[Phase]: Concept Documents
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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.
758 files
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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) -
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) -
Nuclear Heated Steam Generators, by D. J. Stelliga and J.M. Dyke, Babcock & Wilcox Canada, 09/03/1970. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- Presented to the Canadian Electrical Association, Toronto, Ontario, March 9-12, 1970 20053900.pdf (928 kb) -
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) -
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) -
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) -
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) -
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) -
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) -
Mathematics, Course 221, OPG, 01/04/1980. Doc type: Course.
Summary: This course proves an introduction to two topics: equipment reliability evaluation, and calculus.
Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept Operation [Audience] Engineer Manager
- Full Course 20043000.pdf (3593 kb)
- 221.00-1 Index and Objectives 20043001.pdf (124 kb)
- 221.00-2 Indroduction 20043002.pdf (132 kb)
- 421.10-4 Standard Notation 20043003.pdf (122 kb)
- 421.20-1 Algebra Fundamentals 20043004.pdf (239 kb)
- 421.40-1 Graphs 20043005.pdf (153 kb)
- 421.40-2 Graphing Functions 20043006.pdf (80 kb)
- 321.10-3 Logarithms and Exponentials 20043007.pdf (210 kb)
- 321.10-4 Use of Logarithmic Scaled Graph Paper 20043008.pdf (347 kb)
- 221.10-1 Basic Reliability Concepts 20043009.pdf (154 kb)
- 221.20-1 The Straight Line 20043010.pdf (166 kb)
- 221.20-2 The Derivative 20043011.pdf (259 kb)
- 221.20-3 Simple Applications of Derivatives 20043012.pdf (127 kb)
- 221.20-4 Differentiating Exponential Functions 20043013.pdf (193 kb)
- 221.20-5 The Derivative in Science and Technology 20043014.pdf (213 kb)
- 221.30-1 The Integral 20043015.pdf (194 kb)
- 221.30-2 Application of the Integral as an Infinite Sum 20043016.pdf (371 kb)
- 221.40-1 Appendix 1 : Review Exercises 20043017.pdf (202 kb)
- 221.40-2 Appendix 2 : Questions Bearing Directly on Course 221 Content from Recent AECB Nuclear General Examinations 20043018.pdf (75 kb)
- 221.40-3 Appendix 3 : Solving Quadratic Equations 20043019.pdf (84 kb)
- 221.40-4 Answers to Assignments and Review Exercises 20043020.pdf (268 kb) -
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) -
Memories of my Life as a Professional Engineer in the Royal Navy and the Canadian Boiler Industry, by J.M. Dyke, Individual Contributions, 01/01/1981. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- Fran Gregory, Ed 20054000.pdf (2139 kb) -
Mathematics, Nuclear Training Course 121, OPG, 01/07/1981. Doc type: Course.
Summary: Probability and reliability concepts applied to station operation.
Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept [Audience] Engineer Manager
- Cover page, Table of contents, Objectives 20040101.pdf (167 kb)
- Introduction 20040102.pdf (194 kb)
- Probability 20040103.pdf (610 kb)
- Safety Systems Analysis 20040104.pdf (404 kb)
- Safety Systems Analysis - Solutions to Sample Problems 20040105.pdf (455 kb)
- The Binomial Distribution and Power System Reliability 20040106.pdf (302 kb)
- The Normal Distribution and Applications 20040107.pdf (193 kb)
- Basic Reliability Concepts 20040108.pdf (638 kb)
- Operation in the Wearout Mode 20040109.pdf (237 kb)
- Some Modern Reliability Topics 20040110.pdf (634 kb)
- Appendix 1: Confidence Limits 20040111.pdf (219 kb)
- Appendix 2: Solutions to Assignments 20040112.pdf (636 kb) -
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) -
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) -
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) -
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) -
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) -
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) -
Reliability for Management and Professional Staff , Course PI 21, Nuclear Training Centre, OPG, 01/01/1990. Doc type: Course.
Summary: A six part introductory reliability course for management and professional staff.
Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept Operation [Audience] Engineer Manager
- Full Course 20043300.pdf (1585 kb)
- Course Table of Contents 20043301.pdf (219 kb)
- PI 21.00 Intro to the Course 20043302.pdf (104 kb)
- PI 21.01 An Introduction to Reliability 20043303.pdf (166 kb)
- PI 21.02 Reliability Concepts 20043304.pdf (384 kb)
- PI 21.03 Process Systems 20043305.pdf (185 kb)
- PI 21.04 Availability of Safety Systems 20043306.pdf (250 kb)
- PI 21.05 Modern Reliability Techniques 20043307.pdf (208 kb)
- PI 21.06 Reporting and Administration 20043308.pdf (111 kb) -
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) -
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) -
Chernobyl – A Canadian Perspective, by V.G. Snell and J.Q. Howieson, AECL, 01/08/1991. Doc type: Report.
Summary: This brochure looks at the Canadian CANDU (CANada Deuterium Uranium) reactor to see how it stacks up in its ability to tolerate the sorts of mistakes that were made at Chernobyl.
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Concept Design Operation Safety [Audience] Engineer Manager Vendor
- 19910101.pdf (398 kb) -
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) -
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) -
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) -
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) -
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) -
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) -
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) -
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) -
Synergistic Nuclear Fuel Cycles of the Future, by D.A. Meneley, A.R. Dastur, P.J. Fehrenbach and K.H. Talbot, AECL, 11/09/1995. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Fuel Management [Phase] Concept Design Operation [Audience] Engineer Manager
- Global 1995, International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France 20054701.pdf (504 kb)
- Global 1995, International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France 20054702.pdf (443 kb) -
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) -
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) -
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) -
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) -
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) -
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) -
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) -
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) -
Natural Analogs for Nuclear Fuel Disposal, Course 5.2, by J. Cramer, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Workbook 00 - Introduction to Natural Analogs 20052101.pdf (102 kb)
- Workbook 01 - Copper Corrosion 20052102.pdf (396 kb)
- Workbook 02 - Clay Sealing 20052103.pdf (249 kb)
- Workbook 03 - Clay Sealing 2 20052104.pdf (268 kb)
- Workbook 04 - Clay Sealing - Avonlea Bentonite 20052105.pdf (230 kb)
- Workbook 05 - Concrete Stability 20052106.pdf (99 kb)
- Workbook 06 - Concrete & Ground Water 20052107.pdf (48 kb)
- Workbook 07 - Radionuclide Migration in Soils 20052108.pdf (228 kb)
- Workbook 08 - Natural Nuclear Reactor 20052109.pdf (479 kb)
- Workbook 09 - Disposal System Analog 20052110.pdf (1381 kb)
- Workbook 10 - Summary 20052111.pdf (50 kb) -
Hydrogeology of Nuclear Fuel Disposal, Course 5.4, by D. Stevenson, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Workbook 01 - Hydrogeology 20052301.pdf (1408 kb)
- Workbook 02 - Structural Geology & Borehole Studies 20052302.pdf (1036 kb)
- Workbook 03 - Groundwater Sampling 20052303.pdf (1231 kb)
- Workbook 04 - Candidate Site Characterization 20052304.pdf (734 kb) -
Environmental Issues in Nuclear Fuel Disposal, Course 5.5, by S. Sheppard, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Workbook 01 - Environmental Issues in Waste Management 20052401.pdf (2604 kb)
- Workbook 02 - Lakes and Rivers 20052402.pdf (1445 kb)
- Workbook 03 - Atmosphere 20052403.pdf (815 kb)
- Workbook 04 - Natural Realm 20052404.pdf (906 kb)
- Workbook 05 - Sensitivity Analysis 20052405.pdf (1734 kb)
- Workbook 06 - Monte Carlo Models 20052406.pdf (1234 kb) -
Nuclear Fuel Disposal Performance Assessment, Course 5.6, by J. Cramer, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Workbook 00 - Performance Assessment Modeling 20052501.pdf (65 kb)
- Workbook 01 - Introduction & System Variability Analysis 20052502.pdf (2055 kb)
- Workbook 02 - I/O and Systems Model Interfaces 20052503.pdf (1567 kb)
- Workbook 03 - Complex & Large System Models 20052504.pdf (412 kb)
- Workbook 04 - Sensitivity Analysis & SYVAC3 Applications 20052505.pdf (592 kb)
- Workbook 05 - Canadian System Model & SYVAC3-CC3 20052506.pdf (880 kb) -
Radiation Processing, Course 6.1, by A. Sigh and H. Singh, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Workbook 01 - Basics, Current & Emerging Applications 20052701.pdf (360 kb)
- Workbook 02 - Potential Concerns Associated with Irradiated Foods 20052702.pdf (598 kb)
- Workbook 03 - Irradiated Foods (cont'd) 20052703.pdf (392 kb)
- Workbook 04 - Sterilization of Medical Products 20052704.pdf (494 kb)
- Workbook 05 - Dosimetry 20052705.pdf (223 kb)
- Workbook 06 - Radiation Polymerization - Coatins & Links 20052706.pdf (111 kb)
- Workbook 07 - Radiation Polymerization - Grafting 20052707.pdf (110 kb)
- Workbook 08 - Radiation Polymerization - Bioengineering 20052708.pdf (188 kb)
- Workbook 09 - Polymerization - Material Composites 20052709.pdf (93 kb)
- Workbook 10 - Radiation Protection 20052710.pdf (100 kb)
- Workbook 11 - Dose Rate Effect in Food Irradiation 20052711.pdf (1661 kb)
- Workbook 12 - Radiation Processing - Basic Aspects 20052712.pdf (691 kb)
- Workbook 13 - Industrial Irradiators 20052713.pdf (628 kb)
- Workbook 14 - The Environment 20052714.pdf (66 kb)
- Workbook 15 - Chemical Wastes - PCBs 20052715.pdf (62 kb)
- Workbook 16 - Radiation Processing of Sewage 20052716.pdf (194 kb)
- Workbook 17 - Radiation Processing of Flue Gases 20052717.pdf (91 kb)
- Workbook 18 - Electron Processing in the Pulping Industry 20052718.pdf (360 kb)
- Workbook 19 - Chemical Effects 20052719.pdf (274 kb)
- Workbook 20 - Manufacturing of Chemicals 20052720.pdf (50 kb)
- Workbook 21 - Food Irradiation - Dose Rate Effect 20052721.pdf (301 kb)
- Workbook 22 - Electron Processing - Composites 20052722.pdf (887 kb)
- Workbook 23 - Dosimetry Procedures in Electron Processing 20052723.pdf (248 kb)
- Workbook 24 - Safety in Industrial Accelerator Facility 20052724.pdf (467 kb)
- Workbook 25 - Effects on Polymeric Systems - Polymerization 20052725.pdf (68 kb)
- Workbook 26 - Effects on Polymeric Systems - Crosslinking and Scission 20052726.pdf (232 kb)
- Workbook 27 - Effects on Polymeric Systems - Polyethylene Crosslinking 20052727.pdf (91 kb)
- Workbook 28 - Effects on Polymeric Systems - Elastomers 20052728.pdf (138 kb)
- Workbook 29 - Spices, Herbs, Other Vegetable Seasonings 20052729.pdf (236 kb)
- Workbook 30 - Successful Applications in Food Irradiation 20052730.pdf (316 kb)
- Workbook 31 - Irradiation of Fresh Fruits 20052731.pdf (273 kb)
- Workbook 32 - Radiation Processing of Advanced Composites 20052732.pdf (670 kb)
- Workbook 33 - Micronutrients 20052733.pdf (210 kb)
- Workbook 34 - Irradiation of Red Meats 20052734.pdf (157 kb) -
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) -
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) -
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) -
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) -
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) -
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) -
Radioactive Waste Management, Course 5.1, by L. Zikovsky, Chulalongkorn University, 01/01/1997. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Chapter 00 - Table of Contents 20052001.pdf (312 kb)
- Chapter 01 - Introduction 20052002.pdf (1537 kb)
- Chapter 02 - Gaseous Waste 20052003.pdf (1137 kb)
- Chapter 03 - Liquid and Wet Waste 20052004.pdf (2459 kb)
- Chapter 04 - Solid Medium & Low Level 20052005.pdf (2018 kb)
- Chapter 05 - Transport 20052006.pdf (542 kb)
- Chapter 06 - Solid High Level Waste 20052007.pdf (846 kb)
- Chapter 07 - Disposal of High Level Waste 20052008.pdf (3282 kb)
- Chapter 08 - Management of Radioactive Waste in Canada 20052009.pdf (2503 kb)
- Workbook 01 - Radioactive Waste Management 20052010.pdf (374 kb)
- Workbook 02 - Gaseous Radwaste 20052011.pdf (378 kb)
- Workbook 03 - Liquid Radwaste 20052012.pdf (642 kb)
- Workbook 04 - Solid LLW 20052013.pdf (720 kb)
- Workbook 05 - Transport 20052014.pdf (193 kb)
- Workbook 06 - Solid HLW 20052015.pdf (350 kb)
- Workbook 07 - Disposal Principles 20052016.pdf (1066 kb)
- Workbook 08 - Canada's Radwaste 20052017.pdf (1015 kb) -
Engineered Barriers for Fuel Disposal, Course 5.3, by L.H. Johnson, Chulalongkorn University, 18/03/1997. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Workbook 01 - Introduction 20052201.pdf (1579 kb)
- Workbook 02 - Detailed Chemistry Considerations 20052202.pdf (700 kb)
- Workbook 03 - Container Failure Predictions 20052203.pdf (924 kb)
- Workbook 04 - Container Design Considerations 20052204.pdf (829 kb)
- Workbook 05 - Seal Materials, Design, & Performance 20052205.pdf (757 kb)
- Workbook 06 - Large Scale In Situ Testing 20052206.pdf (1582 kb)
- Workbook 07 - Vault Model 20052207.pdf (322 kb) -
Steam Generators for CANDU, Engineering Memoirs, by J.M. Dyke, Individual Contributions, 01/06/1997. Doc type: Essay.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- 20054100.pdf (19 kb) -
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) -
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) -
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) -
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) -
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) -
A Reactor Cannot Explode Like a Nuclear Bomb, by Dan Meneley, Individual Contributions, 01/11/2000. Doc type: Lecture.
Summary:
Keywords: [Concept] - [SI] 03600 Nuclear Safety (Reactor) [Discipline] Nuclear Engineering [Topic] Conceptual Performance [Phase] Concept Design Operation Safety [Audience] College Engineer Manager Technician Vendor
- 20000201.pdf (237 kb) -
How and Why is CANDU designed the way it is, by Bill Garland, CANTEACH, 01/12/2000. Doc type: Paper.
Summary: Why we need nuclear power; A look at the nuclear reactor in a nutshell; The engineering approach - CANDUs are engineered systems, typified by functional decomposition; A quick overview of CANDU vs PWR vs BWR and others.
Keywords: [Concept] Overview [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] Concept Design [Audience] High
- 20000101.pdf (819 kb) -
Why a Chernobyl-type accident cannot happen in CANDU reactors, AECL, 03/01/2001. Doc type: Presentation.
Summary:
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Concept Design Operation Safety [Audience] Engineer Manager Vendor
- 20010701.pdf (1026 kb) -
CANDU Origins and Evolution, by Gordon L.Brooks and John S. Foster, AECL, 01/02/2001. Doc type: Paper.
Summary: While the name 'CANDU' was not adopted until the 1960's, the CANDU program can be considered to have started in early 1954. At that time, a team, called the Nuclear Power Group, was established to undertake studies intended to identify a potential Canadian nuclear power system. While the team operated under the auspices of AECL and was located in Building 456 at AECL's Chalk River Laboratory, its membership was drawn from a cross-section of Canadian utility and industrial organizations supported, as required, with "nuclear" expertise provided by AECL staff.
Keywords: [Concept] Overview [SI] 03000 Engineering Science and Technology 31000 Reactor [Discipline] General Engineering Nuclear Engineering [Topic] Conceptual Important Parameters Intro and Overview [Phase] Concept Design Design Evolution [Audience] Manager
- Overview 20010301.pdf (132 kb)
- Why CANDU 20010302.pdf (99 kb)
- Figure of 8 20010303.pdf (111 kb)
- The Origin and Evolution of the Second Shutdown System 20010305.pdf (101 kb) -
Fuel for the Next Millennia, by Dan Meneley, AECL, 06/03/2001. Doc type: Presentation.
Summary:
Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Fuel Management [Phase] Concept Design Operation [Audience] Engineer Manager
- 20010201.pdf (906 kb) -
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) -
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) -
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) -
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) -
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) -
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) -
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) -
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) -
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) -
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) -
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) -
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) -
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) -
Fretting in Nuclear Steam Generators - A New Approach, by J.M. Dyke, Individual Contributions, 20/04/2003. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- 11th International Conference on Nuclear Engineering, Tokyo, Japan 20054500.pdf (2821 kb) -
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) -
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) -
Safer Nuclear Energy for the Future, by Dan Meneley, AECL, 30/06/2003. Doc type: Presentation.
Summary: Series of lectures by Dan Meneley presented at the 28th International Summer College on Physics and Contemporary Needs, June 30 - July 12, 2003, Nathiagali, Pakistan
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual Performance Safety [Phase] Concept Design Safety [Audience] Engineer Manager
- Introduction 20041000.pdf (77 kb)
- Lecture 1 - Safety Perspectives 20041001.pdf (115 kb)
- Lecture 2 - Past Design Evolution 20041002.pdf (103 kb)
- Lecture 3 - Future Design Directions 20041003.pdf (136 kb)
- Lecture 4 - The Long Term 20041004.pdf (205 kb) -
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) -
The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators, by J.M. Dyke, Individual Contributions, 20/04/2004. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- 12th International Conference on Nuclear Engineering, Washington, DC 20054201.pdf (1714 kb)
- 12th International Conference on Nuclear Engineering, Washington, DC 20054202.pdf (1558 kb) -
Fretting Failures in Early Canadian Nuclear Steam Generators, by J.M. Dyke and W.J. Garland, CANTEACH, 01/03/2006. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- 20060201.pdf (140 kb) -
Evolution of CANDU Steam Generators – A Historical View, by J.M. Dyke and W.J. Garland, CANTEACH, 01/04/2006. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- 20060101.pdf (702 kb) -
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) -
Why Ontario Generates So Much Electricity from Nuclear Energy, by Lorne G. McConnell, CNA, 01/03/2010. Doc type: Paper.
Summary: This historical review provides an excellent summary of the context in which CANDU was conceived, designed, built, commissioned and operated. The origins of some of the major characteristic features of CANDU are also given. Note: Figure G3 herein is a corrected version of the original published version which contained a scale error.
Keywords: [Concept] - [SI] 00000 General Project [Discipline] History [Topic] Intro and Overview [Phase] Commissioning Concept Construction Design Operation [Audience] College
- 20100500.pdf (5844 kb) -
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) -
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)
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