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[Phase]: Concept 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: 786

    1950-01-01---------Jump to [Top]
  1. Simulation Software, by Wm.J. Garland, McMaster University, 1950-01-01. Doc type: Essay.
    Summary: Major endeavours such as a CANDU nuclear power plant involves extensive engineering calculations usually performed using large simulation tools.  However, to aid in conceptual BOE (back of envelope) evaluations and for education and training exercises, simplified and focused calculations are often done.  To aid students and working professional alike, a few such small tools (primarily spreadsheets) are linked below.  Go to Topics: Modelling to see the full list.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor Steam Generators and Auxiliaries [Discipline] General Engineering Mechanical Engineering Nuclear Engineering [Topic] Basic Equations Conceptual Heat Transfer Modelling Process Systems Reactor Physics Thermalhydraulics [Phase] Concept Design Analysis [Audience] College Engineer Grad Technician Ugrad
    - SimulationSoftware.pdf (267 kb)
    2. 1956-01-01---------Jump to [Top]
  2. 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)
    3. 1962-09-01---------Jump to [Top]
  3. Reactor Loops at Chalk River, by Ronald Needham, AECL, 1962-09-01. Doc type: Paper.
    Summary: Description of the Chalk River NRX and NRU in-reactor test loops for materials testing under simulated reactor power conditions.
    Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Materials Engineering Nuclear Engineering [Topic] Radiation Reactor Physics Thermalhydraulics [Phase] Concept [Audience] Engineer Technician Ugrad
    - CRL-Loops1962.pdf (1547 kb)
    4. 1962-11-22---------Jump to [Top]
  4. NPD Generatig Station Index, OPG, 1962-11-22. Doc type: Other.
    Summary: Numerical system index and subject index for the NPD nuclear power plant.
    Keywords: [Concept] General [SI] 00000 General Project [Discipline] General Engineering [Topic] Index [Phase] Concept [Audience] Engineer Technician
    - System Index, General Subject Index NPD-Index-1962.pdf (231 kb)
    5. 1964-08-01---------Jump to [Top]
  5. 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)
  6. 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)
  7. 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)
    8. 1965-01-01---------Jump to [Top]
  8. 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)
    9. 1966-07-01---------Jump to [Top]
  9. 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)
    10. 1967-07-01---------Jump to [Top]
  10. 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)
    11. 1970-03-09---------Jump to [Top]
  11. 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)
    12. 1972-05-25---------Jump to [Top]
  12. 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)
  13. 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)
    14. 1974-07-01---------Jump to [Top]
  14. 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)
    15. 1977-01-01---------Jump to [Top]
  15. 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)
    16. 1978-04-01---------Jump to [Top]
  16. 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)
  17. 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)
    18. 1978-08-01---------Jump to [Top]
  18. 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)
    19. 1980-04-01---------Jump to [Top]
  19. Mathematics, Course 221, OPG, 1980-04-01. Doc type: Course.
    Summary: This course proves an introduction to two topics: equipment reliability evaluation, and calculus.
    Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept Operation [Audience] Engineer Manager
    - Full Course 20043000.pdf (3593 kb)
    - 221.00-1 Index and Objectives, 20043001.pdf (124 kb)
    - 221.00-2 Indroduction, 20043002.pdf (132 kb)
    - 421.10-4 Standard Notation, 20043003.pdf (122 kb)
    - 421.20-1 Algebra Fundamentals, 20043004.pdf (239 kb)
    - 421.40-1 Graphs, 20043005.pdf (153 kb)
    - 421.40-2 Graphing Functions, 20043006.pdf (80 kb)
    - 321.10-3 Logarithms and Exponentials, 20043007.pdf (210 kb)
    - 321.10-4 Use of Logarithmic Scaled Graph Paper, 20043008.pdf (347 kb)
    - 221.10-1 Basic Reliability Concepts, 20043009.pdf (154 kb)
    - 221.20-1 The Straight Line, 20043010.pdf (166 kb)
    - 221.20-2 The Derivative, 20043011.pdf (259 kb)
    - 221.20-3 Simple Applications of Derivatives, 20043012.pdf (127 kb)
    - 221.20-4 Differentiating Exponential Functions, 20043013.pdf (193 kb)
    - 221.20-5 The Derivative in Science and Technology, 20043014.pdf (213 kb)
    - 221.30-1 The Integral, 20043015.pdf (194 kb)
    - 221.30-2 Application of the Integral as an Infinite Sum, 20043016.pdf (371 kb)
    - 221.40-1 Appendix 1 : Review Exercises, 20043017.pdf (202 kb)
    - 221.40-2 Appendix 2 : Questions Bearing Directly on Course 221 Content from Recent AECB Nuclear General Examinations, 20043018.pdf (75 kb)
    - 221.40-3 Appendix 3 : Solving Quadratic Equations, 20043019.pdf (84 kb)
    - 221.40-4 Answers to Assignments and Review Exercises, 20043020.pdf (268 kb)
    20. 1980-08-01---------Jump to [Top]
  20. 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)
    21. 1981-01-01---------Jump to [Top]
  21. 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)
    22. 1981-07-01---------Jump to [Top]
  22. Mathematics, Nuclear Training Course 121, OPG, 1981-07-01. Doc type: Course.
    Summary: Probability and reliability concepts applied to station operation.
    Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept [Audience] Engineer Manager
    - Cover page, Table of contents, Objectives 20040101.pdf (167 kb)
    - Introduction, 20040102.pdf (194 kb)
    - Probability, 20040103.pdf (610 kb)
    - Safety Systems Analysis, 20040104.pdf (404 kb)
    - Safety Systems Analysis - Solutions to Sample Problems, 20040105.pdf (455 kb)
    - The Binomial Distribution and Power System Reliability, 20040106.pdf (302 kb)
    - The Normal Distribution and Applications, 20040107.pdf (193 kb)
    - Basic Reliability Concepts, 20040108.pdf (638 kb)
    - Operation in the Wearout Mode, 20040109.pdf (237 kb)
    - Some Modern Reliability Topics, 20040110.pdf (634 kb)
    - Appendix 1: Confidence Limits, 20040111.pdf (219 kb)
    - Appendix 2: Solutions to Assignments, 20040112.pdf (636 kb)
    23. 1981-11-01---------Jump to [Top]
  23. 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)
    24. 1984-03-01---------Jump to [Top]
  24. 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)
    25. 1984-12-01---------Jump to [Top]
  25. 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)
    26. 1985-04-24---------Jump to [Top]
  26. 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)
    27. 1987-03-01---------Jump to [Top]
  27. Nuclear Journal of Canada, 1987 Vol 1 No. 1, by Hans G. Forsstrom, CNS-, 1987-03-01. Doc type: Paper.
    Summary: The implementation of the Swedish radioactive Waste management system is making good progress. A central interim storage facility for spent nuclear fuel and a sea-based transportation system for spent fuel and other radioactive residues are already In operation. An underground final disposal facility for low- and medium-level waste from reactor operation is under construction. For the remaining steps (final disposal of spent fuel and long-lived radioactive residues) one concept has been developed and approved. Research and development work is continuing, to provide the basis of a final decision on disposal method and site for around the year 2000. This decision will be based on a broad evaluation of available alternative designs.
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Concept [Audience] College Engineer Grad High Manager Technician Ugrad Vendor
    - Progress of the Swedish Radioactive Waste Management Program NJC-1-1-06.pdf (1534 kb)
    - A Non-Intrusive Neutron Method for Poison Concentration Monitoring in CANDU Reactors, by E.M.A. Hussein, D.R. OConnor and M.E. Mosher, NJC-1-1-07.pdf (427 kb)
    - Containment Systems Capability, by W.G. Morison, W. J. Penn, K. Hassmann, J.D. Stevenson, K. Elisson, NJC-1-1-08.pdf (1131 kb)
    28. 1987-06-01---------Jump to [Top]
  28. Nuclear Journal of Canada, 1987 Vol 1 No. 2, by J.L. Gray, CNS-, 1987-06-01. Doc type: Paper.
    Summary: This paper identifies about twenty major decisions of the Canadian Nuclear Power Program from its inception in 1942 to maturity - the decision of Ontario Hydro to complete the Pickering Nuclear Power Station and proceed with a major nuclear power installation program. The decisions are discussed briefly.
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] Concept Construction Operation [Audience] College Engineer Grad Manager Technician Ugrad
    - Early Decisions in the Development of the CANDU Program NJC-1-2-02.pdf (719 kb)
    - Characterization of Radioactive Wastes Incorporated in a Cement Matrix, by E.R. Merz, D. Dyckerhoff and R. Odoj, NJC-1-2-10.pdf (501 kb)
    - Spent Fuel Storage and Transportation Experience for the Idaho National Engineering Laboratory, by C.P. Gertz, D.H. Schoonen and B.H. Wakeman, NJC-1-2-11.pdf (702 kb)
    29. 1987-09-01---------Jump to [Top]
  29. Nuclear Journal of Canada, 1987 Vol 1 No. 3, by W.T. Hancox, CNS-, 1987-09-01. Doc type: Paper.
    Summary: This paper describes the Canadian concept for safe, permanent disposal of nuclear fuel waste deep in plutonic rock of the Canadian Shield. The ability of the disposal concept to isolate the wastes is then discussed in the light of laboratory and field research results. The methodlogy developed to characterize the hydrogeology of a plutonic rock mass is outlined and results obtained from its application to a field site are described. Also highlighted are the Canadian field research areas and the Underground Research Laboratory.
    Keywords: [Concept] General [SI] 03400 Radiation Protection (including Waste Management) [Discipline] General Engineering [Topic] Waste Handling [Phase] Concept [Audience] College Engineer Grad High Manager Technician Ugrad
    - Safe, Permanent Disposal of Nuclear Fuel Waste NJC-1-3-07.pdf (942 kb)
    - The Projected Environmental Impacts of Transportation of Radioactive Material to the First United States Repository Site - An Overview, by J.W. Cashwell, K.S. Neuhauser, P.C. Reardon and G.W. McNair, NJC-1-3-08.pdf (491 kb)
    30. 1987-12-01---------Jump to [Top]
  30. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by J.M. Bewers, CNS-, 1987-12-01. Doc type: Paper.
    Summary: This paper outlines the history and regulation of sea dumping of packaged low-level radioactive waste in the ocean. The procedures by which dumping limits are established and periodic safety evaluations conducted under international auspices are described. Particular reference is made to recent negotiations on the future of the practice within the London Dumping Convention and the role played by Canada in this forum, and in others relevant to this subject.
    Keywords: [Concept] General [SI] 03400 Radiation Protection (including Waste Management) [Discipline] General Engineering [Topic] Waste Handling [Phase] Concept [Audience] College Engineer Grad High Manager Technician Ugrad
    - Sea Dumping of Radioactive Wastes NJC-1-4-03.pdf (1065 kb)
    - Suitability Study of On-Line Leak Tests for CANDU Single-Unit Containment Buildings, by J.F. Lafortune, C.A. McDevitt and S. Poolpol, NJC-1-4-05.pdf (846 kb)
    - Fusion Materials Issues, by P.c. Stangeby and A.A. Haasz, NJC-1-4-08.pdf (916 kb)
    31. 1988-04-01---------Jump to [Top]
  31. 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)
    32. 1989-05-01---------Jump to [Top]
  32. CANDU Advanced Plutonium Burner - The Canadian Response to the ALWR, by A.R. Dastur and A.C. Mao, AECL, 1989-05-01. Doc type: Paper.
    Summary: As published in the Canadian Nuclear Society Bulletin Vol. 10, No. 3, 1989 with the kind permission of the CNS: It is demonstrated that the prescnt CANDU design concept has potential for increased conversion and resource utilization compared with other reactor concepts. Discussed here is a CANDU based concept thau utilizes energy produced by subcritical multiplication in a fertile region designed for accelerated plutonium production is presented. Its feasibility is based on incorporating the channels with fertile material into the primary heal transport circuit. Calculations with multigroup transport codes predict very high fuel utilization due to the production and burnup of fissile plutonium in the fertile region.
    Keywords: [Concept] Reactor Physics [SI] 03300 Nuclear Engineering 31000 Reactor 37000 Fuel [Discipline] Nuclear Engineering [Topic] Conceptual Reactor Physics [Phase] Concept [Audience] Engineer Grad Manager Ugrad Vendor
    - 19890101.pdf (299 kb)
    33. 1990-01-01---------Jump to [Top]
  33. 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)
  34. Reliability for Management and Professional Staff , Course PI 21, Nuclear Training Centre, OPG, 1990-01-01. Doc type: Course.
    Summary: A six part introductory reliability course for management and professional staff.
    Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept Operation [Audience] Engineer Manager
    - Full Course 20043300.pdf (1585 kb)
    - Course Table of Contents, 20043301.pdf (219 kb)
    - PI 21.00 Intro to the Course, 20043302.pdf (104 kb)
    - PI 21.01 An Introduction to Reliability, 20043303.pdf (166 kb)
    - PI 21.02 Reliability Concepts, 20043304.pdf (384 kb)
    - PI 21.03 Process Systems, 20043305.pdf (185 kb)
    - PI 21.04 Availability of Safety Systems, 20043306.pdf (250 kb)
    - PI 21.05 Modern Reliability Techniques, 20043307.pdf (208 kb)
    - PI 21.06 Reporting and Administration, 20043308.pdf (111 kb)
  35. 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)
    36. 1990-07-01---------Jump to [Top]
  36. 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)
    37. 1991-08-01---------Jump to [Top]
  37. 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)
    38. 1992-08-01---------Jump to [Top]
  38. 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)
    39. 1993-01-01---------Jump to [Top]
  39. Fundamentals of Power Reactors, CNSC, 1993-01-01. Doc type: Course.
    Summary: Fundamentals of power reactors covering basic nuclear processes, basic thermodynamics, thermalhydraulics, materials, nuclear systems and radiation protection.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Operation [Audience] College Engineer Ugrad
    - Science & Engineering Fundamentals - Part 1 19930201.pdf (5929 kb)
    - Science & Engineering Fundamentals - Part 2, 19930202.pdf (7656 kb)
    - Nuclear Reactor System - Part 1, 19930203.pdf (6312 kb)
    - Nuclear Reactor System - Part 2, 19930204.pdf (8311 kb)
    - Nuclear Reactor System - Part 3, 19930205.pdf (3791 kb)
    - Nuclear Reactor System - Part 4, 19930206.pdf (4327 kb)
    - Radiation Protection, 19930207.pdf (5465 kb)
  40. 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)
  41. 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)
  42. 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)
    43. 1993-02-01---------Jump to [Top]
  43. 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)
    44. 1993-06-01---------Jump to [Top]
  44. 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)
    45. 1994-09-01---------Jump to [Top]
  45. 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)
    46. 1995-09-11---------Jump to [Top]
  46. 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)
    47. 1996-02-01---------Jump to [Top]
  47. 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)
  48. 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)
  49. 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)
  50. 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)
  51. 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)
  52. 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)
  53. 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)
  54. 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)
  55. 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)
  56. 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)
  57. 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)
  58. 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)
  59. 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)
  60. Neutron Activation Analysis, Course 6.2, by L. Zikovsky, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Nuclear Engineering [Topic] Conceptual [Phase] Concept [Audience] College Engineer Technician Ugrad
    - Chapter 00 - Title and TOC 20052801.pdf (286 kb)
    - Chapter 01 - Activation Analysis, by L. Zikovsky, 20052802.pdf (231 kb)
    - Chapter 02 - General Aspects in Trace Analysis, by L. Zikovsky, 20052803.pdf (198 kb)
    - Chapter 03 - Neutron Induced Reactions, by L. Zikovsky, 20052804.pdf (1636 kb)
    - Chapter 04 - Neutron Sources, by L. Zikovsky, 20052805.pdf (791 kb)
    - Chapter 05 - Growth & Decay of Radioactivity During & After Irradiation, by L. Zikovsky, 20052806.pdf (735 kb)
    - Chapter 06 - Nuclear Disintegration & Radiation Detection, by L. Zikovsky, 20052807.pdf (1459 kb)
    - Chapter 07 - Preparation of Samples & Standards, by L. Zikovsky, 20052808.pdf (1695 kb)
    - Chapter 08 - Activation Analysis with Radiochemical Separations, by L. Zikovsky, 20052809.pdf (1291 kb)
    - Chapter 09 - Analysis Without Chemical Separation, by L. Zikovsky, 20052810.pdf (893 kb)
    - Chapter 10 - Systematic Errors in Activation Analysis, by L. Zikovsky, 20052811.pdf (1410 kb)
    - Chapter 11 - Statistical Interpretation of Results, by L. Zikovsky, 20052812.pdf (1455 kb)
    - Workbook 01 - Activation Analysis = Elemental & Isotopic Analysis, by L. Zikovsky, 20052813.pdf (55 kb)
    - Workbook 02 - Structure of Chlorophyll, by L. Zikovsky, 20052814.pdf (74 kb)
    - Workbook 03 - The Nuclear Reaction & Types of Nuclear Particles Employed, by L. Zikovsky, 20052815.pdf (175 kb)
    - Workbook 04 - Irradiation Sources, by L. Zikovsky, 20052816.pdf (238 kb)
    - Workbook 05 - Quantitative Relationships, by L. Zikovsky, 20052817.pdf (115 kb)
    - Workbook 06 - Nuclear Disintegration & Radiation Detection, by L. Zikovsky, 20052818.pdf (289 kb)
    - Workbook 07 - Apparatus to Avoid Contamination, by L. Zikovsky, 20052819.pdf (37 kb)
    - Workbook 08 - Application of HAP to Activation Analysis of Urine, by L. Zikovsky, 20052820.pdf (52 kb)
    - Workbook 09 - Decay Curve of Chlorine in a Terphenyl Sample, by L. Zikovsky, 20052821.pdf (188 kb)
    - Workbook 10 - Sources of Errors in NAA, by L. Zikovsky, 20052822.pdf (224 kb)
    - Workbook 11 - Optimum Counting Time as Function of Counting Rate and Background Rate, by L. Zikovsky, 20052823.pdf (90 kb)
    - Workbook 12 - Typical analysis schemes for fluids and solids, by L. Zikovsky, 20052824.pdf (148 kb)
  61. 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)
  62. Corrosion for Engineers, Course 7.3, by D. Lister, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: Corrosion cost and measurement, eight forms of corrosion.
    Keywords: [Concept] Chemistry and Corrosion [SI] 31000 Reactor [Discipline] Chemistry [Topic] Corrosion [Phase] Concept Operation [Audience] College Engineer Ugrad
    - Workbook 01 - Cost of Corrosion 20053201.pdf (294 kb)
    - Workbook 02 - Corrosion Measurement, by D. Lister, 20053202.pdf (312 kb)
    - Workbook 03 - Eight Forms of Corrosion, by D. Lister, 20053203.pdf (249 kb)
    - Workbook 04 - Galvanic Corrosion, by D. Lister, 20053204.pdf (751 kb)
    - Workbook 05 - Crevice Corrosion, by D. Lister, 20053205.pdf (587 kb)
    - Workbook 06 - Pittings, by D. Lister, 20053206.pdf (280 kb)
    - Workbook 07 - Intergranular Corrosion, by D. Lister, 20053207.pdf (465 kb)
    - Workbook 08 - Selective Leaching, by D. Lister, 20053208.pdf (462 kb)
    - Workbook 09 - Stress Corrosion, by D. Lister, 20053209.pdf (497 kb)
    - Workbook 10 - Erosion Corrosion, by D. Lister, 20053210.pdf (332 kb)
    - Workbook 11 - Hydrogen Effects (pdf 136 kb, 6 pages), by D. Lister, 20053211.pdf (125 kb)
    - Workbook 12 - Acoustic Corrosion Thermodynamics, by D. Lister, 20053212.pdf (538 kb)
    - Workbook 13 - Corrosion Current, by D. Lister, 20053213.pdf (611 kb)
  63. 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)
    64. 1996-12-05---------Jump to [Top]
  64. 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)
    65. 1997-01-01---------Jump to [Top]
  65. 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)
  66. 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)
    67. 1997-03-18---------Jump to [Top]
  67. 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)
    68. 1997-06-01---------Jump to [Top]
  68. 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)
    69. 1997-10-01---------Jump to [Top]
  69. 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)
    70. 1998-02-01---------Jump to [Top]
  70. 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)
  71. 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)
    72. 1998-09-22---------Jump to [Top]
  72. 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)
    73. 1999-02-23---------Jump to [Top]
  73. 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)
  74. 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)
    75. 1999-10-01---------Jump to [Top]
  75. 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)
    76. 2000-11-01---------Jump to [Top]
  76. 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)
    77. 2000-12-01---------Jump to [Top]
  77. 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)
    78. 2001-01-03---------Jump to [Top]
  78. 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)
    79. 2001-02-01---------Jump to [Top]
  79. 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)
    - The Origin and Evolution of the Second Shutdown System, by Gordon L. Brooks, 20010305.pdf (101 kb)
    80. 2001-03-06---------Jump to [Top]
  80. 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)
    81. 2002-01-01---------Jump to [Top]
  81. 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)
  82. 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)
  83. 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)
  84. 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)
  85. 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)
  86. 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)
  87. 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)
  88. 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)
  89. 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)
    90. 2002-09-01---------Jump to [Top]
  90. 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)
    91. 2002-09-25---------Jump to [Top]
  91. 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)
    92. 2003-01-01---------Jump to [Top]
  92. 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)
  93. 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)
    94. 2003-04-20---------Jump to [Top]
  94. 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)
    95. 2003-06-24---------Jump to [Top]
  95. 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)
  96. 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)
    97. 2003-06-30---------Jump to [Top]
  97. 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)
    98. 2004-01-01---------Jump to [Top]
  98. 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)
    99. 2004-04-20---------Jump to [Top]
  99. 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)
    100. 2004-07-17---------Jump to [Top]
  100. 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)
  101. 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)
  102. 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)
    103. 2006-03-01---------Jump to [Top]
  103. 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)
    104. 2006-04-01---------Jump to [Top]
  104. 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)
    105. 2010-01-01---------Jump to [Top]
  105. 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)
    106. 2010-03-01---------Jump to [Top]
  106. 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)
    107. 2010-09-07---------Jump to [Top]
  107. 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)
    108. 2011-01-01---------Jump to [Top]
  108. Concept Maps, by Wm.J. Garland, CANTEACH, 2011-01-01. Doc type: Other.
    Summary: Illustrated are the overall concepts and topics in the various disciplines involved in the design and operation of CANDU reactors. This provides some guidance for the detailed study of CANDU reactors.
    Keywords: [Concept] Overview [SI] - [Discipline] Nuclear Engineering [Topic] Conceptual Intro and Overview [Phase] Concept [Audience] College Engineer Grad High Manager Technician Ugrad
    - Overview of Concepts and Topics 20110101.pdf (264 kb)
    109. 2017-02-13---------Jump to [Top]
  109. 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)
    110. 2017-12-27---------Jump to [Top]
  110. 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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