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[Audience]: Ugrad 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.

1018 files

    1956---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  1. The Pressurized Water Reactor as a Source of Heat for Steam Power Plants, by J.M. Kay and F.J. Hutchinson, IMechE, 01/01/1956. Doc type: Paper.
    Summary:
    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)
    2. 1967---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  2. Nuclear Theory, Course 227, Nuclear Training Centre, OPG, 01/07/1967. 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)
    3. 1968---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  3. Basic Course for Radiation Surveyors and Contamination Monitors of the Radiation and Industrial Safety Branch, by J.H. Fenn and W.R. Bush, AECL, 01/09/1968. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Design Operation [Audience] Engineer Grad Technician Ugrad
    - 20100200.pdf (6970 kb)
    4. 1971---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  4. Fast Reactor Kinetics - The QXI Code, by D.A. Meneley, K.O. Ott and E.S. Wiener, Individual Contributions, 01/03/1971. 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)
    5. 1972---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  5. AECL Lectures on Nuclear Power Symposium, by G.A. Pon, AECL, 25/05/1972. 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 19720102.pdf (1025 kb)
    - Lecture 3 - Power Reactor Types 19720103.pdf (3378 kb)
    - Lecture 4 - Reactor Physics 19720104.pdf (1755 kb)
    - Lecture 5 - Canadian Reactor Fuel 19720105.pdf (3924 kb)
    - Lecture 8 - System Analysis 19720108.pdf (1770 kb)
    - Lecture 9 - Reactor and Station Control 19720109.pdf (2715 kb)
    - Lecture 10 - Plant Layout 19720110.pdf (3190 kb)
    - Lecture 11 - Accident Analysis 19720111.pdf (1418 kb)
    - Lecture 12 - Licensing 19720112.pdf (1755 kb)
    - Lecture 13 - Training 19720113.pdf (1432 kb)
    - Lecture 14 - Canadian Power Reactor Fuel. See AECL 5609 doc#19760101 for an updated version. 19720114.pdf (2844 kb)
    - Lecture 15 - Construction 19720115.pdf (3542 kb)
    - Lecture 16 - Costs 19720116.pdf (764 kb)
    - Lecture 17 - Development Potential 19720117.pdf (1390 kb)
    - Lectures 6 and 7 - Heat Transport and Auxiliary Systems 19720167.pdf (2431 kb)
  6. An Introduction to the CANDU Nuclear Energy Conversion System, by Archie Harms, McMaster University, 25/05/1972. 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 19750102.pdf (493 kb)
    - Chapter 3: Neutron Physics 19750103.pdf (567 kb)
    - Chapter 4: Reactor Statics 19750104.pdf (650 kb)
    - Chapter 5: Reactor Dynamics 19750105.pdf (428 kb)
    - Chapter 6: Control and Operations 19750106.pdf (499 kb)
    - Chapter 7: Thermal-hydraulic Analysis 19750107.pdf (439 kb)
    - Chapter 8: Nuclear Reactor Materials 19750108.pdf (781 kb)
    - Chapter 9: Safety Analysis 19750109.pdf (152 kb)
    - Chapter 10: CANDU Reactors part 1 19750110.pdf (764 kb)
    - Chapter 10: CANDU Reactors part 2 19750111.pdf (686 kb)
    7. 1974---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  7. Nuclear Theory, Course 127, Nuclear Training Centre, OPG, 01/07/1974. 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)
    8. 1976---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  8. Canadian Power Reactor Fuel, by R.D. Page, AECL, 01/03/1976. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 37000 Fuel [Discipline] Materials Engineering Mechanical Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Design Description [Audience] College Engineer Technician Ugrad
    - AECL 5609, updated version of Lecture 14 of the 1974 Nuclear Power Symposium Series, doc#19720114 19760101.pdf (8580 kb)
  9. Turbine, Generator and Auxiliaries, Course 134, Nuclear Training Centre, OPG, 01/09/1976. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Full Course 20051100.pdf (3779 kb)
    - 134.00-00 Index and Objectives 20051101.pdf (355 kb)
    - 134.00-01 Turbine Theory 20051102.pdf (793 kb)
    - 134.00-02 Turbine Operational Performance 20051103.pdf (534 kb)
    - 134.00-03 Turbine Operational Problems 20051104.pdf (554 kb)
    - 134.00-04 Turbine Start-Up 20051105.pdf (365 kb)
    - 134.00-05 Factors Limiting Startup and Rates of Loading 20051106.pdf (561 kb)
    - 134.00-06 Reliability and Testing Requirements 20051107.pdf (253 kb)
    - 134.00-07 Maintenance 20051108.pdf (404 kb)
    10. 1977---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  10. Fluid Mechanics, Nuclear Training Course 223, January 1977, OPG, 01/01/1977. Doc type: Course.
    Summary: Basic fluid mechanics concepts (viscosity, friction, water hammer, pipe flow, lubrication).
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Course Objectives 20040300.pdf (82 kb)
    - Force - Momentum 20040306.pdf (90 kb)
    - Water Hammer 20040307.pdf (226 kb)
    11. 1978---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  11. Fluid Mechanics, Nuclear Training Course 123, April 1978, OPG, 01/04/1978. Doc type: Course.
    Summary: Basic fluid mechanics concepts (viscosity, friction, water hammer, pipe flow, lubrication).  Note: Doc# 20040201 through to 20040205 are identical to OPG 223.00-1, rev January 1977 (see Doc# 20040301 through to 20040305
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Course Objectives 20040200.pdf (87 kb)
    - Parallel Pipe Flow 20040206.pdf (202 kb)
    - Compressible Flow 20040207.pdf (285 kb)
    - Water Hammer 20040208.pdf (265 kb)
    - Hydrodynamic Film Lubrication 20040209.pdf (562 kb)
  12. Fluid Mechanics, Nuclear Training Course 223, January 1977, OPG, 01/04/1978. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Viscosity 20040301.pdf (147 kb)
    - Reynolds' Number 20040302.pdf (105 kb)
    - Friction in Fluid Flow 20040303.pdf (301 kb)
    - Minor Losses 20040304.pdf (213 kb)
    - Pipe Flow Problems 20040305.pdf (132 kb)
    - Appendix 20040308.pdf (489 kb)
    13. 1980---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  13. Fundamentals of CANDU Reactor Nuclear Design (TDAI-244), by A.A. Pasanen, AECL, 01/01/1980. 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 20042001.pdf (35 kb)
    - Chapter 2 - Physical Description of the CANDU-600 20042002.pdf (672 kb)
    - Chapter 3 - Methodology for Reactor Physics Analysis In Core Design 20042003.pdf (1922 kb)
    - Chapter 4 - Initial Fuel Loading Determination 20042004.pdf (379 kb)
    - Chapter 5 - Physics Analysis and Tests Related to Commissioning 20042005.pdf (764 kb)
    - Bibliography 20042006.pdf (111 kb)
  14. Nuclear Theory, Course 227, Nuclear Training Centre 20053700, by J.E. Crist, J. U. Burnham, A. Broughton, D. Winfield, OPG, 01/08/1980. 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 20053701.pdf (443 kb)
    - 227.00-01 Nuclear Structure 20053702.pdf (274 kb)
    - 227.00-02 Neutron Reactions 20053703.pdf (662 kb)
    - 227.00-03 Neutron Cross Sections, Neutron Density and Neutron Flux 20053704.pdf (318 kb)
    - 227.00-04 Thermal Reactors (Basic Design) 20053705.pdf (342 kb)
    - 227.00-05 Neutron Multiplication Factor and Reactivity 20053706.pdf (196 kb)
    - 227.00-06 Neutron Flux Distribution 20053707.pdf (324 kb)
    - 227.00-07 Effect of Fuel Burnup 20053708.pdf (361 kb)
    - 227.00-08 Changes in Reactor Power with Time 20053709.pdf (328 kb)
    - 227.00-09 Source Neuron Effects 20053710.pdf (217 kb)
    - 227.00-10 Power and Power Measurement 20053711.pdf (356 kb)
    - 227.00-11 Fission Product Poisoning 20053712.pdf (866 kb)
    - 227.00-12 Reactivity Effects Due to Temperature Changes 20053713.pdf (454 kb)
    - 227.00-13 Reactivity Control 20053714.pdf (875 kb)
    - 227.00-14 The Approach to Critical 20053715.pdf (148 kb)
    - 227.00-15 Failed Fuel Monitoring 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)
  15. Electrical Systems, Course 135, Nuclear Training Centre, OPG, 01/11/1980. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Full Course 20051300.pdf (1710 kb)
    - 135.00-00 Index and Objectives 20051301.pdf (279 kb)
    - 135.01-01 Introduction to Symmetrical Components and Unbalanced Current 20051302.pdf (185 kb)
    - 135.02-01 Unbalanced Currents: Their Effects 20051303.pdf (252 kb)
    - 135.03-01 Further Examples of Electrical Protective Relays 20051304.pdf (418 kb)
    - 135.04-01 Composite Electrical Protective Schemes: Part 1 20051305.pdf (344 kb)
    - 135.05-01 Composite Electrical Protective Schemes: Part 2 20051306.pdf (257 kb)
    16. 1981---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  16. Heat and Thermodynamics, Course 125, Nuclear Training Centre, OPG, 01/11/1981. Doc type: Course.
    Summary: Basic concepts of heat and thermodynamics: steam tables, Mollier diagrams, turbine, feedheater, condenser, steam generator, reactor.
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Full Course 20050100.pdf (6328 kb)
    - Module B.7 Course Procedures 20050101.pdf (302 kb)
    - Module B.6 Basics 20050102.pdf (339 kb)
    - Module B.5 Steam Tables 20050103.pdf (740 kb)
    - Module B.4.2 Entropy, Throttling and Molier Diagram 20050104.pdf (904 kb)
    - Module B.4.1 Turbine With Reheat 20050105.pdf (684 kb)
    - Module B.3.2 Feedheater Operation 20050106.pdf (569 kb)
    - Module B.3.1 Condenser Performance 20050107.pdf (594 kb)
    - Module B.2 Steam Generator 20050108.pdf (477 kb)
    - Module B.1 Reactor 20050109.pdf (826 kb)
    - B.6 Self Evaluation 20050110.pdf (87 kb)
    - B.5 Self Evaluation 20050111.pdf (69 kb)
    - B.4.2 Self Evaluation 20050112.pdf (118 kb)
    - B.4.1 Self Evaluation 20050113.pdf (103 kb)
    - B.3.2 Self Evaluation 20050114.pdf (121 kb)
    - B.3.1 Self Evaluation 20050115.pdf (118 kb)
    - B.2 Self Evaluation 20050116.pdf (137 kb)
    - B.1 Self Evaluation 20050117.pdf (102 kb)
    - Criterion Tests 20050118.pdf (134 kb)
    17. 1982---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  17. Electrical Equipment, Course 230.2, Nuclear Training Center, OPG, 01/01/1982. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Module 230.00 Introduction and Table of Contents 20050801.pdf (250 kb)
    - Module 230.21-1 Station Batteries and Battery Charges 20050802.pdf (348 kb)
    - Module 230.22-1 Switchgear - Busbars and Cables 20050803.pdf (188 kb)
    - Module 230.22-2 Switchgear - Motor Control Centres 20050804.pdf (217 kb)
    - Module 230.22-3 Switchgear - Air Circuit Breakers 20050805.pdf (203 kb)
    - Module 230.22-4 Switchgear - Vacuum Contactors 20050806.pdf (80 kb)
    - Module 230.22-5 Switchgear - Disconnect Switches, Ground Switches and G.T.D's 20050807.pdf (257 kb)
    - Module 230.22-6 Switchgear - Oil and Air Blast Breakers 20050808.pdf (266 kb)
    - Module 230.22-7 Switchgear - Circuit Breaker Control 20050809.pdf (241 kb)
    - Module 230.23-1 Transformers - Ratings 20050810.pdf (206 kb)
    - Module 230.23-2 Transformers - Operating Procedures 20050811.pdf (246 kb)
    - Module 230.24-1 Electrical Metering - Voltage and Circtuit Transformers 20050812.pdf (200 kb)
    - Module 230.24-2 Electrical Metering - Voltage Couplers and Meters 20050813.pdf (121 kb)
    - Module 230.25-1 Generators - Electrical and Magnetic Effects 20050814.pdf (139 kb)
    - Module 230.25-2 Generators - Equivalent Circuits 20050815.pdf (214 kb)
    - Module 230.25-3 Generators - Excitation Systems 20050816.pdf (204 kb)
    - Module 230.25-4 Generators - Paralleling and Synchronizing 20050817.pdf (176 kb)
    - Module 230.25-5 Generators - Infinite Bus Operation 20050818.pdf (129 kb)
    - Module 230.25-6 Generators - Non-Infinite Bus Operation 20050819.pdf (151 kb)
    - Module 230.25-7 Generators - Overfluxing 20050820.pdf (120 kb)
    - Module 230.25-8 Generators - Loading 20050821.pdf (272 kb)
    - Module 230.25-9 Generators - Operating Limitations 20050822.pdf (168 kb)
    - Module 230.25-10 Generators - Laboratory AC Generator Project 20050823.pdf (181 kb)
  18. Instrumentation and Control, Course 136, OPG, 01/02/1982. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Course Index and Objectives 20042300.pdf (64 kb)
    - 136.00-12 Control Equipment Review 20042301.pdf (229 kb)
    - 136.00-2 Control Theory Review 20042302.pdf (491 kb)
    - 136.00-3 Control Mode Settings 20042303.pdf (224 kb)
    - 136.00-4 Introduction to Frequency Response 20042304.pdf (628 kb)
    - 136.00-5 Direct Digital Control of Processes 20042305.pdf (249 kb)
  19. Chemistry, Course PI 24, OPG, 01/06/1982. Doc type: Course.
    Summary: Heavy water production, water composition and treatment, moderator water and cover gas chemistry, heat transport system aspects, heavy water leakage, environmental monitoring and control, chemical cleaning, chemical analysis.
    Keywords: [Concept] Chemistry and Corrosion [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Chemistry [Topic] Corrosion Heavy Water Purification Radiation [Phase] Design Operation [Audience] College Engineer Ugrad
    - 24.00-0 Course Index and Checkout 20042700.pdf (62 kb)
    - 24.11-1 Isotopic Separation - General 20042701.pdf (58 kb)
    - 24.11-2 Isotopic Separation - Deuterium and Hydrogen 20042702.pdf (71 kb)
    - 24.11-3 Fractional Distillation 20042703.pdf (102 kb)
    - 24.12-0 Heavy Water Production - Enriching 20042704.pdf (24 kb)
    - 24.13-0 Heavy Water Production - Finishing Process 20042705.pdf (23 kb)
    - 24.21-2 Chemical Additives and Blowdown 20042706.pdf (166 kb)
    - 24.21-3 Make-Up Water Treatment Plant 20042707.pdf (227 kb)
    - 24.21-4 Secondary System Materials 20042708.pdf (21 kb)
    - 24.22-1 Moderator Cover Gas System - System Materials 20042709.pdf (22 kb)
    - 24.22-2 Moderator Water Chemistry 20042710.pdf (52 kb)
    - 24.22-3 Moderator Water - Purification 20042711.pdf (37 kb)
    - 24.22-4 Cover Gas - Purity 20042712.pdf (96 kb)
    - 24.23-1 Primary Heat Transport System - Materials 20042713.pdf (18 kb)
    - 24.23-2 Comissioning (chemical conditioning) of the Primary Heat Transport System 20042714.pdf (96 kb)
    - 24.23-3 Primary Heat Transport System Chemical and Impurity Control 20042715.pdf (154 kb)
    - 24.23-4 Transport of Radioactivity in Nuclear Reactors 20042716.pdf (265 kb)
    - 24.41-1 Heavy Water Leakage - Detection 20042717.pdf (92 kb)
    - 24.42-1Heavy Water Leakage - Recovery by Molecular Sieves 20042718.pdf (42 kb)
    - 24.30-1 Radioactive Materials - Management 20042719.pdf (321 kb)
    - 24.51-1 Environmental Monitoring - Radiological Emissions 20042720.pdf (182 kb)
    - 24.51-2 Environmental Monitoring - Radiological Emission Measurement 20042721.pdf (69 kb)
    - 24.52-1 Environmental Monitoring and Control - BHWP 20042722.pdf (36 kb)
    - 24.52-2 Environmental Monitoring and Control - General 20042723.pdf (40 kb)
    - 24.60-1 Chemical Cleaning of Fouled Equipment 20042724.pdf (132 kb)
    - 24.61-1 Chemical Cleaning - NGD experience 20042725.pdf (21 kb)
    - 24.61-1AI Decontamination of Douglas Pt. Reactor by CAN-DECON process 20042726.pdf (313 kb)
    - 24.61-1AII H.E. Fouling and Cleaning Experience in Ontario Hydro's Nuclear Generating Divisions 20042727.pdf (278 kb)
    - 24.61-1AIII Reference #3 20042728.pdf (349 kb)
    - 24.70-0 Chemical Analysis - General 20042729.pdf (190 kb)
    20. 1984---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  20. Heat and Thermodynamics, Course PI 25, Nuclear Training Centre, OPG, 01/03/1984. Doc type: Course.
    Summary: Basic concepts of heat and thermodynamics: expansion and contraction, heat transfer, pressure control, Mollier diagrams, efficiency, the CANDU cycle.
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Full Course 20050200.pdf (3028 kb)
    - 25-0 Introduction and Course Procedures 20050201.pdf (336 kb)
    - 25-1 Basics 20050202.pdf (471 kb)
    - 25-2 Expansion and Contraction 20050203.pdf (351 kb)
    - 25-3 Heat Transfer Calculations 20050204.pdf (183 kb)
    - 25-4 Pressure Control 20050205.pdf (200 kb)
    - 25-5 Mechanisms of Heat Transfer 20050206.pdf (144 kb)
    - 25-6 Mollier Diagrams and The Turbine Process 20050207.pdf (679 kb)
    - 25-7 Efficiency and The CANDU Cycle 20050208.pdf (298 kb)
    - 25-8 Criterion Tests 20050209.pdf (105 kb)
    - 25-9 Self Evaluation Answer Sheet 20050210.pdf (309 kb)
  21. Fluid Mechanics, Nuclear Training Course 223, December 1984, OPG, 01/12/1984. Doc type: Course.
    Summary: These sections provide definitions and sample calculations for basic concepts such as pressure, density, flowrate, etc. and are NOT the same as the corresponding sections in the January 1977 version of 223.
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fuel Management [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Course Objectives 20040400.pdf (29 kb)
    - Fluid Mechanics 20040401.pdf (599 kb)
    - Answer Section 20040402.pdf (407 kb)
    22. 1986---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  22. Safety and Licensing Philosophy and Experience at Ontario Hydro Nuclear Generating Stations, by W. Lee, OPG, 01/01/1986. 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)
    23. 1988---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  23. Heat and Thermodynamics, Course 225, Nuclear Training Centre, OPG, 01/04/1988. Doc type: Course.
    Summary: Basic concepts of heat and thermodynamics: steam tables, Mollier diagrams, turbine with reheat, feedheater, condenser, steam generator, reactor.
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Full Course 20043100.pdf (4667 kb)
    - Index 20043101.pdf (208 kb)
    - Module 1 Basics 20043102.pdf (404 kb)
    - Module 2 Steam Tables 20043103.pdf (636 kb)
    - Module 3 Entropy, Throttling and Mollier Diagrams 20043104.pdf (701 kb)
    - Module 4 Turbine with Reheat 20043105.pdf (611 kb)
    - Module 5 Feedheater Operation 20043106.pdf (511 kb)
    - Module 6 Condenser Performance 20043107.pdf (546 kb)
    - Module 7 Steam Generator 20043108.pdf (382 kb)
    - Module 8 Reactor 20043109.pdf (710 kb)
    24. 1989---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  24. CANDU Advanced Plutonium Burner - The Canadian Response to the ALWR, by A.R. Dastur and A.C. Mao , AECL, 01/05/1989. 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)
    25. 1990---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  25. Mechanical Equipment, Course PI 30.1, Nuclear Training Centre, OPG, 01/01/1990. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03200 Mechanical Engineering [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Operation [Audience] College Engineer Technician Ugrad
    - Full Course 20043200.pdf (5736 kb)
    - PI 30.10-0 Introduction and Objectives 20043201.pdf (392 kb)
    - 430.10-0 Identification and Coding of Mechanical Equipment 20043202.pdf (251 kb)
    - 430.10-1 Centrifugal Pumps 20043203.pdf (379 kb)
    - 330.10-1 Centrifugal Pumps 20043204.pdf (795 kb)
    - 430.10-2 Positive Displacement Pumps 20043205.pdf (168 kb)
    - 430.10-3 Compressonrs - Dynamic and Positive Displacement 20043206.pdf (270 kb)
    - 430.10-4 Air System 20043207.pdf (82 kb)
    - 430.10-5 Fans 20043208.pdf (57 kb)
    - 430.10-6 Vacuum Pumps 20043209.pdf (185 kb)
    - 230.11-1 Compressors 20043210.pdf (226 kb)
    - 330.11-1 Heat Exchangers 20043211.pdf (218 kb)
    - 430.12-1 Piping and Tubes 20043212.pdf (271 kb)
    - 430.13-1 Valves 20043213.pdf (513 kb)
    - 430.14-1 Lubrification 20043214.pdf (143 kb)
    - 430.14-2 Unit 1 Bearings 20043215.pdf (68 kb)
    - 430.14-2 Unit 2 Lubrification Methods 20043216.pdf (62 kb)
    - 430.14-2 Unit 3 Bearing Design and Installation 20043217.pdf (81 kb)
    - 230.12-1 Lubrification 20043218.pdf (250 kb)
    - 430.15-1 Sealing Devices 20043219.pdf (181 kb)
    - 330.14-1 Axial Mechanical Seals 20043220.pdf (190 kb)
    - 230.13-1 Shaft Couplings 20043221.pdf (204 kb)
    - 230.13-2 Belt Drives 20043222.pdf (247 kb)
    - 230.13-3 Chain Drives 20043223.pdf (115 kb)
    - 230.13-4 Gears and Gearing 20043224.pdf (250 kb)
    - 230.16-1 Gas Turbines 20043225.pdf (289 kb)
  26. Nuclear Theory, Course PI 27 , Nuclear Training Centre, OPG, 01/01/1990. 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)
  27. Electrical Equipment, Course PI 30.2, Nuclear Training Center, OPG, 01/01/1990. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Full Course 20050700.pdf (4615 kb)
    - Table of Contents 20050701.pdf (234 kb)
    - PI 26.34-1 Impedance 20050702.pdf (159 kb)
    - PI 26.35-1 Three Phase Systems 20050703.pdf (282 kb)
    - PI 26.35-2 Power and Power Factor 20050704.pdf (190 kb)
    - PI 30.20-1 The CANDU Generating Station 20050705.pdf (150 kb)
    - PI 30.21-1 Conductors 20050706.pdf (379 kb)
    - PI 30.21-2 Insulation 20050707.pdf (221 kb)
    - PI 30.21-3 Fuses 20050708.pdf (323 kb)
    - PI 30.21-4 Disconnect Switches and Circuit Breakers 20050709.pdf (506 kb)
    - PI 30.22-1 Transformers 20050710.pdf (360 kb)
    - PI 30.23-1 AC Generators 20050711.pdf (357 kb)
    - PI 30.23-2 Generator Auxiliary Systems 20050712.pdf (404 kb)
    - PI 30.24-1 Motors 20050713.pdf (327 kb)
    - PI 30.24 Appendix A 20050714.pdf (77 kb)
    - PI 30.25-1 Motor Control 20050715.pdf (361 kb)
    - PI 30.26-1 Batteries 20050716.pdf (361 kb)
  28. Turbine and Auxiliaries, Course PI 34 / TIMS Ref. PI 3004, Nuclear Training Centre, OPG, 01/01/1990. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Full Course 20051000.pdf (11938 kb)
    - PI 34.00-00 Index and Objectives 20051001.pdf (619 kb)
    - 334.00-01 The Steam Turbine 20051002.pdf (676 kb)
    - 234.00-01 Turbine Construction 20051003.pdf (1037 kb)
    - 334.00-03 The Steam System 20051004.pdf (517 kb)
    - 234.00-02 Steam Control to the Turbine 20051005.pdf (514 kb)
    - 334.00-07 The Condenser 20051006.pdf (476 kb)
    - PI 25-06 The Mollier Diagram and the Turbine Processes 20051007.pdf (1214 kb)
    - 334.00-08 Feedwater Heating System -1 20051008.pdf (212 kb)
    - 334.00-09 Feedwater Heating System -2 20051009.pdf (307 kb)
    - 234.00-07 Feedwater Control and Operation 20051010.pdf (586 kb)
    - PI 24.21-01 Secondary Heat Transport System - Impurities 20051011.pdf (230 kb)
    - PI 24.21-02 Chemical Additives and Blowdown 20051012.pdf (274 kb)
    - PI 25-07 Efficiency of the CANDU Turbine Cycle 20051013.pdf (513 kb)
    - 234.00-03 Steam Valve Hydraulic Control 20051014.pdf (255 kb)
    - 234.00-04 Governor Operation 20051015.pdf (516 kb)
    - 234.00-05 Turbine Governors 20051016.pdf (677 kb)
    - 334.00-10 The Lubricating Oil System 20051017.pdf (275 kb)
    - 334.00-11 The Turning Gear 20051018.pdf (113 kb)
    - 234.00-06 Turbine Operational Problems 20051019.pdf (568 kb)
    - 234.00-08 Factors Limiting Startup and Rates of Loading 20051020.pdf (887 kb)
    - 334.00-13 appendix 1 Ontario Hydro Nuclear Turbine Types 20051021.pdf (245 kb)
  29. Nuclear Theory, Course 427, Nuclear Training Centre, OPG, 01/07/1990. 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)
    30. 1992---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  30. Electrical Systems, Course 235, OPG, 01/07/1992. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Module 235.00 Introduction 20042900.pdf (114 kb)
    - Module 235.01 Unit Service Power 20042901.pdf (305 kb)
    - Module 235.02 Ring Bus Configuration 20042902.pdf (103 kb)
    - Module 235.03 Electrical Protection Schemes 20042903.pdf (87 kb)
    - Module 235.04 Application of Electrical Protection Schemes in the Power Station 20042904.pdf (189 kb)
    - Module 235.05 Electric Motor Protection 20042905.pdf (420 kb)
    - Module 235.06 Power Transformer Protection 20042906.pdf (253 kb)
    - Module 235.07 Generator Protection 20042907.pdf (374 kb)
    - Module 235.08 Generator and Transmission Line Stability 20042908.pdf (682 kb)
    - Appendix A Power Transfer Equation 20042909.pdf (48 kb)
  31. Nuclear Theory, Nuclear Training Course 227 20031001, OPG, 01/08/1992. 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)
  32. Chemistry, Nuclear Training Course 224, OPG, 01/10/1992. Doc type: Course.
    Summary: Reviews the chemical technology fundamentals and addresses the chemistry-realated concerns of the condensate, feedwater and boiler system, the moderator system, the heat trnsport system, the liquid zone control system and the irradiated fuel bay.
    Keywords: [Concept] Chemistry and Corrosion [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Chemistry [Topic] Corrosion Heavy Water Purification Radiation [Phase] Design Operation [Audience] College Engineer Ugrad
    - Cover page, Table of contents, Introduction 20040800.pdf (382 kb)
    - A Review of 424 20040801.pdf (753 kb)
    - The Condensate, Feedwater and Boiler System 20040802.pdf (967 kb)
    - The Moderator and Auxiliary Systems 20040803.pdf (1005 kb)
    - The Heat Transport and Auxiliary Systems 20040804.pdf (511 kb)
    - Auxiliary Systems: Liquid Zone Control, Irradiated Fuel Bay 20040805.pdf (447 kb)
    33. 1993---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  33. Fundamentals of Power Reactors, CNSC, 01/01/1993. Doc type: Course.
    Summary: Fundamentals of power reactors covering basic nuclear processes, basic thermodynamics, thermalhydraulics, materials, nuclear systems and radiation protection.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Operation [Audience] College Engineer Ugrad
    - Science & Engineering Fundamentals - Part 1 19930201.pdf (5929 kb)
    - Science & Engineering Fundamentals - Part 2 19930202.pdf (7656 kb)
    - Nuclear Reactor System - Part 1 19930203.pdf (6312 kb)
    - Nuclear Reactor System - Part 2 19930204.pdf (8311 kb)
    - Nuclear Reactor System - Part 3 19930205.pdf (3791 kb)
    - Nuclear Reactor System - Part 4 19930206.pdf (4327 kb)
    - Radiation Protection 19930207.pdf (5465 kb)
  34. Principes de Science et de Fonctionnement des Réacteurs - 20070500, CNSC, 01/01/1993. 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)
  35. Principes de Science et de Fonctionnement des Réacteurs, CNSC, 01/01/1993. 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)
  36. Principes de Science et de Fonctionnement des Réacteurs - Chaleur et Thermodynamique, CNSC, 01/01/1993. Doc type: Course.
    Summary:
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Chaleur et Thermodynamique 20070900.pdf (850 kb)
  37. A Short History of the CANDU Nuclear Power System, by Gordon L. Brooks, AECL, 01/02/1993. Doc type: Paper.
    Summary: This paper provides a short historical summary of the evolution of the CANDU nuclear power system with emphasis on the roles played by Ontario Hydro and private sector companies in Ontario in collaboration with Atomic Energy of Canada Limited (AECL).
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Operation [Audience] College Engineer Manager Ugrad
    - 19930101.pdf (214 kb)
  38. Materials, Nuclear Training Course 228, OPG, 01/06/1993. Doc type: Course.
    Summary: General material properties and the approach to material selection for CANDU reactors. Failure modes of materials, both mechanical and radiation induced. Pressure tube problems.
    Keywords: [Concept] Materials [SI] 31000 Reactor [Discipline] Materials Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Material Properties and Selection: Cover page, Table of contents, Introduction 20040900.pdf (140 kb)
    - Material Properties and Selection: Basic Material Properties and How They Can Be Altered 20040901.pdf (553 kb)
    - Material Properties and Selection: Common Mechanical-Based Failure Modes 20040902.pdf (870 kb)
    - Material Properties and Selection: Selection and Specification of Materials for Nuclear Applications 20040903.pdf (514 kb)
    - Effect of Radiation on Materials: Radiation Damage to Materials 20040904.pdf (547 kb)
    - Effect of Radiation on Materials: Problems with Pressure Tubes 20040905.pdf (612 kb)
    39. 1994---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  39. Turbine and Auxiliaries, Nuclear Training Course 234, OPG, 01/07/1994. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Module 234-00 Introduction to the Course 20042400.pdf (182 kb)
    - Module 234-01 The Steam Turbine 20042401.pdf (760 kb)
    - Module 234-02 The Boiler 20042402.pdf (851 kb)
    - Module 234-03 The Main Steam System 20042403.pdf (1399 kb)
    - Module 234-04 Auxiliary Steam Systems 20042404.pdf (684 kb)
    - Module 234-05 The Condenser and its Auxiliary Systems 20042405.pdf (1091 kb)
    - Module 234-06 The Condensate, the Boiler Feed and Their Auxiliary Systems 20042406.pdf (1736 kb)
    - Module 234-07 The Turbine Governing System 20042407.pdf (724 kb)
    - Module 234-08 The Turbine Supervisory System 20042408.pdf (273 kb)
    - Module 234-09 The Turning Gear 20042409.pdf (305 kb)
    - Module 234-10 The Turbine Lubricating System 20042410.pdf (503 kb)
    - Module 234-11 Startup and Loading 20042411.pdf (1220 kb)
    - Module 234-12 Unloading and Shutdown 20042412.pdf (333 kb)
    - Module 234-13 Special Modes of Operation and Accidents 20042413.pdf (895 kb)
    - Module 234-14 Turbine Operational Problems 20042414.pdf (850 kb)
  40. Mechanical Equipment, Course 23001, OPG, 01/09/1994. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03200 Mechanical Engineering [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Operation [Audience] College Engineer Technician Ugrad
    - Full Course 20042800.pdf (1261 kb)
    - Intro and Table of Contents 20042801.pdf (44 kb)
    - Module 1 Centrifugal Pumps and Systems 20042802.pdf (1034 kb)
    - Module 2 Positive Displacement Compressor Operation 20042803.pdf (194 kb)
    41. 1995---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  41. Canada's Nuclear Achievement: Technical and Economic Perspectives, by T.E. Rummery and J.A. MacPherson, AECL, 01/07/1995. Doc type: Paper.
    Summary: As published in the Canadian Nuclear Society Bulletin Vol. 16, No. 2, 1995 with the kind permission of the CNS: Canada's leading role and eminent accomplishments in nuclear development now span more than half a century. They encompass aspects as diverse as the design and sale of nuclear power reactors and research reactor technology, to the establishment of a corps of scientists, engineers and technologists with the expertise to address a wide scope of important nuclear science issues. To address the many facets of Canada's nuclear activities over the past 50 years would obviously require space far beyond that available in this paper. We have therefore limited this review to highlights we judge to be the most pertinent and interesting from an historical, technical and economic perspective. We also indicate briefly our view of the future of nuclear power in the overall context of energy needs in a world that is becoming more industrial and increasingly environmentally conscious.
    Keywords: [Concept] General [SI] 00000 General Project [Discipline] History [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High Manager Technician Ugrad Vendor
    - 19950101.pdf (873 kb)
    42. 1996---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  42. Reactor Physics & Fuelling Strategies 1.4, by R. Page, Chulalongkorn University, 01/01/1996. 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 20042117.pdf (482 kb)
  43. Nuclear Physics and Reactor Theory 1.1, by Ian Cameron, Chulalongkorn University, 01/02/1996. 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 20041101.pdf (451 kb)
    - Module 2 - Neutron Reactions 20041102.pdf (783 kb)
    - Module 3 - Neutron Cross-Sections, Neutron Density and Neutron Flux 20041103.pdf (488 kb)
    - Module 4 - Thermal Reactors (Basic Design) 20041104.pdf (413 kb)
    - Module 5 - Neutron Multiplication Factor and Reactivity 20041105.pdf (384 kb)
    - Module 6 - Neutron Flux Distribution 20041106.pdf (313 kb)
    - Module 7 - Effects of Fuel Burnup 20041107.pdf (472 kb)
    - Module 8 - Reactor Power Response to Changes in Reactivity 20041108.pdf (574 kb)
    - Module 9 - Source Neutron Effects 20041109.pdf (278 kb)
    - Module 10 - Power and Power Measurement 20041110.pdf (421 kb)
    - Module 11 - Fission Product Poisoning 20041111.pdf (695 kb)
    - Module 12 - Reactivity Effects Due to Temperature Changes and Coolant Voiding 20041112.pdf (678 kb)
    - Module 13 - Reactivity Control 20041113.pdf (678 kb)
    - Module 14 - The Approach To Critical 20041114.pdf (315 kb)
    - Module 15 - Neutron Detectors And Reactor Instrumentation 20041115.pdf (639 kb)
    - Appendix A 20041116.pdf (72 kb)
  44. Nuclear Theory II (Kinetics) 1.2, by John L. Groh, Chulalongkorn University, 01/02/1996. 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 20041202.pdf (218 kb)
    - Supplement to Chapter 10 20041203.pdf (147 kb)
    - Supplement to Chapter 11 20041204.pdf (263 kb)
    - Supplement to Chapter 12 20041205.pdf (96 kb)
    - Supplement to Chapter 13 20041206.pdf (139 kb)
    - Supplement to Chapter 14 20041207.pdf (147 kb)
    - Workbook, Chapter 8 20041208.pdf (449 kb)
    - Workbook, Chapter 9 20041209.pdf (183 kb)
    - Workbook, Chapter 10 20041210.pdf (128 kb)
    - Workbook, Chapter 11 20041211.pdf (403 kb)
    - Workbook, Chapter 12 20041212.pdf (525 kb)
    - Workbook, Chapter 13 20041213.pdf (128 kb)
    - Workbook, Chapter 14 20041214.pdf (301 kb)
  45. Introduction to Nuclear Reactor Kinetics 1.3, by Daniel Rozon, Chulalongkorn University, 01/02/1996. 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 20041801.pdf (1008 kb)
    - Chapter 2 - The Diffusion Equation and the Steady State 20041802.pdf (1840 kb)
    - Chapter 3 - The Point Kinetics Equation 20041803.pdf (1190 kb)
    - Workbook to Chapter 1 - Neutron/Nucleus Interactions and Fission 20041804.pdf (447 kb)
    - Workbook to Chapter 2 - The Diffusion Equation and the Steady State 20041805.pdf (709 kb)
    - Workbook to Chapter 3 - The Point Kinetics Equations 20041806.pdf (385 kb)
    - Workbook to Chapter 4 - Elementary Solutions to the Kinetics Equations 20041807.pdf (398 kb)
    - Workbook to Chapter 5 - Approximate Solutions for Reactivity Ramps 20041808.pdf (276 kb)
  46. Reactor Physics & Fuelling Strategies 1.4, by John Brenciaglia, Chulalongkorn University, 01/02/1996. 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 20042102.pdf (137 kb)
    - Lecture 3 - Lattice Parameter Calculations 20042103.pdf (531 kb)
    - Lecture 4 - Core Design Analysis 20042104.pdf (332 kb)
    - Lecture 5 - Time Dependence Simulation 20042105.pdf (600 kb)
    - Lecture 6 - Initial Fuel Load 20042106.pdf (253 kb)
    - Lecture 7 - Startup Physics Tests 20042107.pdf (531 kb)
    - Lecture 8 - Power Distribution Control 20042108.pdf (720 kb)
    - Lecture 9 - Safety Analysis Requirements 20042109.pdf (392 kb)
    - Chapter 10 - Fuel Design Analysis 20042110.pdf (187 kb)
    - Lecture 11 - Fueling Strategies and Cycles 20042111.pdf (745 kb)
    - Lecture 12 - Research Reactors Requirements 20042112.pdf (138 kb)
    - Reference to Lecture 8 - In-Core Fuel Management 20042113.pdf (1105 kb)
    - Reference to Lecture 9 - Role of Physics Analysis in Safety and Licensing 20042114.pdf (1389 kb)
    - Reference to Lecture 11 - Fuel Management & Reactor Operation - Review of Operating Experience 20042116.pdf (1501 kb)
  47. Reactor Thermalhydraulics Design, Course 2.1, by W.J. Garland, Chulalongkorn University, 01/02/1996. 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 20043702.pdf (74 kb)
    - Chapter 1 - Introduction 20043703.pdf (130 kb)
    - Chapter 2 - Design Requirements and Engineering Considerations 20043704.pdf (1189 kb)
    - Chapter 3 - Heat Transport System Thermalhydrauilics 20043705.pdf (447 kb)
    - Chapter 4 - Thermodynamics 20043706.pdf (309 kb)
    - Chapter 5 - Fuel Coolant Heat Transfer 20043707.pdf (245 kb)
    - Chapter 6 - Control 20043708.pdf (313 kb)
    - Chapter 7 - The Design Process 20043709.pdf (419 kb)
    - Chapter 8 - Process Design and Optimization 20043710.pdf (441 kb)
    - Appendix 1 - Comparison of Bruce A, B, & Darlington 20043711.pdf (223 kb)
  48. Thermal Study of Nuclear Reactors, Course 2.2, by A. Tapucu, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Design Design Analysis [Audience] Engineer Grad Ugrad
    - Title and Table of Contents 20043801.pdf (96 kb)
    - Chapter 1 - Fundamental Concepts 20043802.pdf (234 kb)
    - Chapter 2 - Single Phase Fluid Equations 20043803.pdf (200 kb)
    - Chapter 3 - Principles of Heat Transfer 20043804.pdf (1061 kb)
    - Chapter 4 - Forced Convection Heat Transfer 20043805.pdf (1624 kb)
    - Chapter 7 - Heat Removal from Nuclear Reactors 20043806.pdf (1557 kb)
    - Appendix 1 - Tensors 20043807.pdf (49 kb)
    - Appendix 2 - Stress in a Fluid 20043808.pdf (256 kb)
    - Appendix 3 - A Short Summary of Orthogonal Functions Used in Chapter 4 20043809.pdf (178 kb)
    - Workbook, Chapter 4 20043810.pdf (2301 kb)
    - Workbook, Chapter 7 20043811.pdf (2043 kb)
  49. Reactor Thermalhydraulics Analysis, Course 2.3, by W.J. Garland, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary: Fundamentals of thermalhydraulic analysis (heat transfer and fluid mechanics)of the heat transport system.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Title and Table of Contents 20043901.pdf (144 kb)
  50. Introduction to Nuclear Reactor Engineering, Course 3.1, by J. Koclas, Chulalongkorn University, 01/02/1996. 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 20044102.pdf (1874 kb)
    - Miscellaneous CANDU-Related Viewgraphs 20044103.pdf (1045 kb)
  51. Nuclear Power Plant Control & Simulaion, Course 3.4, by G. Bereznai, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Workbook, Chapter 1 - Modules A & B 20044401.pdf (644 kb)
    - Workbook, Chapter 2 - Modules A to F 20044402.pdf (3512 kb)
    - Workbook, Chapter 3 - Modules A to I 20044403.pdf (4141 kb)
    - Workbook, Chapter 4 - Modules A to D 20044404.pdf (2750 kb)
    - Workbook, Chapter 5 - Modules A to C 20044405.pdf (1554 kb)
  52. Nuclear Reactor Containment, Course 3.5, by J. Daams, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 20000 Buildings and Structures [Discipline] Civil Engineering [Topic] Conceptual Modelling [Phase] Concept Design [Audience] Engineer Grad Ugrad
    - Reference 1 - Requirements for Containment Systems for Nuclear Power Plants - Doc R7 20044501.pdf (2064 kb)
    - Reference 2 - Real Time Simulation of the Containment by A. Hodhod, L. Vindigni, H. Dana 20044502.pdf (1353 kb)
    - Reference 3 - ANSI 3.5 20044503.pdf (591 kb)
    - Reference 4 - Recent Advances in Concrete Containment Vessels in Japan by T.Koroda, T.Ebine, S.Sato, M. Kato 20044504.pdf (1353 kb)
    - Workbook, Chapter 0 - Title, Objectives 20044505.pdf (38 kb)
    - Workbook, Chapter 1 - Modules A to D 20044506.pdf (1317 kb)
    - Workbook, Chapter 2 - Modules A to C 20044507.pdf (1045 kb)
    - Workbook, Chapter 3 - Modules Ato E 20044508.pdf (1723 kb)
    - Workbook, Chapter 4 - Modules A to F 20044509.pdf (1628 kb)
  53. Nuclear Reactor Safety Design, Course 3.7, by W.J. Garland, Chulalongkorn University, 01/02/1996. 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 20044702.pdf (441 kb)
    - Chapter 3 - Safety Criteria 20044703.pdf (396 kb)
    - Chapter 4 - Design Basis Accidents 20044704.pdf (131 kb)
    - Chapter 5 - Probabilistic Risk Assessment 20044705.pdf (154 kb)
    - Chapter 6 - Safety Analysis 20044706.pdf (190 kb)
    - Chapter 7 - Safety Systems 20044707.pdf (365 kb)
    - Chapter 8 - Good Design Principles & Practices 20044708.pdf (211 kb)
    - References 20044709.pdf (91 kb)
    - Appendix 1 - NRX Accident 20044710.pdf (308 kb)
    - Appendix 2 - Subcategory A.1 Events 20044711.pdf (135 kb)
    - Appendix 3 - Applicable Codes & Standards 20044712.pdf (99 kb)
    - Appendix 4 - Organization of Licensing Basis Document 20044713.pdf (64 kb)
    - Appendix 5 - Accident Analysis Matrix 20044714.pdf (97 kb)
    - Appendix 6 - Large LOCA 20044715.pdf (193 kb)
    - Appendix 7 - Failure Data 20044716.pdf (157 kb)
    - Appendix 8 - Accident Analysis Overview by R. Holmes 20044717.pdf (287 kb)
    - Workbook, Chapter 1 - Figures 20044718.pdf (638 kb)
    - Workbook, Chapter 2 - Figures 20044719.pdf (772 kb)
    - Workbook, Chapter 3 - Figures 20044720.pdf (656 kb)
    - Workbook, Chapter 4 - Figures 20044721.pdf (215 kb)
    - Workbook, Chapter 5 - Figures 20044722.pdf (266 kb)
    - Workbook, Chapter 6 - Figures 20044723.pdf (294 kb)
    - Workbook, Chapter 7 - Figures 20044724.pdf (600 kb)
    - Workbook, Chapter 8 - Figures 20044725.pdf (389 kb)
  54. Neutron Activation Analysis, Course 6.2, by L. Zikovsky, Chulalongkorn University, 01/02/1996. 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 20052802.pdf (231 kb)
    - Chapter 02 - General Aspects in Trace Analysis 20052803.pdf (198 kb)
    - Chapter 03 - Neutron Induced Reactions 20052804.pdf (1636 kb)
    - Chapter 04 - Neutron Sources 20052805.pdf (791 kb)
    - Chapter 05 - Growth & Decay of Radioactivity During & After Irradiation 20052806.pdf (735 kb)
    - Chapter 06 - Nuclear Disintegration & Radiation Detection 20052807.pdf (1459 kb)
    - Chapter 07 - Preparation of Samples & Standards 20052808.pdf (1695 kb)
    - Chapter 08 - Activation Analysis with Radiochemical Separations 20052809.pdf (1291 kb)
    - Chapter 09 - Analysis Without Chemical Separation 20052810.pdf (893 kb)
    - Chapter 10 - Systematic Errors in Activation Analysis 20052811.pdf (1410 kb)
    - Chapter 11 - Statistical Interpretation of Results 20052812.pdf (1455 kb)
    - Workbook 01 - Activation Analysis = Elemental & Isotopic Analysis 20052813.pdf (55 kb)
    - Workbook 02 - Structure of Chlorophyll 20052814.pdf (74 kb)
    - Workbook 03 - The Nuclear Reaction & Types of Nuclear Particles Employed 20052815.pdf (175 kb)
    - Workbook 04 - Irradiation Sources 20052816.pdf (238 kb)
    - Workbook 05 - Quantitative Relationships 20052817.pdf (115 kb)
    - Workbook 06 - Nuclear Disintegration & Radiation Detection 20052818.pdf (289 kb)
    - Workbook 07 - Apparatus to Avoid Contamination 20052819.pdf (37 kb)
    - Workbook 08 - Application of HAP to Activation Analysis of Urine 20052820.pdf (52 kb)
    - Workbook 09 - Decay Curve of Chlorine in a Terphenyl Sample 20052821.pdf (188 kb)
    - Workbook 10 - Sources of Errors in NAA 20052822.pdf (224 kb)
    - Workbook 11 - Optimum Counting Time as Function of Counting Rate and Background Rate 20052823.pdf (90 kb)
    - Workbook 12 - Typical analysis schemes for fluids and solids 20052824.pdf (148 kb)
  55. Intermediate Reactors, Boilers and Auxiliaries, CNSC, 01/02/1996. 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)
  56. Corrosion for Engineers, Course 7.3, by D. Lister, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary: Corrosion cost and measurement, eight forms of corrosion.
    Keywords: [Concept] Chemistry and Corrosion [SI] 31000 Reactor [Discipline] Chemistry [Topic] Corrosion [Phase] Concept Operation [Audience] College Engineer Ugrad
    - Workbook 01 - Cost of Corrosion 20053201.pdf (294 kb)
    - Workbook 02 - Corrosion Measurement 20053202.pdf (312 kb)
    - Workbook 03 - Eight Forms of Corrosion 20053203.pdf (249 kb)
    - Workbook 04 - Galvanic Corrosion 20053204.pdf (751 kb)
    - Workbook 05 - Crevice Corrosion 20053205.pdf (587 kb)
    - Workbook 06 - Pittings 20053206.pdf (280 kb)
    - Workbook 07 - Intergranular Corrosion 20053207.pdf (465 kb)
    - Workbook 08 - Selective Leaching 20053208.pdf (462 kb)
    - Workbook 09 - Stress Corrosion 20053209.pdf (497 kb)
    - Workbook 10 - Erosion Corrosion 20053210.pdf (332 kb)
    - Workbook 11 - Hydrogen Effects (pdf 136 kb, 6 pages) 20053211.pdf (125 kb)
    - Workbook 12 - Acoustic Corrosion Thermodynamics 20053212.pdf (538 kb)
    - Workbook 13 - Corrosion Current 20053213.pdf (611 kb)
  57. Digital Instrumentation & Control, Course 7.4, by M. MacBeth, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Chapter 01 - CANDU DCC Features 20053301.pdf (237 kb)
    - Chapter 02 - Digital Control Concepts 20053302.pdf (317 kb)
    - Chapter 03 - Computer I/O Subsystems 20053303.pdf (423 kb)
    - Chapter 04 - Digital Ctrl Program Concepts 20053304.pdf (492 kb)
    - Chapter 05 - PHT P&IC Control Program 20053305.pdf (906 kb)
    - Chapter 06 - Steam Generator Level Control 20053306.pdf (727 kb)
    - Chapter 07 - Computerized Shutdown System 20053307.pdf (250 kb)
    - Chapter 08 - S/W Categorization Methods 20053308.pdf (233 kb)
    - Chapter 09 - General Display Requirements 20053309.pdf (349 kb)
    - Chapter 10 - Human Interface Design (HFE) 20053310.pdf (1014 kb)
    - Chapter 11 - HFE Methods 20053311.pdf (365 kb)
    - Chapter 12 - Work Assignment 20053312.pdf (173 kb)
    - Chapter 13 - Typical Design Guide Features 20053313.pdf (376 kb)
    - Chapter 14 - Typical HFE Eng. Program 20053314.pdf (421 kb)
    - Workbook 01 Module 01 - Introduction to Instrumentation 20053315.pdf (182 kb)
    - Workbook 01 Module 02 - ISA Symbols 20053316.pdf (94 kb)
    - Workbook 01 Module 03 - Pressure Instrumentation 20053317.pdf (122 kb)
    - Workbook 01 Module 04 - Level Instrumentation 20053318.pdf (249 kb)
    - Workbook 01 Module 05 - Flow Instrumentation 20053319.pdf (267 kb)
    - Workbook 01 Module 06 - Temperature Instrumentation 20053320.pdf (235 kb)
    - Workbook 01 Module 07 - Digital Computer Control 20053321.pdf (237 kb)
    - Workbook 01 Module 08 - Control Valves, Accessories 20053322.pdf (931 kb)
    - Workbook 02 Module 01 - Control Concepts 20053323.pdf (588 kb)
    - Workbook 02 Module 02 - Control Equipment 20053324.pdf (414 kb)
    - Workbook 02 Module 03 - Control and Process Considerations 20053325.pdf (371 kb)
    - Workbook 03 Module 01 - Level Control 20053326.pdf (566 kb)
    - Workbook 03 Module 02 - Pressure Control 20053327.pdf (203 kb)
    - Workbook 04 Module 01 - Log and Linear Ranges 20053328.pdf (96 kb)
    - Workbook 04 Module 02 - Log range detectors 20053329.pdf (126 kb)
    - Workbook 04 Module 03 - Linear Range Detectors 20053330.pdf (119 kb)
    - Workbook 05 Module 01 - Zone Level Control 20053331.pdf (216 kb)
    - Workbook 05 Module 02 - Reactor Regulating System 20053332.pdf (228 kb)
    - Workbook 05 Module 03 - Reactor Shutdown Systems 20053333.pdf (625 kb)
    - Workbook 05 Module 04 - Recovery from a Poison Outage 20053334.pdf (79 kb)
    - Workbook 06 Module 01 - Feed and Bleed Pressure Control 20053335.pdf (206 kb)
    - Workbook 06 Module 02 - Pressure Control by Pressurizer 20053336.pdf (111 kb)
    - Workbook 06 Module 03 - Heat Transport Bleed Control 20053337.pdf (245 kb)
    - Workbook 07 Module 01 - Unit Control Concepts 20053338.pdf (173 kb)
    - Workbook 07 Module 02 - Boiler Pressure Control 20053339.pdf (255 kb)
    - Workbook 07 Module 03 - Unit Startup 20053340.pdf (380 kb)
    - Workbook 08 Module 01 - Controller Tuning 20053341.pdf (189 kb)
    - Workbook 09 Module 01 - CANDU 9 Plant Control 20053342.pdf (182 kb)
  58. Welding Technology, Course 7.5, by I. Grant, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary: Appreciation of metal joining techniques: wleding, welding processes, weldment quality, symbols on drawings, nondestructive examination, and codes and standards.
    Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Chapter 01 - Introduction 20053401.pdf (1359 kb)
    - Chapter 02 - Specification – Covered Carbon Steel Electrodes 20053402.pdf (2022 kb)
    - Chapter 03 - Submerged Arc Welding 20053403.pdf (1118 kb)
    - Chapter 04 - Gas Metal Arc Welding 20053404.pdf (949 kb)
    - Chapter 05 - Plasma Welding 20053405.pdf (119 kb)
    - Chapter 06 - Electrical Power Sources 20053406.pdf (551 kb)
    - Chapter 07 - Welding Stainless Steel Tubing 20053407.pdf (473 kb)
    - Chapter 08 - Thermal Efficiency of Arc Welding Processes 20053408.pdf (737 kb)
    - Chapter 09 - Solidification Structures & Properties of Fusion Welds 20053409.pdf (3163 kb)
    - Chapter 10 - Prediction of Welding Distortion 20053410.pdf (618 kb)
    - Chapter 11 - Material & Fabrication Considerations for CANDU Heat Transport Systems 20053411.pdf (1808 kb)
    - Chapter 13 - Fitness for Purpose 20053413.pdf (858 kb)
    - Chapter 14 - Welding Variables Procedure Specs 20053414.pdf (965 kb)
    - Chapter 17 - Calculating Force/Unit Length on Welds 20053417.pdf (773 kb)
    - Chapter 18 - Design for Welding 20053418.pdf (569 kb)
    - Chapter 19 - Design and Construction Methods for Welded Steel Merchant Vessels 20053419.pdf (313 kb)
    - Workbook 01 - Welding Technologyes) 20053420.pdf (240 kb)
    - Workbook 02 - Flux Shielded Welding Processes 20053421.pdf (549 kb)
    - Workbook 03 - Submerged Arc Welding 20053422.pdf (636 kb)
    - Workbook 04 - Gas Metal Arc Welding 20053423.pdf (497 kb)
    - Workbook 05 - Plasma Arc Welding 20053424.pdf (169 kb)
    - Workbook 06 - Welding Power Supplies & Controls 20053425.pdf (262 kb)
    - Workbook 07 - Arc Physics and Weld Pool Behaviour 20053426.pdf (281 kb)
    - Workbook 08 - Heat Flow in Welding 20053427.pdf (262 kb)
    - Workbook 09 - Metallurgical Effects of the Weld Thermal Cycle 20053428.pdf (1172 kb)
    - Workbook 10 - Distortion, Residual Stress & Post-Weld Heat Treatment 20053429.pdf (361 kb)
    - Workbook 11 - Weldability of Structural Steels 20053430.pdf (535 kb)
    - Workbook 12 - Weld Discontinuities 20053431.pdf (923 kb)
    - Workbook 13 - Inspection & Testing 20053432.pdf (327 kb)
    - Workbook 14 - Welding Qualification & Certification 20053433.pdf (480 kb)
    - Workbook 15 - Design for Welding 20053434.pdf (605 kb)
    - Workbook 16 - Weld Symbols on Drawings 20053435.pdf (531 kb)
    - Workbook 17 Static Strength of Welded Joints 20053436.pdf (443 kb)
    - Workbook 18 - Fatigue Failure of Welded Joints 20053437.pdf (557 kb)
    - Workbook 19 - Fracture of Welded Structures 20053438.pdf (539 kb)
  59. Reactor Control & Simulation, Course 3.3, by J. Koclas, Chulalongkorn University, 01/08/1996. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Chapter 0 - Title and Table of Contents 20044301.pdf (67 kb)
    - Chapter 1 - Point Kinetics 20044302.pdf (490 kb)
    - Chapter 2 - General Concepts 20044303.pdf (262 kb)
    - Chapter 3 - Power Measurement & Calibration 20044304.pdf (211 kb)
    - Chapter 4 - Power Error 20044305.pdf (193 kb)
    - Chapter 5 - Liquid Zone Control 20044306.pdf (134 kb)
    - Chapter 6 - Adjuster Rod Control 20044307.pdf (109 kb)
    - Chapter 7 - MCA Control 20044308.pdf (90 kb)
    - Chapter 8 - Shutoff Rods Extraction 20044309.pdf (35 kb)
    - Chapter 9 - Modal Flux Synthesis 20044310.pdf (83 kb)
    - Chapter 10 - Reactor Setback Program 20044311.pdf (66 kb)
    - Chapter 11 - Reactor Stepback 20044312.pdf (62 kb)
    - Chapter 12 - Shutdown Systems: SDS1 and SDS2 20044313.pdf (173 kb)
    - Chapter XX - Supplementary Materials 20044314.pdf (531 kb)
    - Workbook, Chapter 2 - General Concepts 20044315.pdf (331 kb)
    - Workbook, Chapter 3 - Power Measurement & Calibration 20044316.pdf (263 kb)
    - Workbook, Chapter 4 - Power Error 20044317.pdf (254 kb)
    - Workbook, Chapter 5 - Liquid Zone Control 20044318.pdf (159 kb)
    - Workbook, Chapter 6 - Adjuster Rod Control 20044319.pdf (125 kb)
    - Workbook, Chapter 7 - Mechanical Control Absorbers 20044320.pdf (94 kb)
    - Workbook, Chapter 8 - Shutoff Rods Extraction 20044321.pdf (46 kb)
    - Workbook, Chapter 9 - Modal Flux Synthesis 20044322.pdf (103 kb)
    - Workbook, Chapter 10 - Reactor Setback Program 20044323.pdf (85 kb)
    - Workbook, Chapter 11 - Reactor Stepback 20044324.pdf (80 kb)
    - Workbook, Chapter 12 - Shutdown Systems: SDS1 and SDS2 20044325.pdf (209 kb)
  60. CANDU Overiew, Course 3.2, by G. Bereznai, Chulalongkorn University, 01/11/1996. 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 20044202.pdf (973 kb)
    - Chapter 2 - Reactor and Moderator 20044203.pdf (659 kb)
    - Chapter 3 - Reactor Control 20044204.pdf (881 kb)
    - Chapter 4 - Heat Transport 20044205.pdf (755 kb)
    - Chapter 5 - Steam, Turbine and Feedwater 20044206.pdf (666 kb)
    - Chapter 6 - Special Safety Systems 20044207.pdf (1131 kb)
    - Workbook, Chapter 0 - Table of Contents, Course Introduction 20044208.pdf (194 kb)
    - Workbook, Chapter 1 - Modules A to E 20044209.pdf (3559 kb)
    - Workbook, Chapter 2 - Modules A to C 20044210.pdf (688 kb)
    - Workbook, Chapter 3 - Modules A to C 20044211.pdf (2317 kb)
    - Workbook, Chapter 4 - Modules A to D 20044212.pdf (1115 kb)
    - Workbook, Chapter 5 - Modules A & B 20044213.pdf (1110 kb)
    - Workbook, Chapter 6 - Modules A to D 20044214.pdf (464 kb)
  61. Non-Destructive Testing, Course 7.2, by E. Hussein, Chulalongkorn University, 05/12/1996. Doc type: Course.
    Summary: Nondestructive testing including ultrasonics, magnetic flux leakage, eddy current, radiography, acoustic emission, and microwaves.
    Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Chapter 00 - Table of Contents 20053101.pdf (162 kb)
    - Chapter 01 - Introduction 20053102.pdf (220 kb)
    - Chapter 02 - Ultrasonics 20053103.pdf (670 kb)
    - Chapter 03 - Magnetic Flux Leakage 20053104.pdf (301 kb)
    - Chapter 04 - Eddy Current (pdf 340 kb, 20 pages) 20053105.pdf (369 kb)
    - Chapter 05 - Radiography 20053106.pdf (409 kb)
    - Chapter 06 - Acoustic Emission 20053107.pdf (305 kb)
    - Chapter 07 - Microwaves 20053108.pdf (145 kb)
    62. 1997---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  62. Nuclear Theory I (Statics), or Introduction to Nuclear Technology 1.1a, by Robin Chaplin, Chulalongkorn University, 01/01/1997. 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 20041701.pdf (461 kb)
    - Section 1 - Nuclear Physics (Figures) 20041702.pdf (346 kb)
    - Section 2 - Nuclear Interactions 20041703.pdf (727 kb)
    - Section 2 - Nuclear Interactions (Figures) 20041704.pdf (775 kb)
    - Section 3 - Neutron Diffusion 20041705.pdf (255 kb)
    - Section 4 - Reactor Theory 20041706.pdf (534 kb)
    - Section 4 - Reactor Theory (Figures) 20041707.pdf (456 kb)
    - Section 5 - Reactor Kinetics 20041708.pdf (1075 kb)
    - Question Bank 20041709.pdf (1095 kb)
    - Reference Data 20041710.pdf (537 kb)
  63. Monte Carlo Method for Particle Transport Simulation, Course 1.6, by E. Hussein, Chulalongkorn University, 08/04/1997. 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 20043502.pdf (30 kb)
    - Chapter 2 - Monte Carlo Method 20043503.pdf (283 kb)
    - Chapter 3 - Boltzmann Transport Equation 20043504.pdf (79 kb)
    - Chapter 4 - MCNP Input Structure 20043505.pdf (29 kb)
    - Chapter 5 - Geometry in MCNP 20043506.pdf (105 kb)
    - Chapter 6 - MCNP Source Parameters 20043507.pdf (173 kb)
    - Chapter 7 - Physics & Material Cross-Sections 20043508.pdf (67 kb)
    - Chapter 8 - Termination Parameters 20043509.pdf (30 kb)
    - Chapter 9 - Importance Sampling 20043510.pdf (122 kb)
    - Chapter 10 - Tallying 20043511.pdf (163 kb)
    - Chapter 11 - Uncertainty Analysis 20043512.pdf (177 kb)
    - Chapter 12 - Criticality in MCNP 20043513.pdf (42 kb)
    - Workbook, Chapter 1 20043514.pdf (60 kb)
    - Workbook, Chapter 2 20043515.pdf (460 kb)
    - Workbook, Chapter 3 20043516.pdf (103 kb)
    - Workbook, Chapter 4 20043517.pdf (45 kb)
    - Workbook, Chapter 5 20043518.pdf (167 kb)
    - Workbook, Chapter 6 20043519.pdf (270 kb)
    - Workbook, Chapter 7 20043520.pdf (95 kb)
    - Workbook, Chapter 8 20043521.pdf (41 kb)
    - Workbook, Chapter 9 20043522.pdf (195 kb)
    - Workbook, Chapter 10 20043523.pdf (265 kb)
    - Workbook, Chapter 11 20043524.pdf (281 kb)
    - Workbook, Chapter 12 20043525.pdf (68 kb)
  64. Reactor Core Analysis & Fuel Management, Course 1.5, by D. Rozon, Chulalongkorn University, 01/08/1997. 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)
  65. Reactor Mechanical Design, Course 3.6, by R.S. Porter, Chulalongkorn University, 01/10/1997. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Mechanical Engineering [Topic] Conceptual Physical Description [Phase] Concept Design [Audience] Engineer Grad Ugrad
    - Section 0 - Title, Table of Contents 20044601.pdf (99 kb)
    - Section 1 - Overview, Reg. Req’ts, Codes & Standards 20044602.pdf (531 kb)
    - Section 2 - Design Philosophy, Rationale, Key Operating Parameters 20044603.pdf (481 kb)
    - Section 3 - Stress Analysis of Reactor Structures 20044604.pdf (253 kb)
    - Section 4 - Excitation Spectra Etc. 20044605.pdf (374 kb)
    - Section 5 - Design of Fuel Channels 20044606.pdf (622 kb)
    - Section 6 - Design of Reactivity Control Units 20044607.pdf (1181 kb)
    - Section 7 - Design of Fuel Handling System 20044608.pdf (1121 kb)
    - Appendix 1 - Design Loads and Load Cases for CANDU 6 20044609.pdf (174 kb)
    - Appendix 2 - Stresses for Design Cases 20044610.pdf (316 kb)
    - Appendix 3 - Finite Element Analysis 20044611.pdf (96 kb)
    - Appendix 4 - Seismic Behaviour of CANDU 6 20044612.pdf (168 kb)
    - Workbook, Chapter 1 - Figures 20044613.pdf (208 kb)
    - Workbook, Chapter 2 - Figures 20044614.pdf (778 kb)
    - Workbook, Chapter 3 - Figures 20044615.pdf (355 kb)
    - Workbook, Chapter 4 - Figures 20044616.pdf (455 kb)
    - Workbook, Chapter 5 - Figures 20044617.pdf (150 kb)
    - Workbook, Chapter 6 - Figures 20044618.pdf (964 kb)
    - Workbook, Chapter 7 - Figures 20044619.pdf (1006 kb)
  66. Reactor Core Analysis & Fuel Management, Course 1.5, by B. Rouben, Chulalongkorn University, 01/12/1997. 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 20043402.pdf (1188 kb)
    - Chapter 4 - Fuel Management in CANDU 20043404.pdf (1542 kb)
    - Workbook, Chapter 1 - Neutronics-Thermalhydraulics Overheads 20043406.pdf (330 kb)
    - Workbook, Chapter 2 - Core Physics Overheads 20043407.pdf (567 kb)
    - Chapter 3 - Fuel Management and Advanced Fuel Cycles 20043403.pdf (1436 kb)
    67. 1998---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  67. Neutronic Analysis of Reactors, Course 1.7, by J. Koclas, Chulalongkorn University, 01/02/1998. 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 20043602.pdf (102 kb)
    - Chapter 2 - Parameter Definitions 20043603.pdf (144 kb)
    - Chapter 3 - Derivation of the Space-Time Kinetics Equations 20043604.pdf (174 kb)
    - Chapter 4 - Energy Condensation 20043605.pdf (137 kb)
    - Chapter 5 - Matrix Form of Equations 20043606.pdf (60 kb)
    - Chapter 6 - Spatial Mesh Considerations 20043607.pdf (592 kb)
    - Chapter 7 - Statics 20043608.pdf (255 kb)
    - Chapter 8 - Numerical Methods in Reactor Statics 20043609.pdf (420 kb)
    - Chapter 9 - KInetics Methods Classification 20043610.pdf (34 kb)
    - Chapter 10 - Point Kinetics 20043611.pdf (233 kb)
    - Chapter 11 - Elementary Numerical Integration Techniques 20043612.pdf (218 kb)
    - Chapter 12 - Adiabatic Method 20043613.pdf (140 kb)
    - Chapter 13 - Quasistatic Method 20043614.pdf (102 kb)
    - Chapter 14 - Modal Synthesis 20043615.pdf (164 kb)
    - Chapter 15 - Mesh Centered Finite Difference 20043616.pdf (409 kb)
    - Chapter 16 - Time Integration of the Space-Time Kinetics Equations 20043617.pdf (178 kb)
    - Chapter 17 - Comparisons of Spatial Approximations 20043618.pdf (300 kb)
  68. Reactor Thermalhydraulics Analysis, Course 2.3, by W.J. Garland, Chulalongkorn University, 01/02/1998. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Glossary and Foreword 20043902.pdf (152 kb)
    - Chapter 1 - Course Overview 20043903.pdf (140 kb)
    - Chapter 2 - Basic Equations for Thermalhydraulic Systems Analysis 20043904.pdf (561 kb)
    - Chapter 3 - Nodalization 20043905.pdf (303 kb)
    - Chapter 4 - Equation of State 20043906.pdf (338 kb)
    - Chapter 5 - The Rate Form of the Equation of State 20043907.pdf (512 kb)
    - Chapter 6 - Thermalhydraulic Network Simulation 20043908.pdf (343 kb)
    - Chapter 7 - Empirical Correlations 20043909.pdf (532 kb)
    - Chapter 8 - On Design Tools 20043910.pdf (481 kb)
    - Workbook, Chapter 1 20043911.pdf (151 kb)
    - Workbook Chapter, 2 20043912.pdf (767 kb)
    - Workbook Chapter 3 20043913.pdf (466 kb)
    - Workbook Chapter 4 20043914.pdf (604 kb)
    - Workbook Chapter 5 20043915.pdf (847 kb)
    - Workbook Chapter 6 20043916.pdf (614 kb)
    - Workbook Chapter 7 20043917.pdf (719 kb)
    - Workbook Chapter 8 20043918.pdf (903 kb)
    - Workbook Figures 20043919.pdf (509 kb)
  69. Reactor Thermalhydraulics Analysis, Supplementary, Course 2.3a, by W.J. Garland, Chulalongkorn University, 01/02/1998. Doc type: Course.
    Summary: Supplementary info for thermalhydraulic analysis (heat transfer and fluid mechanics)of the heat transport system.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Appendices 1 - 4 1 - Time Derivatives 2 - The Reynolds Transport Theorem 3 - Rearrangement of Independent Variables 4 - Fast Calculation of Light-Water Properties 20044001.pdf (647 kb)
    - Calculation of Water Properties 20044002.pdf (947 kb)
    - THSIM User Manual 20044003.pdf (733 kb)
    - A Pedagogical Look at Fully- and Semi-Implicit Solutions to T-H Eq'ns 20044004.pdf (320 kb)
    - Basic Equations for T-H Systems Analysis 20044005.pdf (590 kb)
    - Miscellaneous Figures and Equations 20044006.pdf (315 kb)
  70. IAEA CANDU Instrumentation & Control Course, by Mike MacBeth, IAEA, 18/09/1998. Doc type: Course.
    Summary: IAEA CANDU Instrumentation & Control Course, by Dr. Mike MacBeth (AECL), September 13 - 18, 1998, SNERDI, Shanghai
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Instrumentation Equipment 20041601.pdf (2847 kb)
    - Electronic Control 20041602.pdf (1680 kb)
    - Controller Tuning 20041603.pdf (510 kb)
    - Computer Input/Output Subsystems 20041604.pdf (484 kb)
    - Control Programs 20041605.pdf (810 kb)
    - Nuclear Instrumentation 20041606.pdf (518 kb)
    - Reactor Control and Protection 20041607.pdf (627 kb)
    - Heat Transport Control Systems 20041608.pdf (1415 kb)
    - Reactor Protection 20041609.pdf (712 kb)
    - Overall Unit Control 20041610.pdf (693 kb)
  71. 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, 22/09/1998. 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 19980102.pdf (2650 kb)
    - Moderator, HTS, Heavy Water 19980103.pdf (2454 kb)
    - Main Steam & T/G Systems 19980104.pdf (2626 kb)
    - Special Safety Systems 19980105.pdf (949 kb)
    - CANDU Reactor Control 19980106.pdf (1038 kb)
    72. 1999---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  72. China Journal of Nuclear Power Engineering, 1999 Vol 20 No. 6, by Xu Jijun and K.R. Hedges, AECL, 01/10/1999. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - Paper 01 - The Development of CANDU 20054401.pdf (2187 kb)
    - Paper 02 - Introduction to the Qinshan Phase III CANDU Nuclear Power Plant 20054402.pdf (3387 kb)
    - Paper 03 - Reactor Core Structure of Qinshan Phase III CANDU Nuclear Power Plant 20054403.pdf (1893 kb)
    - Paper 04 - Moderator, Heat Transport, and Steam Systems of Qinshan Phase III Nuclear Power Plant 20054404.pdf (353 kb)
    - Paper 05 - Fuel Handling System for Qinshan Phase III Nuclear Power Plant 20054405.pdf (649 kb)
    - Paper 06 - Control System of Qinshan Phase III Nuclear Power Plant, by Zhang Jianmin and R.A. Olmstead 20054406.pdf (427 kb)
    - Paper 07 - Main Electric Power and Balance of Plant Systems and Equipment for Qinshan Phase III Nuclear Power Plant 20054407.pdf (2543 kb)
    - Paper 08 - Safety Systems and Safety Analysis of Qinshan Phase III Nuclear Power Plant 20054408.pdf (197 kb)
    - Paper 09 - Design and Performance of Fuel for Qinshan Phase III Nuclear Power Plant 20054409.pdf (168 kb)
    - Paper 10 - Computer-Aided Engineering for Qinshan CANDU Projects 20054410.pdf (366 kb)
    - Paper 11 - Fuel Management of CANDU Reactors 20054411.pdf (252 kb)
    - Paper 12 - Physics Codes and Methods for CANDU Reactors 20054412.pdf (240 kb)
    - Paper 13 - Thermalhydraulic Design Methods and Computer Codes for CANDU Reactors 20054413.pdf (577 kb)
    - Paper 14 - Operational Characteristics and Management of the Qinshan Phase III CANDU Nuclear Power Plant 20054414.pdf (201 kb)
    - Paper 15 - Advanced CANDU Fuel Cycle Vision 20054415.pdf (80 kb)
    - Paper 16 - A Brief Introduction to CANDU9 – A New Generation of Pressurized Heavy Water Reactors 20054416.pdf (189 kb)
    73. 2000---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  73. Radiation Monitoring Notebook, by James T. Voss, Individual Contributions, 01/06/2000. Doc type: Reference.
    Summary: LA-UR-00-2584 James T. (Tom) Voss, NRRPT, CHP June 2000 (Feb. 2001 Update)
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Design Operation [Audience] Engineer Grad Technician Ugrad
    - 20041901.pdf (191 kb)
    74. 2001---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  74. Radiation Protection ("Green Book"), by Jan Burnham, NB Power, 01/06/2001. Doc type: Book.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Design Operation [Audience] Engineer Grad Technician Ugrad
    - Cover Page 20031300.pdf (98 kb)
    - Chapter 1 - Atomic Structure 20031301.pdf (898 kb)
    - Chapter 2 - Radiation Theory 20031302.pdf (1729 kb)
    - Chapter 3 - Radiation Dose 20031303.pdf (2016 kb)
    - Chapter 4 - Biological Effects Of Radiation 20031304.pdf (1341 kb)
    - Chapter 5 - Dose Limits And Risk 20031305.pdf (1929 kb)
    - Chapter 6 - Instruments 20031306.pdf (8721 kb)
    - Chapter 7 - Protection From External Exposures 20031307.pdf (3122 kb)
    - Chapter 8 - Internal Dose 20031308.pdf (1414 kb)
    - Chapter 9 - Contamination Control 20031309.pdf (9704 kb)
    - Chapter 10 - Dose Records 20031310.pdf (1925 kb)
    - Chapter 11 - Waste Management 20031311.pdf (4460 kb)
    - Chapter 12 - Work Planning 20031312.pdf (2171 kb)
    - Chapter 13 - Emergency Planning 20031313.pdf (2632 kb)
    - Answers to Problems 20031314.pdf (1093 kb)
    - Index 20031315.pdf (1210 kb)
  75. Starting Up a CANDU Reactor, by Dan Meneley, AECL, 20/07/2001. 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)
    76. 2002---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  76. Reactor Physics Course, CNSC, 01/01/2002. 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)
  77. Mechanical Equipment Course, CNSC, 01/01/2002. Doc type: Course.
    Summary:
    Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Cover Page 20030200.pdf (86 kb)
    - 20030201.pdf (1463 kb)
    - Vibrations 20030202.pdf (1123 kb)
    - Valves 20030203.pdf (2952 kb)
    - Flowsheets 20030204.pdf (1693 kb)
  78. Materials Course, CNSC, 01/01/2002. Doc type: Course.
    Summary: This course covers the following areas pertaining to Mechanical Properties: Mechanical and Thermal Stress, Corrosion, Pressure Tubes and Fuel Bundles
    Keywords: [Concept] Materials [SI] - [Discipline] Materials Engineering [Topic] Corrosion Radiation [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Cover Page 20030300.pdf (86 kb)
    - 20030301.pdf (844 kb)
    - Materials & Chemistry 20030302.pdf (687 kb)
    - Corrosion 20030303.pdf (1280 kb)
    - Radiation Effects on Materials 20030304.pdf (1093 kb)
  79. Basic Instrumentation and Control Course, CNSC, 01/01/2002. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Conceptual Function [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Cover Page 20030400.pdf (87 kb)
    - 20030401.pdf (850 kb)
    - Pressure Measurement 20030402.pdf (350 kb)
    - Flow Measurement 20030403.pdf (391 kb)
    - Level Measurement 20030404.pdf (162 kb)
    - Temperature Measurement 20030405.pdf (209 kb)
    - Neutron Flux Measurement 20030406.pdf (282 kb)
    - Control 20030407.pdf (539 kb)
    - I&C Diagrams 20030408.pdf (98 kb)
  80. Electrical Course, CNSC, 01/01/2002. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Cover Page 20030800.pdf (83 kb)
    - Course 20030801.pdf (2299 kb)
    - Electrical Module - Presentation 20030802.pdf (1468 kb)
    - Transformers Module - Presentation 20030803.pdf (664 kb)
    - Generators Module - Presentation 20030804.pdf (2615 kb)
    - Electrical Protection Module - Presentation 20030805.pdf (2756 kb)
  81. Heat and Thermodynamics Course, CNSC, 01/01/2002. Doc type: Course.
    Summary: This module covers the following areas pertaining to thermodynamics: Introduction, Heat and Thermodynamics - The Basics, Reactor and Heat Transport System Normal Operation, Heat Transport System Component Operation
    Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Cover Page 20030900.pdf (83 kb)
    - 20030901.pdf (647 kb)
    - Presentation 20030902.pdf (1557 kb)
  82. Principes de Science et de Fonctionnement des Réacteurs - Électricité, CNSC, 01/01/2002. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Électricité 20070200.pdf (1659 kb)
  83. Principes de Science et de Fonctionnement des Réacteurs - Instrumentation Fondamentale, CNSC, 01/01/2002. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Conceptual Function [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Instrumentation Fondamentale 20070400.pdf (869 kb)
  84. Heavy Water Reactors: Status and Projected Development, Technical Report Series No. 407, IAEA, Vienna, Austria, 2002., IAEA, 01/01/2002. Doc type: .
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - Table of Contents. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp. D407_cont.pdf (54 kb)
    - Part 1. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp. D407_scr1.pdf (4200 kb)
    - Part 2. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp. D407_scr2.pdf (3619 kb)
    - Part 3. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp. D407_scr3.pdf (1384 kb)
    - Cover Page. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp. D407_start.pdf (53 kb)
  85. Introduction to Reactor Physics, by Ben Rouben, AECL, 01/09/2002. 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 20040502.pdf (13610 kb)
  86. ACR Presentation given to the US Nuclear Regulatory Commission on September 25-26, 2002, AECL, 25/09/2002. Doc type: Presentation.
    Summary: Presentation given by AECL to the US Nuclear Regulatory Commission on September 25-26, 2002
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - Introduction. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031201.pdf (1939 kb)
    - An Overview of the ACR Design. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031202.pdf (7935 kb)
    - ACR Technology Base. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031203.pdf (19271 kb)
    - ACR Reactor and Fuel Handling. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031204.pdf (12607 kb)
    - Core Design & Reactor Physics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031205.pdf (957 kb)
    - Reactor Coolant System, Moderator and Major Auxiliary Systems. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031206.pdf (17255 kb)
    - ACR Safety Support Systems Safety Assessment. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031207.pdf (583 kb)
    - ACR Technology Base: Reactor Physics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031208.pdf (1490 kb)
    - ACR Technology Base: Fuel. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031209.pdf (2924 kb)
    - ACR Technology Base: RCS Thermalhydraulics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031210.pdf (3081 kb)
    - ACR Technology Base: Fuel Channels. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031211.pdf (1817 kb)
    - ACR Technology Base: Fuel Channel Thermalhydraulics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031212.pdf (1444 kb)
    - ACR Moderator Circulation. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031213.pdf (2038 kb)
    - ACR Technology Base: Containment. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031214.pdf (792 kb)
    - Qualification Process for Safety Analysis Computer Codes. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031215.pdf (493 kb)
    87. 2003---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  87. Principes de Science et de Fonctionnement des Réacteurs - Les Matériaux, CNSC, 01/01/2003. Doc type: Course.
    Summary:
    Keywords: [Concept] Materials [SI] - [Discipline] Materials Engineering [Topic] Corrosion Radiation [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Les Matériaux 20070600.pdf (420 kb)
  88. Principes de Science et de Fonctionnement des Réacteurs - Équipement Mécanique, CNSC, 01/01/2003. Doc type: Course.
    Summary:
    Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Équipement Mécanique 20070700.pdf (954 kb)
  89. What is RTD, RdF Corporation, 01/02/2003. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - 20030701.pdf (198 kb)
  90. Qinshan CANDU Project Construction Experiences and Lessons Learned to Reduce Capital Costs and Schedule Based on Qinshan CANDU Project in China, by Ken Petrunik, Kang Rixin, AECL, 01/02/2003. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Construction [Audience] College Engineer Ugrad
    - 20031701.pdf (1470 kb)
    - 20031901.pdf (513 kb)
  91. Chemistry Control Requirements for Generic CANDU Power Stations, by Stu Groom, NB Power, 01/05/2003. Doc type: Presentation.
    Summary: A series of presentations by Stu Groom to the Karachi Nuclear Power Plant (KANUPP) in May 2003 as a part of an IAEA 5-day training program to review the chemistry control requirements of the Karachi Nuclear Power Plant.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Construction [Audience] College Engineer Ugrad
    - Basic Chemistry Concepts 20032101.pdf (833 kb)
    - Moderator System Chemistry Control 20032102.pdf (264 kb)
    - Annulus Gas System Chemistry Control 20032103.pdf (362 kb)
    - Primary Heat Transport System Chemistry Control 20032104.pdf (667 kb)
    - Feeder Thinning 20032105.pdf (600 kb)
    - Boiler Feedwater / Condensate Chemistry Control 20032106.pdf (605 kb)
    - Steam Generator Chemistry Control 20032107.pdf (430 kb)
    - ECC and Dousing Systems Chemistry Control 20032108.pdf (116 kb)
    - Spent Fuel Bay Chemistry Control 20032109.pdf (85 kb)
    - Plant Chemistry Controm - PLGS Manual 20032110.pdf (4826 kb)
    - PHT System Chemitry Monitoring and Control Improvements 20032111.pdf (753 kb)
    - Chemistry Laboratory Analytical Procedure – Gadolinium Arsenazo III 20032112.pdf (175 kb)
    - Chemistry Specifications 20032113.pdf (119 kb)
  92. Preserving CANDU Technical Knowledge – The CANTEACH Project, by Bill Garland, Yulia Kosarenko, Malcolm Lightfoot, Dan Meneley, CANTEACH, 10/05/2003. 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)
  93. Preservation and Dissemination of CANDU® Technical Knowledge (The CANTEACH Project), by Bill Garland, Yulia Kosarenko, Malcolm Lightfoot, Dan Meneley, CANTEACH, 10/05/2003. 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)
  94. CANTEACH Flyer, by CANTEACH, CANTEACH, 01/06/2003. 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)
  95. Qinshan Project, by Ken Petrunik, AECL, 01/06/2003. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Construction [Audience] College Engineer Ugrad
    - CNS 2003 Conference Paper 20031801.pdf (3687 kb)
  96. Fluid Mechanics, CNSC, 24/06/2003. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Presentation 20040602.pdf (610 kb)
  97. CANDU Fundamentals, CNSC, 24/06/2003. 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)
  98. Principes Fondamentaux des Réacteurs CANDU - CANDU Fundamentals, CNSC, 24/06/2003. 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)
  99. Nuclear Safety & Reliability Course, by Dan Meneley, University of New Brunswick, 01/10/2003. 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 20032201.pdf (293 kb)
    - Week 2 20032202.pdf (461 kb)
    - Week 3 20032203.pdf (378 kb)
    - Week 4 20032204.pdf (335 kb)
    - Week 5 20032205.pdf (666 kb)
    - Week 6 20032206.pdf (636 kb)
    - Week 7 20032207.pdf (930 kb)
    - Week 8 20032208.pdf (1943 kb)
    - Week 9 20032209.pdf (2120 kb)
    - Week 10 20032210.pdf (433 kb)
    - Week 11 20032211.pdf (476 kb)
    - Week 12 20032212.pdf (353 kb)
    100. 2004---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  100. Fluid Mechanics, CNSC, 01/01/2004. Doc type: Course.
    Summary: Fluid systems are the backbone of nuclear power plants and the CANDU stations are no exception. We will use the term fluid as a generic term for both liquids and gases. The fluid systems are used primarily as heat transport vehicles. An example would be the generator stator cooling system. Heat generated in the stator windings is transferred to the closed-loop stator cooling system and then to the low-pressure service water. This module is designed to help you understand processes that occur in individual fluid handling parts and devices as well as entire systems.
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - 20040601.pdf (353 kb)
    - 20070300.pdf (336 kb)
    101. 2005---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  101. Nuclear Power Plant Systems and Operation, by G. Bereznai, University of Ontario Institute of Technology, 01/07/2005. 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)
    102. 2010---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  102. ACR-1000 Technical Description Summary, AECL, 01/01/2010. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - 20100100.pdf (2399 kb)
  103. 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, 07/09/2010. 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 20110202.pdf (10737 kb)
    - Supplement 1: R&D Activities for HWR Design and Safety Analysis 20110203.pdf (8280 kb)
    - Supplement 2: Alternative Concepts and Early HWR Prototypes 20110204.pdf (8403 kb)
    104. 2011---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  104. Concept Maps, by Bill Garland, CANTEACH, 01/01/2011. 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)
    105. 2012---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  105. Design and Safety of Canadian Nuclear Reactors, by V. Snell, UNENE, 25/01/2012. 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)
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