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[Topic]: Conceptual 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.

500 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. 1972---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  3. 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)
  4. 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)
    5. 1974---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  5. 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)
    6. 1980---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  6. 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)
  7. 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)
    8. 1981---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  8. 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)
    9. 1989---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  9. 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)
    10. 1990---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  10. 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)
  11. 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)
  12. 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)
    13. 1992---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  13. 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)
    14. 1993---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  14. 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)
  15. 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)
    16. 1996---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  16. 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)
  17. 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)
  18. 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)
  19. 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)
  20. 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)
  21. 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)
  22. 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)
  23. 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)
    24. 1997---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  24. 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)
  25. Nuclear Weapons and Nuclear Reactors, by Dan Meneley, OPG, 01/08/1997. Doc type: Report.
    Summary: This report addresses the tenuous link between nuclear power reactor development and the proliferation of nuclear weapons, particularly with respect to possible terrorist exploitation. Arguments are presented which contradict the popular image of nuclear weaponry as a "basement project".
    Keywords: [Concept] - [SI] 03600 Nuclear Safety (Reactor) [Discipline] Nuclear Engineering [Topic] Conceptual Waste Handling [Phase] Operation [Audience] Engineer Manager Vendor
    - Nuclear Studies & Safety Department, Ontario Hydro, Report No. 77157 20032001.pdf (101 kb)
  26. 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)
    27. 1998---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  27. 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)
    28. 1999---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  28. CANDU Safety - presentations in Shanghai, 1999, by V. Snell, AECL, 21/06/1999. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual [Phase] Design Safety [Audience] Engineer Manager
    - CANDU Nuclear Power Plant Design 19990101.pdf (1646 kb)
    - Risk from Nuclear Power Plants 19990102.pdf (84 kb)
    - Nuclear Safety Characteristics 19990103.pdf (286 kb)
    - Thermalhydraulic Safety Characteristics of CANDU Reactors 19990104.pdf (1183 kb)
    - Safety Functions - Shutdown Systems 19990105.pdf (517 kb)
    - Heat Removal 19990106.pdf (767 kb)
    - Emergency Core Cooling 19990107.pdf (1182 kb)
    - Containment 19990108.pdf (699 kb)
    - Grouping and Separation 19990109.pdf (65 kb)
    - Design and Analysis Process 19990110.pdf (524 kb)
    - Reactivity Control 19990111.pdf (412 kb)
    - Large Loss of Coolant Accident 19990112.pdf (578 kb)
    - Small Loss of Coolant Accident 19990113.pdf (651 kb)
    - Loss of Heat Sink 19990114.pdf (199 kb)
    - Loss of Forced Circulation 19990115.pdf (1517 kb)
    - Large Loss of Coolant Accident with Coincident Loss of Emergency Core Cooling 19990116.pdf (554 kb)
    - Severe Core Damage Accidents 19990117.pdf (478 kb)
    - Safety Research and Development 19990118.pdf (1851 kb)
    - Safety Research and Development Programs 19990119.pdf (903 kb)
    - Safety Analysis Tools 19990120.pdf (608 kb)
    - Probabilistic Safety Analysis 19990121.pdf (81 kb)
    - Regulation of CANDU 19990122.pdf (1223 kb)
    - Regulatory Requirements for Design 19990123.pdf (162 kb)
    - Regulatory Requirements for Accident Analysis 19990124.pdf (60 kb)
    - CANDU 9 Design Overview 19990125.pdf (630 kb)
    - CANDU 9 Safety and Licensability 19990126.pdf (580 kb)
    29. 2000---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  29. 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)
    30. 2001---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  30. 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)
    - Emergency Core Cooling System 20010304.pdf (107 kb)
    - The Origin and Evolution of the Second Shutdown System 20010305.pdf (101 kb)
    31. 2002---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  31. 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)
  32. 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)
  33. 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)
  34. 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)
    - Électricité 20070200.pdf (1659 kb)
  35. 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)
  36. 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)
    37. 2003---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  37. 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)
  38. 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)
  39. 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)
  40. 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)
    41. 2005---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  41. 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)
    42. 2010---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  42. 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)
    43. 2011---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  43. 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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