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[Discipline]: Nuclear Engineering 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: 837

    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. 1958-09-01---------Jump to [Top]
  3. NPD-2 Design Description, OPG, 1958-09-01. Doc type: Report.
    Summary: This booklet presents a detailed design description of the NPD-2 station, a joint project of AECL, CGE and the Hydro-Electric Power Commission of Ontario.
    Keywords: [Concept] General [SI] 00000 General Project 30000 Reactor, Steam Generators and Auxiliaries 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Description [Audience] College Engineer High Technician Ugrad
    - Canada's First Nuclear Power Station CGE-NPD-DD-Sept1958.pdf (2766 kb)
    4. 1961-04-01---------Jump to [Top]
  4. NDP-2 Systems - Calandria Assembly, Course T.T.01-312, OPG, 1961-04-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heavy Water Physical Description Process Systems [Phase] Design [Audience] College Engineer Technician Ugrad
    - NPD-TT01-312-1961.pdf (2972 kb)
    5. 1961-05-01---------Jump to [Top]
  5. NDP-2 Systems - Moderator, Course T.T.4-4.320, OPG, 1961-05-01. Doc type: Course.
    Summary:
    Keywords: [Concept] General [SI] 32000 Moderator System [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] Design [Audience] College Engineer Technician Ugrad
    - General description only, 3 pages. NPD-TT4-4-320-1961.pdf (138 kb)
    6. 1961-09-18---------Jump to [Top]
  6. NPD, a Description of, by J.L Olsen, OPG, 1961-09-18. Doc type: Presentation.
    Summary: Nuclear Power Demonstration. An illustrated talk presented at the Seventh AECL Symposium on Atomic Energy, Chalk River, September 18, 1961.
    Keywords: [Concept] General [SI] 00000 General Project 30000 Reactor, Steam Generators and Auxiliaries 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Description [Audience] College Engineer High Technician Ugrad
    - Canada's First Nuclear Power Station CAPD10--Sept1961NPD-Description.pdf (5637 kb)
    7. 1962-09-01---------Jump to [Top]
  7. 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)
    8. 1962-11-01---------Jump to [Top]
  8. NPD Nucleonics Description, by Nucleonics, OPG, 1962-11-01. Doc type: Other.
    Summary:
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] - [Phase] Design Operation [Audience] College Engineer Grad Manager Technician Ugrad
    - NPD on the Line - a foldout description with layout diagrams and design date. NDP-NucleonicsNov1962.PDF (4922 kb)
    9. 1963-07-01---------Jump to [Top]
  9. NDP-2 Systems - Reactor, Course T.T.4-5.310, OPG, 1963-07-01. Doc type: Course.
    Summary:
    Keywords: [Concept] General [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] Design [Audience] College Engineer Technician Ugrad
    - General description only, 9 pages. NPD-TT4-5-310-1963.pdf (511 kb)
    10. 1966-11-01---------Jump to [Top]
  10. Reactor, Boiler and Auxiliaries, Course 133, Nuclear Training Center, OPG, 1966-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Full Course 20050900.pdf (10930 kb)
    - 133.00-00 Index, 20050901.pdf (252 kb)
    - 133.10-01 The Function of a Reactor, 20050902.pdf (262 kb)
    - 133.10-02 Reactor Classification - Fast and Thermal Reactors, 20050903.pdf (306 kb)
    - 133.10-03 Reactor Classification - Types of Thermal Reactors, 20050904.pdf (791 kb)
    - 133.10-04 Reactor Construction, 20050905.pdf (622 kb)
    - 133.20-01 Moderator Requirements, 20050906.pdf (227 kb)
    - 133.20-02 Moderator Materials Properties and Comparison, 20050907.pdf (459 kb)
    - 133.20-03 Moderator System and Equipment Considerations, 20050908.pdf (930 kb)
    - 133.30-01 Heat Transport Fluid Requirements, 20050909.pdf (401 kb)
    - 133.30-02 Heat Transport Fluid Comparisons, 20050910.pdf (600 kb)
    - 133.30-03 Main Circuit Considerations, 20050911.pdf (845 kb)
    - 133.30-04 Auxiliary Circuits, 20050912.pdf (708 kb)
    - 133.40-01 Reflector Systems, 20050913.pdf (367 kb)
    - 133.40-02 Shield Cooling Systems, 20050914.pdf (318 kb)
    - 133.50-01 Functions of Reactivity Mechanisms, 20050915.pdf (191 kb)
    - 133.50-02 Comparisons of Reactivity Mechanisms, 20050916.pdf (711 kb)
    - 133.62-01 Upgrading Requirements and Processes, 20050917.pdf (170 kb)
    - 133.62-02 Principles of Isotope Separation, 20050918.pdf (126 kb)
    - 133.62-03 The Distillation Upgrading Process, 20050919.pdf (258 kb)
    - 133.62-04 The Electrolytic Process, 20050920.pdf (149 kb)
    - 133.62-05 Common Problems, 20050921.pdf (183 kb)
    - 133.71-01 General Fuel Considerations, 20050922.pdf (190 kb)
    - 133.71-02 Fuel Preparation and Manufacture, 20050923.pdf (233 kb)
    - 133.71-03 Canadian Designs and Their Performance, 20050924.pdf (294 kb)
    - 133.91-01 Safety Standards and Safety Measures, 20050925.pdf (198 kb)
    - 133.91-02 Emergency Injection and Containment Systems, 20050926.pdf (160 kb)
    - 133.91-03 Safety System Performance, 20050927.pdf (199 kb)
    - 133.92-01Chemistry of Water Circuits, 20050928.pdf (940 kb)
    11. 1967-07-01---------Jump to [Top]
  11. 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)
    12. 1968-11-01---------Jump to [Top]
  12. Reactor Boiler and Auxiliaries, Course 433, Nuclear Training Centre, OPG, 1968-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Full Course 20051200.pdf (1786 kb)
    - 433.00-00 Index, 20051201.pdf (241 kb)
    - 433.10-01 Nuclear Power, 20051202.pdf (121 kb)
    - 433.10-02 Power Reactor Construction, 20051203.pdf (179 kb)
    - 433.20-01 Moderator Systems, 20051204.pdf (141 kb)
    - 433.30-01 Heat Transport Systems, 20051205.pdf (239 kb)
    - 433.40-01 Auxiliary Circuits, 20051206.pdf (205 kb)
    - 433.50-01 Fuel, 20051207.pdf (247 kb)
    - 433.50-02 Fuel Handling and Storage, 20051208.pdf (172 kb)
    - 433.60-01 Boiler Steam and Water Systems, 20051209.pdf (291 kb)
    13. 1969-01-01---------Jump to [Top]
  13. Pickering Generating Station Design Description, OPG, 1969-01-01. Doc type: Report.
    Summary:
    Keywords: [Concept] Overview [SI] 00000 General Project 10000 Site and Improvements 20000 Buildings and Structures 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries 50000 Electric Power Systems 60000 Instrumentation and Control [Discipline] General Engineering Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Operation Safety [Audience] College Engineer Technician Ugrad
    - OH-PickeringDD1969.pdf (23589 kb)
    14. 1970-03-09---------Jump to [Top]
  14. 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)
    15. 1971-03-01---------Jump to [Top]
  15. Fast Reactor Kinetics - The QXI Code, by D.A. Meneley, K.O. Ott and E.S. Wiener, Individual Contributions, 1971-03-01. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Modelling [Phase] Design Analysis Safety Analysis [Audience] Grad Ugrad
    - 20070100.pdf (7793 kb)
    16. 1971-09-06---------Jump to [Top]
  16. Commissioning and Operating Experience with Canadian Nuclear Electric Stations, by L. W. Woodhead, D. C. Milley, K. E. Elston, E.P. Horton, A. Dahlinger and R.C. Johnston, AECL, 1971-09-06. Doc type: Report.
    Summary:  
    Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Performance [Phase] Commissioning Operation [Audience] Engineer Manager Technician
    - Paper No. A/Conf. 49/A/148 presented at the Fourth U.N. International Conference on the Peaceful Uses of Atomic Energy, Geneva, 6-16 September, 1971 19710101.pdf (965 kb)
    17. 1972-05-25---------Jump to [Top]
  17. 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)
  18. 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)
    19. 1974-07-01---------Jump to [Top]
  19. 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)
    20. 1977-04-01---------Jump to [Top]
  20. Reactor, Boilers and Auxiliaries, Nuclear Training Course 133, OPG, 1977-04-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Cover Page, Table of Contents, Basic Moderator Requirements 20041301.pdf (194 kb)
    - Moderator System & Equipment, 20041302.pdf (911 kb)
    - Basic Heat Transport Fluid Requirements, 20041303.pdf (274 kb)
    - Main Heat Transport Circuit Considerations, 20041304.pdf (1476 kb)
    - Auxiliary PHT System Features, 20041305.pdf (477 kb)
    - Shield Systems, 20041306.pdf (446 kb)
    - Annulus Gas System, 20041307.pdf (97 kb)
    - Containment Systems, 20041308.pdf (522 kb)
    - Reactivity Mechanisms, 20041309.pdf (233 kb)
    - Practical Reactivity Mechanisms, 20041310.pdf (161 kb)
    - Choice of Reactivity Mechanisms, 20041311.pdf (855 kb)
    - Fuel - Design and Manufacturing Features, 20041312.pdf (447 kb)
    - Fuel Performance and Operating Experience, 20041313.pdf (213 kb)
    21. 1980-01-01---------Jump to [Top]
  21. Fundamentals of CANDU Reactor Nuclear Design (TDAI-244), by A.A. Pasanen, AECL, 1980-01-01. Doc type: Report.
    Summary: A Lecture Series given at Trieste 22 January - 28 March 1980, TDAI-244 1980 August
    Keywords: [Concept] - [SI] 31000 Reactor 37000 Fuel [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Manager Ugrad
    - Title and Table of Contents 20042000.pdf (176 kb)
    - Chapter 1 - Introduction, by A.A. Pasanen, 20042001.pdf (35 kb)
    - Chapter 2 - Physical Description of the CANDU-600, by A.A. Pasanen, 20042002.pdf (672 kb)
    - Chapter 3 - Methodology for Reactor Physics Analysis In Core Design, by A.A. Pasanen, 20042003.pdf (1922 kb)
    - Chapter 4 - Initial Fuel Loading Determination, by A.A. Pasanen, 20042004.pdf (379 kb)
    - Chapter 5 - Physics Analysis and Tests Related to Commissioning, by A.A. Pasanen, 20042005.pdf (764 kb)
    - Bibliography, by A.A. Pasanen, 20042006.pdf (111 kb)
    22. 1980-08-01---------Jump to [Top]
  22. 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)
    23. 1981-01-01---------Jump to [Top]
  23. 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)
    24. 1985-04-24---------Jump to [Top]
  24. 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)
    25. 1986-01-01---------Jump to [Top]
  25. Safety and Licensing Philosophy and Experience at Ontario Hydro Nuclear Generating Stations, by W. Lee, OPG, 1986-01-01. Doc type: Paper.
    Summary: As published in the Canadian Nuclear Society Bulletin Vol. 7, No. 1, 1986 with the kind permission of the CNS: The safely and licensing philosophy adopted by Ontario Hydro in establishing the need for retrofit design modifications to CANDU nuclear generating stations in operation since the early 1970's is discussed. This philosophy was developed in response to regulatory requests to determine whether this need exists in view of the more extensive safely and licensing design features incorporated in recent CANDU nuclear generating stations compared to the earlier designs. These addition features generally reflect evolving safety knowledge and licensing requirements over time.
    Keywords: [Concept] Safety [SI] 03600 Nuclear Safety (Reactor) 10000 Site and Improvements [Discipline] Nuclear Engineering [Topic] Safety [Phase] Operation Safety [Audience] Engineer Grad Manager Technician Ugrad
    - 19860101.pdf (2661 kb)
    26. 1987-03-01---------Jump to [Top]
  26. Nuclear Journal of Canada, 1987 Vol 1 No. 1, by E.M.A. Hussein, D.R. OConnor and M.E. Mosher, CNS-, 1987-03-01. Doc type: Paper.
    Summary: A neutron reflection method is developed for measuring the concentration of the neutron absorbing gadolinium in the tanks of the liquid poison injection shutdown system of a CANDU reactor. The feasibility of the method is demonstrated experimentally, and Monte Carlo simulations are utilized to design and model the performance of a proposed device.
    Keywords: [Concept] Reactor Physics [SI] 32700 Moderator Liquid Poison System [Discipline] Nuclear Engineering Physics [Topic] Reactor Physics [Phase] Concept [Audience] College Grad Technician Ugrad
    - A Non-Intrusive Neutron Method for Poison Concentration Monitoring in CANDU Reactors 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)
    - Gestion du cycle de combustible a la Centrale Nucleaire Gentilly-2, by G. Hotte, G. Parent, L. Cloutier, A. Aubin and N. Macici, NJC-1-1-10.pdf (762 kb)
    27. 1987-06-01---------Jump to [Top]
  27. 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)
    - Insights from Chernobyl on Severe Accident Assessment of CANDU Reactors, by J.T. Rogers, NJC-1-2-03.pdf (829 kb)
    - The Drift Flux Model in the ASSERTSubchannel Code, by M.B. Carver, R.A. Judd, J.E. Kiteley, and A. Tahir, NJC-1-2-08.pdf (742 kb)
    28. 1987-09-01---------Jump to [Top]
  28. Nuclear Journal of Canada, 1987 Vol 1 No. 3, by J.Q. Howieson and V.G. Snell, CNS-, 1987-09-01. Doc type: Paper.
    Summary: On 26 April 1986, the unit 4 reactor at the Chernobyl Nuclear Power Station in the Soviet Union suffered a severe accident which destroyed the reactor core. The reactor design, as it relates to the accident sequence, is reviewed in detail, using information presented in Soviet literature and at the International Atomic Energy Agency Post-Accident Review Meeting in August 1986.
    Keywords: [Concept] Safety [SI] 03600 Nuclear Safety (Reactor) [Discipline] Nuclear Engineering [Topic] Safety [Phase] Operation Safety [Audience] College Engineer Grad Technician Ugrad
    - Chernobyl - A Canadian Technical Perspective NJC-1-3-02.pdf (1766 kb)
    - CATHENA Simulation of Thermosiphoning in a Pressurized-Water Test Facility, by J.P. Mallory and P.J. Ingham, NJC-1-3-05.pdf (615 kb)
    - Book Review: Fallout from Chernobyl by L. Ray Silver, by A.N. Sinclair, NJC-1-3-09.pdf (104 kb)
    29. 1987-12-01---------Jump to [Top]
  29. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by L.L. Bennett, CNS-, 1987-12-01. Doc type: Paper.
    Summary: In light of the accident at the Chernobyl nuclear power station, 1986 represents a critical year for nuclear power programmes. This paper reviews the nuclear power programmes in a number of countries, and gives an overview of the current status and future prospects of nuclear power for electricity generation in the world, with particular emphasis to developing countries. The paper also presents economic comparisons of nuclear and coal-fired stations, since the competitiveness of nuclear power is an important factor in nuclear power development.
    Keywords: [Concept] Safety [SI] 03600 Nuclear Safety (Reactor) [Discipline] Nuclear Engineering [Topic] Safety [Phase] Operation Safety [Audience] College Engineer Grad Technician Ugrad
    - The Outlook for Nuclear Power after Chernobyl NJC-1-4-02.pdf (499 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)
    - Trivac: A Modular Diffusion Code for Fuel Management and Design Applications, by Alain Hebert, NJC-1-4-06.pdf (472 kb)
    - Fusion Materials Issues, by P.c. Stangeby and A.A. Haasz, NJC-1-4-08.pdf (916 kb)
    - Locating Gas Pipelines with Radioactive Sources, by Lubomir Zikovsky and Mostafa Yagoubi, NJC-1-4-11.pdf (145 kb)
    - Book Reviews: (1) Planet Earth in Jeopardy: Environmental Consequences of Nuclear War by Lydia Datto; (2) Understanding Chernobyl by The Uranium Institute, by Alan Wyatt, David Mosey, NJC-1-4-14.pdf (168 kb)
    30. 1989-05-01---------Jump to [Top]
  30. 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)
    31. 1990-01-01---------Jump to [Top]
  31. 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)
    32. 1990-07-01---------Jump to [Top]
  32. 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)
    33. 1991-08-01---------Jump to [Top]
  33. 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)
    34. 1992-06-01---------Jump to [Top]
  34. Reactor Boiler and Auxiliaries, Course 233, Nuclear Training, OPG, 1992-06-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Full Course 20053800.pdf (13185 kb)
    - Abstract and Table of Contents, 20053801.pdf (162 kb)
    - Module 0 - Introduction, 20053802.pdf (269 kb)
    - Module 1 - Moderator Heavy Water, 20053803.pdf (359 kb)
    - Module 2 - Moderator Circulation System, 20053804.pdf (418 kb)
    - Module 3 - Moderator Cover Gas System, 20053805.pdf (387 kb)
    - Module 4 - The Moderator Liquid Poison System, 20053806.pdf (578 kb)
    - Module 5 - The Moderator Purification System, 20053807.pdf (486 kb)
    - Module 6 - HTS Heat Sources and Heat Transfer Paths, 20053808.pdf (362 kb)
    - Module 7 - HTS Pressure and Inventory Control, 20053809.pdf (1482 kb)
    - Module 8 - Heat Transport System Shutdown Operation, 20053810.pdf (609 kb)
    - Module 9 - HTS Heavy Water, 20053811.pdf (602 kb)
    - Module 10 - Heat Transport System Auxiliaries, 20053812.pdf (755 kb)
    - Module 11 - Shutdown Systems, 20053813.pdf (704 kb)
    - Module 12 - Emergency Coolant Injection, 20053814.pdf (663 kb)
    - Module 13 - Containment, 20053815.pdf (1004 kb)
    - Module 14 - Annulus Gas System, 20053816.pdf (407 kb)
    - Module 15 - Shield Cooling Systems, 20053817.pdf (528 kb)
    - Module 16 - Fuel Performance, 20053818.pdf (751 kb)
    - Module 17 - Fuel Handling, 20053819.pdf (616 kb)
    - Module 18 - Unit Upsets, 20053820.pdf (1950 kb)
    35. 1992-08-01---------Jump to [Top]
  35. 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)
    36. 1993-01-01---------Jump to [Top]
  36. 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)
  37. 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)
    38. 1993-02-01---------Jump to [Top]
  38. Reactor, Boiler and Accessories, Course 233, OPG, 1993-02-01. Doc type: Course.
    Summary: Table of contents and Objectives for Course 233, Reactor, Boiler, and Auxiliaries.
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Table of Contents and Objectives 20042200.pdf (640 kb)
    - 233.20-1 Moderator and Main Moderator System, 20042201.pdf (485 kb)
    - 233.20-2 Moderator Purification, 20042202.pdf (241 kb)
    - 233.20-3 Moderator Cover Gas System, 20042203.pdf (202 kb)
    - 233.20-4 Moderator D2O Collection, 20042204.pdf (117 kb)
    - 233.20-5 Moderator Liquid Poison System, 20042205.pdf (343 kb)
    - 233.30-1 Heat Transport D2O and Heat Transport Main System, 20042206.pdf (284 kb)
    - 233.30-2 Heat Transport Pressurizing System, 20042207.pdf (277 kb)
    - 233.30-3 Heat Transport Purification, 20042208.pdf (235 kb)
    - 233.30-4 Heat Transport Gland Seal Circuit, 20042209.pdf (165 kb)
    - 233.30-5 Heat Transport Shutdown Cooling, 20042210.pdf (144 kb)
    - 233.30-6 Heat Transport Maintenance Cooling System, 20042211.pdf (56 kb)
    - 233.30-7 Heat Transport H2 Addition, 20042212.pdf (132 kb)
    - 233.30-8 Heat Transport Pressure Relief, 20042213.pdf (204 kb)
    - 233.30-9 Heat Transport D2O Collection, 20042214.pdf (100 kb)
    - 233.30-10 Heat Transport D2O Recovery, 20042215.pdf (113 kb)
    - 233.30-11 Emergency Coolant Injection System, 20042216.pdf (197 kb)
    - 233.30-12 Heat Sources and Transfer Paths, 20042217.pdf (271 kb)
    - 233.40-1 Shield Cooling Systems, 20042218.pdf (250 kb)
    - 233.40-2 Containment System, 20042219.pdf (462 kb)
    - 233.40-3 Annulus Gas System, 20042220.pdf (95 kb)
    - 233.60-1 Steam Supply System, 20042221.pdf (383 kb)
    - 233.70-1 Fuel Design and Manufacturing Features, 20042222.pdf (377 kb)
    - 233.70-2 Fuel Performance and Operating Features, 20042223.pdf (521 kb)
    39. 1995-06-25---------Jump to [Top]
  39. Effects Contributing to Positive Coolant Void Reactivity in CANDU, by J. J. Whitlock, Wm.J. Garland, M.S. Milgram, McMaster University, 1995-06-25. Doc type: Paper.
    Summary: The lattice cell properties leading to positive coolant void reactivity in the CANDU reactor are described. The effect is subdivided into spectral, spatial, and isotopic components, and described in terms of criticality factors based on the six-factor fo
    Keywords: [Concept] Reactor Physics [SI] 03000 Engineering Science and Technology 31000 Reactor [Discipline] Nuclear Engineering [Topic] Reactor Physics3 [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Whitlock_ANS_1995.pdf (777 kb)
    40. 1995-09-11---------Jump to [Top]
  40. 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)
    41. 1996-01-01---------Jump to [Top]
  41. Reactor Physics & Fuelling Strategies 1.4, by R.D. Page, Chulalongkorn University, 1996-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Reference to Lecture 10 - Canadian Power Reactor Fuel 20042115.pdf (2381 kb)
    - Reference to Lecture 12 - Results of a Survey on Accident and Safety Analysis Codes, Benchmarks. Verification and Validation Methods, by A.G. Lee and G.B. Wilkin, 20042117.pdf (482 kb)
    42. 1996-02-01---------Jump to [Top]
  42. 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)
  43. 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)
  44. 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)
  45. Reactor Physics & Fuelling Strategies 1.4, by John Brenciaglia, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: Descriptive reactor physics associated with fuel management. Simulation, flux mapping. Reference text used: Fundamentals of CANDU Reactor Nuclear Design (TDAI-244) (AECL)
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Lecture 1 - Reactor Design Philosophies 20042101.pdf (665 kb)
    - Lecture 2 - Use of Reactor Design Codes, by John Brenciaglia, 20042102.pdf (137 kb)
    - Lecture 3 - Lattice Parameter Calculations, by John Brenciaglia, 20042103.pdf (531 kb)
    - Lecture 4 - Core Design Analysis, by John Brenciaglia, 20042104.pdf (332 kb)
    - Lecture 5 - Time Dependence Simulation, by John Brenciaglia, 20042105.pdf (600 kb)
    - Lecture 6 - Initial Fuel Load, by John Brenciaglia, 20042106.pdf (253 kb)
    - Lecture 7 - Startup Physics Tests, by John Brenciaglia, 20042107.pdf (531 kb)
    - Lecture 8 - Power Distribution Control, by John Brenciaglia, 20042108.pdf (720 kb)
    - Lecture 9 - Safety Analysis Requirements, by John Brenciaglia, 20042109.pdf (392 kb)
    - Chapter 10 - Fuel Design Analysis, by John Brenciaglia, 20042110.pdf (187 kb)
    - Lecture 11 - Fueling Strategies and Cycles, by John Brenciaglia, 20042111.pdf (745 kb)
    - Lecture 12 - Research Reactors Requirements, by John Brenciaglia, 20042112.pdf (138 kb)
    - Reference to Lecture 8 - In-Core Fuel Management, by D.A. Jenkins, 20042113.pdf (1105 kb)
    - Reference to Lecture 9 - Role of Physics Analysis in Safety and Licensing, by H.C. Chow, 20042114.pdf (1389 kb)
    - Reference to Lecture 11 - Fuel Management & Reactor Operation - Review of Operating Experience, by G.M. Frescura and A.L. Wight, 20042116.pdf (1501 kb)
  46. 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)
  47. 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)
  48. 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)
  49. Reactor Licensing & Siting, Course 4.1, by F.C. Boyd, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Safety [Phase] Licensing [Audience] Engineer Manager Vendor
    - Section 01 - Schedules Made Persuant to the Nuclear Liability Act 20051501.pdf (299 kb)
    - Section 02 - Atomic Energy Control Regulations, by F.C. Boyd, 20051502.pdf (1000 kb)
    - Section 03 - Liability Act, by F.C. Boyd, 20051503.pdf (1128 kb)
    - Section 04 - Bill C-125 Physical Security, by F.C. Boyd, 20051504.pdf (1341 kb)
    - Section 05 - Transport Packaging, U and Th Mining, by F.C. Boyd, 20051505.pdf (2067 kb)
    - Section 06 - R-7 Containment, R-8 Shutdown, R-9 Emergency Cooling, by F.C. Boyd, 20051506.pdf (1114 kb)
    - Section 07 - R-10, R-58, R-75, by F.C. Boyd, 20051507.pdf (656 kb)
    - Section 08 - R-76, R-85, R-90, by F.C. Boyd, 20051508.pdf (653 kb)
    - Section 09 - R-99, R-104, by F.C. Boyd, 20051509.pdf (1128 kb)
    - Section 10 - AECB 1139 The Licensing Process, by F.C. Boyd, 20051510.pdf (937 kb)
    - Section 11 - Licensing Systems & Inspection, by F.C. Boyd, 20051511.pdf (1703 kb)
    - Workbook 01 - Licensing of Nuclear Facilities, by F.C. Boyd, 20051512.pdf (982 kb)
    - Workbook 02 - Siting of NPP, by F.C. Boyd, 20051513.pdf (624 kb)
    - Workbook 03 - Containment & Siting Requirements from IAEA Conference, 1967, by F.C. Boyd, 20051514.pdf (2248 kb)
  50. Principles of Nuclear Safety, Course 4.3, by L. Haacke, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety [Audience] Engineer Manager Vendor
    - Module 01 - Introduction to the Course 20051701.pdf (70 kb)
    - Module 02 - Safety Management & Safety Culture, by L. Haacke, 20051702.pdf (367 kb)
    - Module 03 - Defence in Depth, by L. Haacke, 20051703.pdf (599 kb)
    - Module 04 - Control/Cool/Contain, by L. Haacke, 20051704.pdf (324 kb)
    - Module 05 - Guaranteed Shutdown State, by L. Haacke, 20051705.pdf (212 kb)
    - Module 06 - Reliability Concepts, by L. Haacke, 20051706.pdf (807 kb)
    - Module 07 - Licensing Principles & Safety Assumptions, by L. Haacke, 20051707.pdf (593 kb)
    - Module 08 - Operating Policies & Procedures, by L. Haacke, 20051708.pdf (150 kb)
    - Module 09 - Hierarchy of Documents, by L. Haacke, 20051709.pdf (82 kb)
    - Module 10 - Authorizations & Approvals, by L. Haacke, 20051710.pdf (302 kb)
    - Module 11 - Change Control, by L. Haacke, 20051711.pdf (193 kb)
    - Module 12 - Emergency Procedures, by L. Haacke, 20051712.pdf (177 kb)
    - Module 13 - Quality Assurance, by L. Haacke, 20051713.pdf (239 kb)
    - Module 14 - Surveillance, by L. Haacke, 20051714.pdf (177 kb)
    - Module 15 - Impairments, by L. Haacke, 20051715.pdf (195 kb)
    - Module 16 - Emissions Compliance Monitoring, by L. Haacke, 20051716.pdf (148 kb)
    - Module 17 - Maintenance, by L. Haacke, 20051717.pdf (462 kb)
    - Module 18 - Investigating & Reporting Incidents, by L. Haacke, 20051718.pdf (326 kb)
    - Appendix I - Definitions, by L. Haacke, 20051719.pdf (371 kb)
    - Appendix II - Acronyms, by L. Haacke, 20051720.pdf (55 kb)
    - Appendix III - References, by L. Haacke, 20051721.pdf (11 kb)
    - Workbook 01 - Introduction to Ontario Hydro, by L. Haacke, 20051722.pdf (95 kb)
    - Workbook 02 - Safety Management & Safety Culture, by L. Haacke, 20051723.pdf (254 kb)
    - Workbook 03 - Defence in Depth, by L. Haacke, 20051724.pdf (206 kb)
    - Workbook 04 - Control/Cool/Contain, by L. Haacke, 20051725.pdf (93 kb)
    - Workbook 05 - Guaranteed Shutdown State, by L. Haacke, 20051726.pdf (68 kb)
    - Workbook 06 - Reliability Concepts, by L. Haacke, 20051727.pdf (144 kb)
    - Workbook 07 - Licensing Principles & Safety Assumptions, by L. Haacke, 20051728.pdf (190 kb)
    - Workbook 08 - Operating Policies & Principles, by L. Haacke, 20051729.pdf (39 kb)
    - Workbook 09 - Hierarchy of Documents, by L. Haacke, 20051730.pdf (24 kb)
    - Workbook10 - Authorizations & Approvals, by L. Haacke, 20051731.pdf (58 kb)
    - Workbook11 - Change Control, by L. Haacke, 20051732.pdf (32 kb)
    - Workbook 12 - Emergency Procedures, by L. Haacke, 20051733.pdf (60 kb)
    - Workbook 13 - Quality Assurance, by L. Haacke, 20051734.pdf (48 kb)
    - Workbook 14 - Surveillance, by L. Haacke, 20051735.pdf (39 kb)
    - Workbook 15 - Impairments, by L. Haacke, 20051736.pdf (48 kb)
    - Workbook 16 - Emissions Compliance Monitoring, by L. Haacke, 20051737.pdf (66 kb)
    - Workbook 17 - Maintenance, by L. Haacke, 20051738.pdf (124 kb)
    - Workbook 18 - Investigating & Reporting Incidents, by L. Haacke, 20051739.pdf (113 kb)
  51. Operation & Maintenance of a Nuclear Power Plant, Course 4.4, by D. McQuade, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Maintainability [Phase] Operation [Audience] Engineer Manager Technician
    - Title, Objectives, Text Index 20051801.pdf (374 kb)
    - Workbook 01 - Management of a Nuclear Power Plant, by D. McQuade, 20051802.pdf (591 kb)
    - Workbook 02 - Principles of Operation & Maintenance, by D. McQuade, 20051803.pdf (1187 kb)
    - Workbook 03 - Configuration Management, by D. McQuade, 20051804.pdf (620 kb)
    - Workbook 04 - Maintenance of an NPP, by D. McQuade, 20051805.pdf (1093 kb)
    - Workbook 05 - Outage Management, by D. McQuade, 20051806.pdf (1108 kb)
    - Workbook 06 - Specialist Requirements in Maintenance, by D. McQuade, 20051807.pdf (348 kb)
    - Workbook 07 - Operator and Maintenance Standards, by D. McQuade, 20051808.pdf (1048 kb)
    - Workbook 08 - System Surveillance, by D. McQuade, 20051809.pdf (795 kb)
    - Workbook 09 - Building the Total Team, by D. McQuade, 20051810.pdf (771 kb)
  52. 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)
  53. 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)
  54. 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)
  55. 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)
  56. 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)
  57. 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)
  58. 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)
    59. 1996-11-01---------Jump to [Top]
  59. CANDU Overiew, Course 3.2, by G. Bereznai, Chulalongkorn University, 1996-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Operation [Audience] College Engineer Ugrad
    - Chapter 0 - Title, Table of Contents, Objectives 20044201.pdf (89 kb)
    - Chapter 1 - Overall Unit, by G. Bereznai, 20044202.pdf (973 kb)
    - Chapter 2 - Reactor and Moderator, by G. Bereznai, 20044203.pdf (659 kb)
    - Chapter 3 - Reactor Control, by G. Bereznai, 20044204.pdf (881 kb)
    - Chapter 4 - Heat Transport, by G. Bereznai, 20044205.pdf (755 kb)
    - Chapter 5 - Steam, Turbine and Feedwater, by G. Bereznai, 20044206.pdf (666 kb)
    - Chapter 6 - Special Safety Systems, by G. Bereznai, 20044207.pdf (1131 kb)
    - Workbook, Chapter 0 - Table of Contents, Course Introduction, by G. Bereznai, 20044208.pdf (194 kb)
    - Workbook, Chapter 1 - Modules A to E, by G. Bereznai, 20044209.pdf (3559 kb)
    - Workbook, Chapter 2 - Modules A to C, by G. Bereznai, 20044210.pdf (688 kb)
    - Workbook, Chapter 3 - Modules A to C, by G. Bereznai, 20044211.pdf (2317 kb)
    - Workbook, Chapter 4 - Modules A to D, by G. Bereznai, 20044212.pdf (1115 kb)
    - Workbook, Chapter 5 - Modules A & B, by G. Bereznai, 20044213.pdf (1110 kb)
    - Workbook, Chapter 6 - Modules A to D, by G. Bereznai, 20044214.pdf (464 kb)
    60. 1997-01-01---------Jump to [Top]
  60. 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)
  61. 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)
    62. 1997-03-18---------Jump to [Top]
  62. 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)
    63. 1997-04-08---------Jump to [Top]
  63. Monte Carlo Method for Particle Transport Simulation, Course 1.6, by E. Hussein, Chulalongkorn University, 1997-04-08. Doc type: Course.
    Summary: A brief introduction to the basics of the Monte Carlo method, how the Boltzmann particle transport equation lends itself to solution by the Monte Carlo method, specific aspects of the MCNP code.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Modelling Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Chapter 0 - Table of Contents 20043501.pdf (59 kb)
    - Chapter 1 - Introduction, by E. Hussein, 20043502.pdf (30 kb)
    - Chapter 2 - Monte Carlo Method, by E. Hussein, 20043503.pdf (283 kb)
    - Chapter 3 - Boltzmann Transport Equation, by E. Hussein, 20043504.pdf (79 kb)
    - Chapter 4 - MCNP Input Structure, by E. Hussein, 20043505.pdf (29 kb)
    - Chapter 5 - Geometry in MCNP, by E. Hussein, 20043506.pdf (105 kb)
    - Chapter 6 - MCNP Source Parameters, by E. Hussein, 20043507.pdf (173 kb)
    - Chapter 7 - Physics & Material Cross-Sections, by E. Hussein, 20043508.pdf (67 kb)
    - Chapter 8 - Termination Parameters, by E. Hussein, 20043509.pdf (30 kb)
    - Chapter 9 - Importance Sampling, by E. Hussein, 20043510.pdf (122 kb)
    - Chapter 10 - Tallying, by E. Hussein, 20043511.pdf (163 kb)
    - Chapter 11 - Uncertainty Analysis, by E. Hussein, 20043512.pdf (177 kb)
    - Chapter 12 - Criticality in MCNP, by E. Hussein, 20043513.pdf (42 kb)
    - Workbook, Chapter 1, by E. Hussein, 20043514.pdf (60 kb)
    - Workbook, Chapter 2, by E. Hussein, 20043515.pdf (460 kb)
    - Workbook, Chapter 3, by E. Hussein, 20043516.pdf (103 kb)
    - Workbook, Chapter 4, by E. Hussein, 20043517.pdf (45 kb)
    - Workbook, Chapter 5, by E. Hussein, 20043518.pdf (167 kb)
    - Workbook, Chapter 6, by E. Hussein, 20043519.pdf (270 kb)
    - Workbook, Chapter 7, by E. Hussein, 20043520.pdf (95 kb)
    - Workbook, Chapter 8, by E. Hussein, 20043521.pdf (41 kb)
    - Workbook, Chapter 9, by E. Hussein, 20043522.pdf (195 kb)
    - Workbook, Chapter 10, by E. Hussein, 20043523.pdf (265 kb)
    - Workbook, Chapter 11, by E. Hussein, 20043524.pdf (281 kb)
    - Workbook, Chapter 12, by E. Hussein, 20043525.pdf (68 kb)
    64. 1997-06-01---------Jump to [Top]
  64. 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)
    65. 1997-08-01---------Jump to [Top]
  65. Nuclear Weapons and Nuclear Reactors, by Dan Meneley, OPG, 1997-08-01. Doc type: Report.
    Summary: This report addresses the tenuous link between nuclear power reactor development and the proliferation of nuclear weapons, particularly with respect to possible terrorist exploitation. Arguments are presented which contradict the popular image of nuclear weaponry as a "basement project".
    Keywords: [Concept] - [SI] 03600 Nuclear Safety (Reactor) [Discipline] Nuclear Engineering [Topic] Conceptual Waste Handling [Phase] Operation [Audience] Engineer Manager Vendor
    - Nuclear Studies & Safety Department, Ontario Hydro, Report No. 77157 20032001.pdf (101 kb)
  66. Reactor Core Analysis & Fuel Management, Course 1.5, by D. Rozon, Chulalongkorn University, 1997-08-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Chapter 5 - SLOWKIN: A Simplified Model for the Stimulation of Transients in a SLOWPOKE-2 Reactor 20043405.pdf (1297 kb)
    67. 1997-11-01---------Jump to [Top]
  67. Peer Evaluation Techniques, Course 4.5, by R.B. Taylor, Chulalongkorn University, 1997-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Performance [Phase] Operation [Audience] Engineer Manager Technician
    - Section 01 - Self-Assessment 20051901.pdf (410 kb)
    - Section 02 - Operational Safety Review, by R.B. Taylor, 20051902.pdf (394 kb)
    - Section 03 - Control of Plant Operations, by R.B. Taylor, 20051903.pdf (432 kb)
    - Section 04 - Operations, by R.B. Taylor, 20051904.pdf (474 kb)
    - Section 05 - Maintenance, by R.B. Taylor, 20051905.pdf (631 kb)
    - Section 06 - Housekeeping, Material Conditions, Industrial Safety, by R.B. Taylor, 20051906.pdf (246 kb)
    - Section 07 - Configuration Management, by R.B. Taylor, 20051907.pdf (218 kb)
    - Workbook 01 - Self-Assessment, by R.B. Taylor, 20051908.pdf (286 kb)
    - Workbook 02 - IAEA-OSART, by R.B. Taylor, 20051909.pdf (468 kb)
    - Workbook 03 - Control of Plant Activities, by R.B. Taylor, 20051910.pdf (228 kb)
    - Workbook 04 - Operations, by R.B. Taylor, 20051911.pdf (459 kb)
    - Workbook 05 - Maintenance, by R.B. Taylor, 20051912.pdf (515 kb)
    - Workbook 06 - Housekeeping, Material Conditions, Industrial Safety, by R.B. Taylor, 20051913.pdf (324 kb)
    - Workbook 07 - Configuration Management, by R.B. Taylor, 20051914.pdf (309 kb)
    68. 1997-12-01---------Jump to [Top]
  68. Reactor Core Analysis & Fuel Management, Course 1.5, by B. Rouben, Chulalongkorn University, 1997-12-01. Doc type: Course.
    Summary: A coupled neutronics-thermalhydraulics analysis of a loss-of-coolants accident (LOCA) in CANDU is presented. The calculation is performed with the CERBERUS (spatial-kinetics) module of the finite-core code RFSP, coupled to the thermalhydraulics code FIREBIRD. The power pulse which results fiom the hypothetical LOCA is assumed terminated by Shutdown System 1 (SDSl). The calculational methodology and the physics model used in the LOCA analysis are detailed. The significant parameters which govern the results of the calculation are discussed.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Chapter 1 - Coupled Neutronics-Thermalhydaulics LOCA Analysis 20043401.pdf (970 kb)
    - Chapter 2 - Core Physics Aspects of Safety Analysis, by B. Rouben, 20043402.pdf (1188 kb)
    - Chapter 4 - Fuel Management in CANDU, by B. Rouben, 20043404.pdf (1542 kb)
    - Workbook, Chapter 1 - Neutronics-Thermalhydraulics Overheads, by B. Rouben, 20043406.pdf (330 kb)
    - Workbook, Chapter 2 - Core Physics Overheads, by B. Rouben, 20043407.pdf (567 kb)
    - Chapter 3 - Fuel Management and Advanced Fuel Cycles, by D. Rozon, 20043403.pdf (1436 kb)
    69. 1998-02-01---------Jump to [Top]
  69. Neutronic Analysis of Reactors, Course 1.7, by J. Koclas, Chulalongkorn University, 1998-02-01. Doc type: Course.
    Summary: Covers methods used to solve reactor physics problems in both steady state and transient.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations [Phase] Design [Audience] Engineer Grad Ugrad
    - Chapter 0 - Title and Table of Contents 20043601.pdf (175 kb)
    - Chapter 1 - Introduction, by J. Koclas, 20043602.pdf (102 kb)
    - Chapter 2 - Parameter Definitions, by J. Koclas, 20043603.pdf (144 kb)
    - Chapter 3 - Derivation of the Space-Time Kinetics Equations, by J. Koclas, 20043604.pdf (174 kb)
    - Chapter 4 - Energy Condensation, by J. Koclas, 20043605.pdf (137 kb)
    - Chapter 5 - Matrix Form of Equations, by J. Koclas, 20043606.pdf (60 kb)
    - Chapter 6 - Spatial Mesh Considerations, by J. Koclas, 20043607.pdf (592 kb)
    - Chapter 7 - Statics, by J. Koclas, 20043608.pdf (255 kb)
    - Chapter 8 - Numerical Methods in Reactor Statics, by J. Koclas, 20043609.pdf (420 kb)
    - Chapter 9 - KInetics Methods Classification, by J. Koclas, 20043610.pdf (34 kb)
    - Chapter 10 - Point Kinetics, by J. Koclas, 20043611.pdf (233 kb)
    - Chapter 11 - Elementary Numerical Integration Techniques, by J. Koclas, 20043612.pdf (218 kb)
    - Chapter 12 - Adiabatic Method, by J. Koclas, 20043613.pdf (140 kb)
    - Chapter 13 - Quasistatic Method, by J. Koclas, 20043614.pdf (102 kb)
    - Chapter 14 - Modal Synthesis, by J. Koclas, 20043615.pdf (164 kb)
    - Chapter 15 - Mesh Centered Finite Difference, by J. Koclas, 20043616.pdf (409 kb)
    - Chapter 16 - Time Integration of the Space-Time Kinetics Equations, by J. Koclas, 20043617.pdf (178 kb)
    - Chapter 17 - Comparisons of Spatial Approximations, by J. Koclas, 20043618.pdf (300 kb)
    70. 1998-09-22---------Jump to [Top]
  70. 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)
    71. 1999-02-23---------Jump to [Top]
  71. 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)
    72. 1999-03-01---------Jump to [Top]
  72. CANDU Fuel Management Course, by Ben Rouben, AECL, 1999-03-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
    - Cover Page 20031100.pdf (91 kb)
    - Complete Course, by Ben Rouben, 20031101.pdf (286 kb)
    - Basic Characteristics of the CANDU Lattice, by Ben Rouben, 20031111.pdf (186 kb)
    - The CANDU Reactivity Devices, by Ben Rouben, 20031112.pdf (147 kb)
    - Detector Systems, by Ben Rouben, 20031113.pdf (141 kb)
    - Computational Scheme for CANDU Neutronics, by Ben Rouben, 20031114.pdf (182 kb)
    - General Discussion on CANDU Fuel Management, by Ben Rouben, 20031115.pdf (125 kb)
    - Equilibrium-Core Design, by Ben Rouben, 20031116.pdf (217 kb)
    - Ongoing Reactor Operation with Channel Refuellings, by Ben Rouben, 20031117.pdf (252 kb)
    - Effects of 135Xe, by Ben Rouben, 20031118.pdf (151 kb)
    - Summary, by Ben Rouben, 20031119.pdf (61 kb)
    - Basic Characteristics of the CANDU Lattice - Figures, by Ben Rouben, 20031121.pdf (324 kb)
    - The CANDU Reactivity Devices - Figures, by Ben Rouben, 20031122.pdf (404 kb)
    - Detector Systems - Figures, by Ben Rouben, 20031123.pdf (418 kb)
    - Computational Scheme for CANDU Neutronics - Figures, by Ben Rouben, 20031124.pdf (83 kb)
    - General Discussion on CANDU Fuel Management - Figures, by Ben Rouben, 20031125.pdf (78 kb)
    - Equilibrium-Core Design - Figures, by Ben Rouben, 20031126.pdf (309 kb)
    - Ongoing Reactor Operation with Channel Refuellings - Figures, by Ben Rouben, 20031127.pdf (323 kb)
    - Effects of 135Xe - Figures, by Ben Rouben, 20031128.pdf (99 kb)
    73. 1999-06-21---------Jump to [Top]
  73. CANDU Safety - presentations in Shanghai, 1999, by V. Snell, AECL, 1999-06-21. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual [Phase] Design Safety [Audience] Engineer Manager
    - CANDU Nuclear Power Plant Design 19990101.pdf (1646 kb)
    - Risk from Nuclear Power Plants, by V. Snell, 19990102.pdf (84 kb)
    - Nuclear Safety Characteristics, by V. Snell, 19990103.pdf (286 kb)
    - Thermalhydraulic Safety Characteristics of CANDU Reactors, by F.J. Doria, 19990104.pdf (1183 kb)
    - Safety Functions - Shutdown Systems, by V. Snell, 19990105.pdf (517 kb)
    - Heat Removal, by V. Snell, 19990106.pdf (767 kb)
    - Emergency Core Cooling, by V. Snell, 19990107.pdf (1182 kb)
    - Containment, by V. Snell, 19990108.pdf (699 kb)
    - Grouping and Separation, by V. Snell, 19990109.pdf (65 kb)
    - Design and Analysis Process, by F.J. Doria, 19990110.pdf (524 kb)
    - Reactivity Control, by V. Snell, 19990111.pdf (412 kb)
    - Large Loss of Coolant Accident, by F.J. Doria, 19990112.pdf (578 kb)
    - Small Loss of Coolant Accident, by F.J. Doria, 19990113.pdf (651 kb)
    - Loss of Heat Sink, by V. Snell, 19990114.pdf (199 kb)
    - Loss of Forced Circulation, by V. Snell, 19990115.pdf (1517 kb)
    - Large Loss of Coolant Accident with Coincident Loss of Emergency Core Cooling, by F.J. Doria, 19990116.pdf (554 kb)
    - Severe Core Damage Accidents, by V. Snell, 19990117.pdf (478 kb)
    - Safety Research and Development, by V. Snell, 19990118.pdf (1851 kb)
    - Safety Research and Development Programs, by F.J. Doria, 19990119.pdf (903 kb)
    - Safety Analysis Tools, by F.J. Doria, 19990120.pdf (608 kb)
    - Probabilistic Safety Analysis, by V.G. Snell and R. Jaitly, 19990121.pdf (81 kb)
    - Regulation of CANDU, by V. Snell, 19990122.pdf (1223 kb)
    - Regulatory Requirements for Design, by V. Snell, 19990123.pdf (162 kb)
    - Regulatory Requirements for Accident Analysis, by V. Snell, 19990124.pdf (60 kb)
    - CANDU 9 Design Overview, by V. Snell, 19990125.pdf (630 kb)
    - CANDU 9 Safety and Licensability, by V. Snell, 19990126.pdf (580 kb)
    74. 2000-03-29---------Jump to [Top]
  74. RFSP Training Course, by Benoit Arsenault, AECL, 2000-03-29. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
    - Chapter 01 - Course Agenda 20054301.pdf (106 kb)
    - Chapter 02 - General Intro to Methods of Physics Analysis & Physics Computer Codes, by Benoit Arsenault, 20054302.pdf (381 kb)
    - Chapter 03 - The RFSP Direct-Access File, by Benoit Arsenault, 20054303.pdf (274 kb)
    - Chapter 04 - RFSP Model, by Benoit Arsenault, 20054304.pdf (400 kb)
    - Chapter 05 - Time-Average Model, by Benoit Arsenault, 20054305.pdf (322 kb)
    - Chapter 06 - Spatial Kinetics, by Benoit Arsenault, 20054306.pdf (272 kb)
    - Chapter 07 - Powderpufs-V, by Benoit Arsenault, 20054307.pdf (348 kb)
    - Chapter 08 - *Simulate and *Intrep, by Benoit Arsenault, 20054308.pdf (494 kb)
    - Chapter 09 - Flux and Power Mapping in RFSP, by Benoit Arsenault, 20054309.pdf (375 kb)
    - Chapter 10 - RRS Modelling in RFSP, by Benoit Arsenault, 20054310.pdf (275 kb)
    - Chapter 11 - *INSTANTAN, by Benoit Arsenault, 20054311.pdf (127 kb)
    - Chapter 12 - RFSP Code Development, by Benoit Arsenault, 20054312.pdf (336 kb)
    75. 2000-09-13---------Jump to [Top]
  75. Safety Analysis Technology: Evolution, Revolution and the Drive to Re-Establish Margins, by John C Luxat, OPG, 2000-09-13. Doc type: Presentation.
    Summary: A historical perspective of the evolution of safety analysis technology at OPG is presented below. The key elements of the new safety analysis methodology are then described together with its relationship to other components of Canadian nuclear safety technology. This development is placed in context with similar work being conducted in the international Light Water Reactor (LWR) community.
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Performance [Phase] Commissioning Design Operation Safety [Audience] Engineer Technician
    - 20000301.pdf (256 kb)
    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)
    - Emergency Core Cooling System, by Gordon L. Brooks, 20010304.pdf (107 kb)
    - The Origin and Evolution of the Second Shutdown System, by Gordon L. Brooks, 20010305.pdf (101 kb)
    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. 2001-07-20---------Jump to [Top]
  81. Starting Up a CANDU Reactor, by D.A. Meneley, AECL, 2001-07-20. Doc type: Paper.
    Summary: CANDU power reactor designers and operators are fully aware of the need for caution in starting up power reactors. However, the open literature describing these established methods is quite sparse, especially with regard to the unique advantages in operability and safety that arise from the computer-driven Reactor Regulating System (RRS). The following text provides a general outline of one procedure appropriate for start-up of a CANDU 6 reactor.
    Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Reactor Physics [Phase] Operation [Audience] College Engineer Manager Technician Ugrad
    - Abbreviated Step-by Step Procedure 20010401.pdf (94 kb)
    82. 2002-01-01---------Jump to [Top]
  82. 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)
    83. 2002-09-01---------Jump to [Top]
  83. 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)
    84. 2003-04-20---------Jump to [Top]
  84. 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)
    85. 2003-05-10---------Jump to [Top]
  85. Preserving CANDU Technical Knowledge – The CANTEACH Project, by Wm.J. Garland, Yulia Kosarenko, Malcolm Lightfoot, D.A. Meneley, CANTEACH, 2003-05-10. Doc type: Paper.
    Summary:
    Keywords: [Concept] General [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High K-8 Manager Technician Ugrad Vendor
    - 20031401.pdf (245 kb)
  86. Preservation and Dissemination of CANDU® Technical Knowledge (The CANTEACH Project), by Wm.J. Garland, Yulia Kosarenko, Malcolm Lightfoot, D.A. Meneley, CANTEACH, 2003-05-10. Doc type: Paper.
    Summary:
    Keywords: [Concept] General [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High K-8 Manager Technician Ugrad Vendor
    - 20031501.pdf (299 kb)
    87. 2003-06-01---------Jump to [Top]
  87. CANTEACH Flyer, by CANTEACH, CANTEACH, 2003-06-01. Doc type: Presentation.
    Summary:
    Keywords: [Concept] General [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High K-8 Manager Technician Ugrad Vendor
    - 20031601.pdf (156 kb)
    88. 2003-06-24---------Jump to [Top]
  88. 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)
  89. Principes Fondamentaux des Réacteurs CANDU - CANDU Fundamentals, CNSC, 2003-06-24. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Operation [Audience] College Engineer Ugrad
    - Texte Complet 20060300.pdf (7093 kb)
    - Table des Matières, 20060301.pdf (102 kb)
    - Chapitre 1 - Objectifs, 20060302.pdf (105 kb)
    - Chapitre 2 - Structure de l’Atome, 20060303.pdf (156 kb)
    - Chapitre 3 - Radioactivité - Phénomènes Nucléaires Spontanés, 20060304.pdf (296 kb)
    - Chapitre 4 - Stabilité et Instabilité Nucléaires, 20060305.pdf (198 kb)
    - Chapitre 5 - Activité et Période, 20060306.pdf (177 kb)
    - Chapitre 6 - Les Neutrons et Leurs Interactions, 20060307.pdf (206 kb)
    - Chapitre 7 - La Fission, 20060308.pdf (382 kb)
    - Chapitre 8 - Combustible, Modérateur et Gestion du Réacteur, 20060309.pdf (156 kb)
    - Chapitre 9 - Sûreté Nucléaire, 20060310.pdf (141 kb)
    - Chapitre 10 - Réacteurs de Puissance, 20060311.pdf (157 kb)
    - Chapitre 11 - Structure d’un Réacteur, 20060312.pdf (820 kb)
    - Chapitre 12 - Modérateur et Circuit du Modérateur, 20060313.pdf (125 kb)
    - Chapitre 13 - Circuits Auxiliaires du Modérateur, 20060314.pdf (250 kb)
    - Chapitre 14 - Circuit Caloporteur (CC), 20060315.pdf (356 kb)
    - Chapitre 15 - Systèmes Auxiliaires du Circuit Caloporteur, 20060316.pdf (321 kb)
    - Chapitre 16 - Le Combustible CANDU, 20060317.pdf (575 kb)
    - Chapitre 17 - Cycle de Vie des Neutrons, 20060318.pdf (126 kb)
    - Chapitre 18 - Criticité et Multiplication de Neutrons, 20060319.pdf (189 kb)
    - Chapitre 19 - Changements dans la Puissance du Réacteur au Fil du Temps, 20060320.pdf (149 kb)
    - Chapitre 20 - Un Produit de Fission Agissant Comme Poison : le Xénon, 20060321.pdf (211 kb)
    - Chapitre 21 - Effets des Changements de Température sur la Réactivité, 20060322.pdf (197 kb)
    - Chapitre 22 - Contrôle du Flux de Neutron, 20060323.pdf (267 kb)
    - Chapitre 23 - Mécanismes de Contrôle de la Réactivité, 20060324.pdf (461 kb)
    - Chapitre 24 - Injection d’Urgence de Caloporteur et Confinement, 20060325.pdf (969 kb)
    - Chapitre 25 - Les Parties Non Nucléaires de la Centrale, 20060326.pdf (1176 kb)
    - Chapitre 26 - Autres Grands Systèmes, 20060327.pdf (752 kb)
    90. 2003-06-30---------Jump to [Top]
  90. 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)
    91. 2003-10-01---------Jump to [Top]
  91. Nuclear Safety & Reliability Course, by D.A. Meneley, University of New Brunswick, 2003-10-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Design Safety [Audience] Grad Ugrad
    - Cover Page 20032200.pdf (89 kb)
    - Week 1, by D.A. Meneley, 20032201.pdf (293 kb)
    - Week 2, by D.A. Meneley, 20032202.pdf (461 kb)
    - Week 3, by D.A. Meneley, 20032203.pdf (378 kb)
    - Week 4, by D.A. Meneley, 20032204.pdf (335 kb)
    - Week 5, by D.A. Meneley, 20032205.pdf (666 kb)
    - Week 6, by D.A. Meneley, 20032206.pdf (636 kb)
    - Week 7, by D.A. Meneley, 20032207.pdf (930 kb)
    - Week 8, by D.A. Meneley, 20032208.pdf (1943 kb)
    - Week 9, by D.A. Meneley, 20032209.pdf (2120 kb)
    - Week 10, by D.A. Meneley, 20032210.pdf (433 kb)
    - Week 11, by D.A. Meneley, 20032211.pdf (476 kb)
    - Week 12, by D.A. Meneley, 20032212.pdf (353 kb)
    92. 2004-04-20---------Jump to [Top]
  92. 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)
    93. 2004-07-17---------Jump to [Top]
  93. CANDU fuel channel 1-D temperature calculation, by Wm.J. Garland, McMaster University, 2004-07-17. Doc type: Other.
    Summary: CANDU fuel channel 1-D temperature calculation spreadsheet.
    Keywords: [Concept] - [SI] 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Modelling [Phase] Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - channel1 (511 kb)
  94. 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)
    95. 2005-07-01---------Jump to [Top]
  95. Nuclear Power Plant Systems and Operation, by G. Bereznai, University of Ontario Institute of Technology, 2005-07-01. Doc type: Reference.
    Summary: Nuclear Power Plant Systems and Operation course covering following: science fundamentals, equipment and systems principles relevant to CANDU reactors; CANDU reactor power plant systems and their operation.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Operation [Audience] College Engineer Ugrad
    - 20071000.pdf (2511 kb)
    96. 2006-03-01---------Jump to [Top]
  96. 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)
    97. 2006-04-01---------Jump to [Top]
  97. 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)
    98. 2009-05-30---------Jump to [Top]
  98. Large LOCA Margins in CANDU Reactors - An Overview of the COG Report, by A.P. Muzumdar and D.A. Meneley, COG, 2009-05-30. Doc type: Paper.
    Summary: This paper discusses the background and conclusions of the 2007 COG report on Large LOCA Safety Margins in CANDU Reactors, and the various initiatives that have resulted from this study since its release. The COG study challenged the notion that positive void reactivity itself is a design weakness, raised as an issue at the Convention on Nuclear Safety, to demonstrate the safety of operating CANDUs worldwide when compared to other certified LWR designs. The paper will briefly describe a new perspective on how the seemingly complex analytical results on reactor safety parameters can be compared on a level playing field, in such a manner that the non-specialist is able to understand. The paper is presented together with a companion paper that focuses on the comparison of reactivity initiated events in CANDU with some other internationally accepted LWR reactor designs.
    Keywords: [Concept] - [SI] 31000 Reactor 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety Safety Analysis [Audience] College Engineer Grad Manager Technician Ugrad Vendor
    - 20090101.pdf (89 kb)
  99. Power Reactor Safety Comparison - A Limited Review, by D.A. Meneley and A.P. Muzumdar, COG, 2009-05-30. Doc type: Paper.
    Summary: A large amount of attention has been paid to avoiding positive coolant void reactivity in LWR reactors. This can be justified due to specific accident events that could lead to severe consequences. Somewhat less attention has been paid to other accident sequences that can lead to positive reactivity addition. Other designs, for example the CANDU-PHWR, exhibit positive coolant void reactivity but include both inherent and engineered systems that compensate for this undesirable characteristic. This paper represents the beginning of a long-term process intended to enable a balanced and fair comparison of the real safety of all reactor types.
    Keywords: [Concept] - [SI] 31000 Reactor 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety Safety Analysis [Audience] College Engineer Grad Manager Technician Ugrad Vendor
    - 20090201.pdf (170 kb)
    100. 2010-09-07---------Jump to [Top]
  100. 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)
    101. 2011-01-01---------Jump to [Top]
  101. 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)
    102. 2012-01-25---------Jump to [Top]
  102. Design and Safety of Canadian Nuclear Reactors, by V. Snell, UNENE, 2012-01-25. Doc type: Presentation.
    Summary:
    Keywords: [Concept] Safety [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety [Audience] Engineer Grad Manager Technician Ugrad
    - 20120101.pdf (11620 kb)
    103. 2015-01-01---------Jump to [Top]
  103. The Essential CANDU, by Wm.J. Garland, Editor-in-Chief, UNENE, 2015-01-01. Doc type: Book.
    Summary: The Essential CANDU is a textbook about nuclear science and engineering pertaining to CANDU reactors using CANDU as the reference design. This distinguishes it from comparable textbooks based on PWR reactors. This is not a product description of CANDU per se. The book emphasizes theory over other aspects of nuclear science. This is a textbook about CANDU nuclear reactor and power plant engineering, not just the reactor physics of the core.
    Keywords: [Concept] General [SI] 30000 Reactor, Steam Generators and Auxiliaries 35000 Fuel Transfer and Storage 36000 Steam Generator Steam and Water Systems 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Chemistry General Engineering Health Physics Nuclear Engineering [Topic] Corrosion Fluid Mechanics Fuel Management Heat Transfer Important Parameters Physical Description Process Systems Radiation Reactor Physics Safety Thermalhydraulics Thermodynamics Waste Handling [Phase] Design Design Analysis Design Description Design Evolution Safety Safety Analysis [Audience] Engineer Grad Ugrad
    - A textbook on the CANDU nuclear power plant technology. press_release-Jan2016.pdf (382 kb)
    104. 2017-02-13---------Jump to [Top]
  104. Xenon and iodine kinetics simulation, by Wm.J. Garland, McMaster University, 2017-02-13. Doc type: Other.
    Summary: Xenon and iodine kinetics simulation using Excel spreadsheet and VBA. Easy to play with and modify.
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual Modelling Reactor Physics [Phase] Concept Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - Xe.xls (91 kb)
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