves, 20030203.pdf (2952 kb)
    - Flowsheets, 20030204.pdf (1693 kb)
  140. Materials Course, CNSC, 2002-01-01. Doc type: Course.
    Summary: This course covers the following areas pertaining to Mechanical Properties: Mechanical and Thermal Stress, Corrosion, Pressure Tubes and Fuel Bundles
    Keywords: [Concept] Materials [SI] - [Discipline] Materials Engineering [Topic] Corrosion Radiation [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Cover Page 20030300.pdf (86 kb)
    - , 20030301.pdf (844 kb)
    - Materials & Chemistry, 20030302.pdf (687 kb)
    - Corrosion, 20030303.pdf (1280 kb)
    - Radiation Effects on Materials, 20030304.pdf (1093 kb)
  141. Basic Instrumentation and Control Course, CNSC, 2002-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Conceptual Function [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Cover Page 20030400.pdf (87 kb)
    - , 20030401.pdf (850 kb)
    - Pressure Measurement, 20030402.pdf (350 kb)
    - Flow Measurement, 20030403.pdf (391 kb)
    - Level Measurement, 20030404.pdf (162 kb)
    - Temperature Measurement, 20030405.pdf (209 kb)
    - Neutron Flux Measurement, 20030406.pdf (282 kb)
    - Control, 20030407.pdf (539 kb)
    - I&C Diagrams, 20030408.pdf (98 kb)
  142. Electrical Course, CNSC, 2002-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Cover Page 20030800.pdf (83 kb)
    - Course, 20030801.pdf (2299 kb)
    - Electrical Module - Presentation, 20030802.pdf (1468 kb)
    - Transformers Module - Presentation, 20030803.pdf (664 kb)
    - Generators Module - Presentation, 20030804.pdf (2615 kb)
    - Electrical Protection Module - Presentation, 20030805.pdf (2756 kb)
  143. Heat and Thermodynamics Course, CNSC, 2002-01-01. Doc type: Course.
    Summary: This module covers the following areas pertaining to thermodynamics: Introduction, Heat and Thermodynamics - The Basics, Reactor and Heat Transport System Normal Operation, Heat Transport System Component Operation
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Cover Page 20030900.pdf (83 kb)
    - , 20030901.pdf (647 kb)
    - Presentation, 20030902.pdf (1557 kb)
  144. Principes de Science et de Fonctionnement des Réacteurs - Électricité, CNSC, 2002-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Électricité 20070200.pdf (1659 kb)
  145. Principes de Science et de Fonctionnement des Réacteurs - Instrumentation Fondamentale, CNSC, 2002-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Conceptual Function [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Instrumentation Fondamentale 20070400.pdf (869 kb)
  146. Heavy Water Reactors: Status and Projected Development, Technical Report Series No. 407, IAEA, Vienna, Austria, 2002., IAEA, 2002-01-01. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - Table of Contents. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp. D407_cont.pdf (54 kb)
    - Part 1. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp., D407_scr1.pdf (4200 kb)
    - Part 2. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp., D407_scr2.pdf (3619 kb)
    - Part 3. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp., D407_scr3.pdf (1384 kb)
    - Cover Page. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp., D407_start.pdf (53 kb)
    147. 2002-09-01---------Jump to [Top]
  147. 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)
    148. 2002-09-25---------Jump to [Top]
  148. ACR Presentation given to the US Nuclear Regulatory Commission on September 25-26, 2002, AECL, 2002-09-25. Doc type: Presentation.
    Summary: Presentation given by AECL to the US Nuclear Regulatory Commission on September 25-26, 2002
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - Introduction. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031201.pdf (1939 kb)
    - An Overview of the ACR Design. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031202.pdf (7935 kb)
    - ACR Technology Base. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031203.pdf (19271 kb)
    - ACR Reactor and Fuel Handling. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031204.pdf (12607 kb)
    - Core Design & Reactor Physics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031205.pdf (957 kb)
    - Reactor Coolant System, Moderator and Major Auxiliary Systems. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031206.pdf (17255 kb)
    - ACR Safety Support Systems Safety Assessment. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031207.pdf (583 kb)
    - ACR Technology Base: Reactor Physics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031208.pdf (1490 kb)
    - ACR Technology Base: Fuel. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031209.pdf (2924 kb)
    - ACR Technology Base: RCS Thermalhydraulics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031210.pdf (3081 kb)
    - ACR Technology Base: Fuel Channels. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031211.pdf (1817 kb)
    - ACR Technology Base: Fuel Channel Thermalhydraulics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031212.pdf (1444 kb)
    - ACR Moderator Circulation. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031213.pdf (2038 kb)
    - ACR Technology Base: Containment. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031214.pdf (792 kb)
    - Qualification Process for Safety Analysis Computer Codes. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031215.pdf (493 kb)
    149. 2003-01-01---------Jump to [Top]
  149. Principes de Science et de Fonctionnement des Réacteurs - Les Matériaux, CNSC, 2003-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Materials [SI] - [Discipline] Materials Engineering [Topic] Corrosion Radiation [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Les Matériaux 20070600.pdf (420 kb)
  150. Principes de Science et de Fonctionnement des Réacteurs - Équipement Mécanique, CNSC, 2003-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Équipement Mécanique 20070700.pdf (954 kb)
    151. 2003-02-01---------Jump to [Top]
  151. What is RTD, RdF Corporation, 2003-02-01. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - 20030701.pdf (198 kb)
    152. 2003-04-20---------Jump to [Top]
  152. Fretting in Nuclear Steam Generators - A New Approach, by J.M. Dyke, Individual Contributions, 2003-04-20. 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
    - 11th International Conference on Nuclear Engineering, Tokyo, Japan 20054500.pdf (2821 kb)
    153. 2003-06-24---------Jump to [Top]
  153. Fluid Mechanics, CNSC, 2003-06-24. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Presentation 20040602.pdf (610 kb)
  154. CANDU Fundamentals, CNSC, 2003-06-24. Doc type: Course.
    Summary: Fundamentals of reactor processes of the CANDU reactor.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Complete Course 20040700.pdf (6375 kb)
    - Objectives, 20040701.pdf (422 kb)
    - Atomic Structure, 20040702.pdf (257 kb)
    - Radioactivity - Spontaneous Nuclear Processes, 20040703.pdf (372 kb)
    - Nuclear Stability And Instability, 20040704.pdf (264 kb)
    - Activity and Half-Life, 20040705.pdf (271 kb)
    - Neutrons and Neutron Interactions, 20040706.pdf (296 kb)
    - Fission, 20040707.pdf (488 kb)
    - Fuel, Moderator, and Reactor Management, 20040708.pdf (231 kb)
    - Nuclear Safety, 20040709.pdf (182 kb)
    - Nuclear Power Reactors, 20040710.pdf (205 kb)
    - Candu Reactor Construction, 20040711.pdf (653 kb)
    - Moderator and Moderator System, 20040712.pdf (196 kb)
    - Moderator Auxiliary Systems, 20040713.pdf (253 kb)
    - Heat Transport System (HTS), 20040714.pdf (410 kb)
    - Heat Transport Auxiliary Systems, 20040715.pdf (372 kb)
    - Reactor Fuel, 20040716.pdf (503 kb)
    - Neutron Life Cycle, 20040717.pdf (221 kb)
    - Criticality and Neutron Multiplication, 20040718.pdf (297 kb)
    - Changes In Reactor Power With Time, 20040719.pdf (236 kb)
    - Xenon: A Fission Product Poison, 20040720.pdf (287 kb)
    - Reactivity Effects of Temperature Changes, 20040721.pdf (268 kb)
    - Neutron Flux Control, 20040722.pdf (311 kb)
    - Reactivity Mechanisms, 20040723.pdf (538 kb)
    - Emergency Coolant Injection & Containment, 20040724.pdf (795 kb)
    - The Conventional Side of the Station, 20040725.pdf (1049 kb)
    - Other Major Systems, 20040726.pdf (665 kb)
    - Radioactivity - Spontaneous Nuclear Processes, 20040727.pdf (539 kb)
    - Nuclear Stability And Instability, 20040728.pdf (1360 kb)
    - Activity and Half-Life, 20040729.pdf (120 kb)
    - Neutrons and Neutron Interactions, 20040730.pdf (163 kb)
    - Fission, 20040731.pdf (3750 kb)
    - Fuel, Moderator, and Reactor Management, 20040732.pdf (937 kb)
    - Nuclear Safety, 20040733.pdf (465 kb)
    - Nuclear Power Reactors, 20040734.pdf (693 kb)
    - CANDU Reactor Construction, 20040735.pdf (1259 kb)
    - Moderator System, 20040736.pdf (731 kb)
    - Heat Transport System, 20040737.pdf (1053 kb)
    - Fuel and Fuelling, 20040738.pdf (2226 kb)
    - Neutron Life Cycle, 20040739.pdf (151 kb)
    - Criticality and Neutron Multiplication, 20040740.pdf (709 kb)
    - Changes in Reactor Power with time, 20040741.pdf (2744 kb)
    - Neutron Flux Control, 20040742.pdf (157 kb)
    - Reactivity Mechanisms, 20040743.pdf (1894 kb)
    - Emergency Coolant Injection & Containment, 20040744.pdf (1024 kb)
    - The Conventional Side of the Station, 20040745.pdf (1535 kb)
    - Other Major Systems, 20040746.pdf (2581 kb)
    155. 2003-06-30---------Jump to [Top]
  155. Safer Nuclear Energy for the Future, by D.A. Meneley, AECL, 2003-06-30. Doc type: Presentation.
    Summary: Series of lectures by Dan Meneley presented at the 28th International Summer College on Physics and Contemporary Needs, June 30 - July 12, 2003, Nathiagali, Pakistan
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual Performance Safety [Phase] Concept Design Safety [Audience] Engineer Manager
    - Introduction 20041000.pdf (77 kb)
    - Lecture 1 - Safety Perspectives, by D.A. Meneley, 20041001.pdf (115 kb)
    - Lecture 2 - Past Design Evolution, by D.A. Meneley, 20041002.pdf (103 kb)
    - Lecture 3 - Future Design Directions, by D.A. Meneley, 20041003.pdf (136 kb)
    - Lecture 4 - The Long Term, by D.A. Meneley, 20041004.pdf (205 kb)
    156. 2003-10-01---------Jump to [Top]
  156. Nuclear Safety & Reliability Course, by D.A. Meneley, University of New Brunswick, 2003-10-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Design Safety [Audience] Grad Ugrad
    - Cover Page 20032200.pdf (89 kb)
    - Week 1, by D.A. Meneley, 20032201.pdf (293 kb)
    - Week 2, by D.A. Meneley, 20032202.pdf (461 kb)
    - Week 3, by D.A. Meneley, 20032203.pdf (378 kb)
    - Week 4, by D.A. Meneley, 20032204.pdf (335 kb)
    - Week 5, by D.A. Meneley, 20032205.pdf (666 kb)
    - Week 6, by D.A. Meneley, 20032206.pdf (636 kb)
    - Week 7, by D.A. Meneley, 20032207.pdf (930 kb)
    - Week 8, by D.A. Meneley, 20032208.pdf (1943 kb)
    - Week 9, by D.A. Meneley, 20032209.pdf (2120 kb)
    - Week 10, by D.A. Meneley, 20032210.pdf (433 kb)
    - Week 11, by D.A. Meneley, 20032211.pdf (476 kb)
    - Week 12, by D.A. Meneley, 20032212.pdf (353 kb)
    157. 2004-01-01---------Jump to [Top]
  157. Fluid Mechanics, CNSC, 2004-01-01. Doc type: Course.
    Summary: Fluid systems are the backbone of nuclear power plants and the CANDU stations are no exception. We will use the term fluid as a generic term for both liquids and gases. The fluid systems are used primarily as heat transport vehicles. An example would be the generator stator cooling system. Heat generated in the stator windings is transferred to the closed-loop stator cooling system and then to the low-pressure service water. This module is designed to help you understand processes that occur in individual fluid handling parts and devices as well as entire systems.
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - 20040601.pdf (353 kb)
    - , 20070300.pdf (336 kb)
    158. 2004-04-20---------Jump to [Top]
  158. The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators, by J.M. Dyke, Individual Contributions, 2004-04-20. 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
    - 12th International Conference on Nuclear Engineering, Washington, DC 20054201.pdf (1714 kb)
    - Associated Presentation, by J.M. Dyke, 20054202.pdf (1558 kb)
    159. 2004-07-17---------Jump to [Top]
  159. 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)
  160. 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)
  161. 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)
  162. 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)
    163. 2005-05-01---------Jump to [Top]
  163. CANDU 6 Technical Summary, by AECL staff, AECL, 2005-05-01. Doc type: Report.
    Summary: This Technical Summary provides an overview of the CANDU 6 nuclear power system. All CANDU 6 power plants are fundamentally the same, although there are differences in detail: these largely result from different site conditions, and from improvements made in the newer designs. The evolution of CANDU 6 is illustrated in the inside back cover.
    Keywords: [Concept] - [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] General Engineering [Topic] Process Systems [Phase] Design [Audience] College Engineer High Manager Ugrad Vendor
    - CANDU6_TechnicalSummary-s.pdf (3750 kb)
    164. 2006-03-01---------Jump to [Top]
  164. 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)
    165. 2006-04-01---------Jump to [Top]
  165. 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)
    166. 2010-01-01---------Jump to [Top]
  166. ACR-1000 Technical Description Summary, AECL, 2010-01-01. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - 20100100.pdf (2399 kb)
    167. 2010-03-01---------Jump to [Top]
  167. Why Ontario Generates So Much Electricity from Nuclear Energy, by Lorne G. McConnell, CNA, 2010-03-01. Doc type: Paper.
    Summary: This historical review provides an excellent summary of the context in which CANDU was conceived, designed, built, commissioned and operated. The origins of some of the major characteristic features of CANDU are also given. Note: Figure G3 herein is a corrected version of the original published version which contained a scale error.
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] History [Topic] Intro and Overview [Phase] Commissioning Concept Construction Design Operation [Audience] College
    - 20100500.pdf (5844 kb)
    168. 2010-09-07---------Jump to [Top]
  168. 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, by Blair P. Bromley, FJOHSS, 2010-09-07. Doc type: Lecture.
    Summary:
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] History Nuclear Engineering Physics [Topic] Conceptual Important Parameters Intro and Overview Physical Description [Phase] Concept Design Design Description Design Evolution [Audience] College Engineer Manager Ugrad
    - Main Lecture - Short Version 20110201.pdf (3441 kb)
    - Main Lecture - Long Version, by Blair P. Bromley, 20110202.pdf (10737 kb)
    - Supplement 1: R&D Activities for HWR Design and Safety Analysis, by Blair P. Bromley, 20110203.pdf (8280 kb)
    - Supplement 2: Alternative Concepts and Early HWR Prototypes, by Blair P. Bromley, 20110204.pdf (8403 kb)
    169. 2015-01-01---------Jump to [Top]
  169. 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)
    170. 2017-02-13---------Jump to [Top]
  170. 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)
    171. 2017-12-27---------Jump to [Top]
  171. Canada's Power Reactor Fuel Bundle Design and Development, by R.D. Page and A.J. Langdon, AECL, 2017-12-27. Doc type: Other.
    Summary: This pictorial record of Canada's power reactor fuel bundles was prepared to historically record the evolution of the power reactor fuel over the years. No one report issued over the years has been able to describe in detail the various changes that these pictures portray. It should be noted that the record does not include WR-1 type fuel or special irradiation of assemblies. "A picture speaks a thousand words". Full resolution versions of the images contained in this document can be found in the Image Library of CANTEACH web site http://canteach.candu.org listed under the System Index (SI) 37000 - Fuel.
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Materials Engineering Mechanical Engineering [Topic] Chemistry Fluid Mechanics Heat Transfer Physical Description Thermalhydraulics [Phase] Concept Design Design Evolution [Audience] College Engineer Grad High Manager Technician Ugrad
    - Historical and Pictorial Record FuelStory.pdf (355 kb)
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