Jump to year -> [1967] [1971] [1974] [1977] [1978] [1980] [1984] [1989] [1990] [1991] [1992] [1993] [1996] [1997] [1998] [1999] [2000] [2001] [2002] [2003] [2004]
[SI]: 31000 Reactor 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.

365 files

    1967---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  1. 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)
    2. 1971---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  2. Fast Reactor Kinetics - The QXI Code, by D.A. Meneley, K.O. Ott and E.S. Wiener, Individual Contributions, 01/03/1971. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Modelling [Phase] Design Analysis Safety Analysis [Audience] Grad Ugrad
    - 20070100.pdf (7793 kb)
    3. 1974---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  3. 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)
    4. 1977---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  4. 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)
    5. 1978---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  5. 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)
  6. 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)
    7. 1980---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  7. Fundamentals of CANDU Reactor Nuclear Design (TDAI-244), by A.A. Pasanen, AECL, 01/01/1980. Doc type: Report.
    Summary: A Lecture Series given at Trieste 22 January - 28 March 1980, TDAI-244 1980 August
    Keywords: [Concept] - [SI] 31000 Reactor 37000 Fuel [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Manager Ugrad
    - Title and Table of Contents 20042000.pdf (176 kb)
    - Chapter 1 - Introduction 20042001.pdf (35 kb)
    - Chapter 2 - Physical Description of the CANDU-600 20042002.pdf (672 kb)
    - Chapter 3 - Methodology for Reactor Physics Analysis In Core Design 20042003.pdf (1922 kb)
    - Chapter 4 - Initial Fuel Loading Determination 20042004.pdf (379 kb)
    - Chapter 5 - Physics Analysis and Tests Related to Commissioning 20042005.pdf (764 kb)
    - Bibliography 20042006.pdf (111 kb)
  8. 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)
    9. 1984---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  9. 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)
    10. 1989---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  10. 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)
    11. 1990---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  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. 1991---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  13. 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)
    14. 1992---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  14. 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)
    15. 1993---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  15. 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)
  16. 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)
  17. 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)
    18. 1996---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  18. Reactor Physics & Fuelling Strategies 1.4, by R. Page, Chulalongkorn University, 01/01/1996. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Reference to Lecture 10 - Canadian Power Reactor Fuel 20042115.pdf (2381 kb)
    - Reference to Lecture 12 - Results of a Survey on Accident and Safety Analysis Codes, Benchmarks. Verification and Validation Methods 20042117.pdf (482 kb)
  19. 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)
  20. 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)
  21. 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)
  22. Reactor Physics & Fuelling Strategies 1.4, by John Brenciaglia, Chulalongkorn University, 01/02/1996. Doc type: Course.
    Summary: Descriptive reactor physics associated with fuel management. Simulation, flux mapping. Reference text used: Fundamentals of CANDU Reactor Nuclear Design (TDAI-244) (AECL)
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Lecture 1 - Reactor Design Philosophies 20042101.pdf (665 kb)
    - Lecture 2 - Use of Reactor Design Codes 20042102.pdf (137 kb)
    - Lecture 3 - Lattice Parameter Calculations 20042103.pdf (531 kb)
    - Lecture 4 - Core Design Analysis 20042104.pdf (332 kb)
    - Lecture 5 - Time Dependence Simulation 20042105.pdf (600 kb)
    - Lecture 6 - Initial Fuel Load 20042106.pdf (253 kb)
    - Lecture 7 - Startup Physics Tests 20042107.pdf (531 kb)
    - Lecture 8 - Power Distribution Control 20042108.pdf (720 kb)
    - Lecture 9 - Safety Analysis Requirements 20042109.pdf (392 kb)
    - Chapter 10 - Fuel Design Analysis 20042110.pdf (187 kb)
    - Lecture 11 - Fueling Strategies and Cycles 20042111.pdf (745 kb)
    - Lecture 12 - Research Reactors Requirements 20042112.pdf (138 kb)
    - Reference to Lecture 8 - In-Core Fuel Management 20042113.pdf (1105 kb)
    - Reference to Lecture 9 - Role of Physics Analysis in Safety and Licensing 20042114.pdf (1389 kb)
    - Reference to Lecture 11 - Fuel Management & Reactor Operation - Review of Operating Experience 20042116.pdf (1501 kb)
  23. 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)
  24. 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)
  25. 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)
    26. 1997---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  26. 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)
  27. Monte Carlo Method for Particle Transport Simulation, Course 1.6, by E. Hussein, Chulalongkorn University, 08/04/1997. Doc type: Course.
    Summary: A brief introduction to the basics of the Monte Carlo method, how the Boltzmann particle transport equation lends itself to solution by the Monte Carlo method, specific aspects of the MCNP code.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Modelling Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Chapter 0 - Table of Contents 20043501.pdf (59 kb)
    - Chapter 1 - Introduction 20043502.pdf (30 kb)
    - Chapter 2 - Monte Carlo Method 20043503.pdf (283 kb)
    - Chapter 3 - Boltzmann Transport Equation 20043504.pdf (79 kb)
    - Chapter 4 - MCNP Input Structure 20043505.pdf (29 kb)
    - Chapter 5 - Geometry in MCNP 20043506.pdf (105 kb)
    - Chapter 6 - MCNP Source Parameters 20043507.pdf (173 kb)
    - Chapter 7 - Physics & Material Cross-Sections 20043508.pdf (67 kb)
    - Chapter 8 - Termination Parameters 20043509.pdf (30 kb)
    - Chapter 9 - Importance Sampling 20043510.pdf (122 kb)
    - Chapter 10 - Tallying 20043511.pdf (163 kb)
    - Chapter 11 - Uncertainty Analysis 20043512.pdf (177 kb)
    - Chapter 12 - Criticality in MCNP 20043513.pdf (42 kb)
    - Workbook, Chapter 1 20043514.pdf (60 kb)
    - Workbook, Chapter 2 20043515.pdf (460 kb)
    - Workbook, Chapter 3 20043516.pdf (103 kb)
    - Workbook, Chapter 4 20043517.pdf (45 kb)
    - Workbook, Chapter 5 20043518.pdf (167 kb)
    - Workbook, Chapter 6 20043519.pdf (270 kb)
    - Workbook, Chapter 7 20043520.pdf (95 kb)
    - Workbook, Chapter 8 20043521.pdf (41 kb)
    - Workbook, Chapter 9 20043522.pdf (195 kb)
    - Workbook, Chapter 10 20043523.pdf (265 kb)
    - Workbook, Chapter 11 20043524.pdf (281 kb)
    - Workbook, Chapter 12 20043525.pdf (68 kb)
  28. Reactor Core Analysis & Fuel Management, Course 1.5, by D. Rozon, Chulalongkorn University, 01/08/1997. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Chapter 5 - SLOWKIN: A Simplified Model for the Stimulation of Transients in a SLOWPOKE-2 Reactor 20043405.pdf (1297 kb)
    - Chapter 1 - Coupled Neutronics-Thermalhydaulics LOCA Analysis 20043401.pdf (970 kb)
    - Chapter 2 - Core Physics Aspects of Safety Analysis 20043402.pdf (1188 kb)
    - Chapter 4 - Fuel Management in CANDU 20043404.pdf (1542 kb)
    - Workbook, Chapter 1 - Neutronics-Thermalhydraulics Overheads 20043406.pdf (330 kb)
    - Workbook, Chapter 2 - Core Physics Overheads 20043407.pdf (567 kb)
    - Chapter 3 - Fuel Management and Advanced Fuel Cycles 20043403.pdf (1436 kb)
    29. 1998---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  29. Neutronic Analysis of Reactors, Course 1.7, by J. Koclas, Chulalongkorn University, 01/02/1998. Doc type: Course.
    Summary: Covers methods used to solve reactor physics problems in both steady state and transient.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations [Phase] Design [Audience] Engineer Grad Ugrad
    - Chapter 0 - Title and Table of Contents 20043601.pdf (175 kb)
    - Chapter 1 - Introduction 20043602.pdf (102 kb)
    - Chapter 2 - Parameter Definitions 20043603.pdf (144 kb)
    - Chapter 3 - Derivation of the Space-Time Kinetics Equations 20043604.pdf (174 kb)
    - Chapter 4 - Energy Condensation 20043605.pdf (137 kb)
    - Chapter 5 - Matrix Form of Equations 20043606.pdf (60 kb)
    - Chapter 6 - Spatial Mesh Considerations 20043607.pdf (592 kb)
    - Chapter 7 - Statics 20043608.pdf (255 kb)
    - Chapter 8 - Numerical Methods in Reactor Statics 20043609.pdf (420 kb)
    - Chapter 9 - KInetics Methods Classification 20043610.pdf (34 kb)
    - Chapter 10 - Point Kinetics 20043611.pdf (233 kb)
    - Chapter 11 - Elementary Numerical Integration Techniques 20043612.pdf (218 kb)
    - Chapter 12 - Adiabatic Method 20043613.pdf (140 kb)
    - Chapter 13 - Quasistatic Method 20043614.pdf (102 kb)
    - Chapter 14 - Modal Synthesis 20043615.pdf (164 kb)
    - Chapter 15 - Mesh Centered Finite Difference 20043616.pdf (409 kb)
    - Chapter 16 - Time Integration of the Space-Time Kinetics Equations 20043617.pdf (178 kb)
    - Chapter 17 - Comparisons of Spatial Approximations 20043618.pdf (300 kb)
    30. 1999---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  30. 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)
    31. 2000---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  31. Safety Analysis Technology: Evolution, Revolution and the Drive to Re-Establish Margins, by John C Luxat, OPG, 13/09/2000. Doc type: Presentation.
    Summary: A historical perspective of the evolution of safety analysis technology at OPG is presented below. The key elements of the new safety analysis methodology are then described together with its relationship to other components of Canadian nuclear safety technology. This development is placed in context with similar work being conducted in the international Light Water Reactor (LWR) community.
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Performance [Phase] Commissioning Design Operation Safety [Audience] Engineer Technician
    - 20000301.pdf (256 kb)
    32. 2001---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  32. 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)
  33. 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)
    - The Origin and Evolution of the Second Shutdown System 20010305.pdf (101 kb)
    34. 2002---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  34. 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)
  35. Testing the Dynamics of Shutdown Systems, by Oszvald Glockler, OPG, 01/05/2002. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Electrical Engineering [Topic] Performance [Phase] Commissioning Operation [Audience] Engineer Technician
    - Instrumentation in Reactor Trip Measurements 20030501.pdf (153 kb)
  36. Reactor Noise Measurements in the Safety and Regulating Systems of CANDU Stations, by Oszvald Glockler, OPG, 01/05/2002. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Electrical Engineering [Topic] Performance [Phase] Commissioning Operation [Audience] Engineer Technician
    - 20030601.pdf (242 kb)
  37. 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)
    38. 2003---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  38. 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)
  39. 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)
  40. Nuclear Safety & Reliability Course, by Dan Meneley, University of New Brunswick, 01/10/2003. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Design Safety [Audience] Grad Ugrad
    - Cover Page 20032200.pdf (89 kb)
    - Week 1 20032201.pdf (293 kb)
    - Week 2 20032202.pdf (461 kb)
    - Week 3 20032203.pdf (378 kb)
    - Week 4 20032204.pdf (335 kb)
    - Week 5 20032205.pdf (666 kb)
    - Week 6 20032206.pdf (636 kb)
    - Week 7 20032207.pdf (930 kb)
    - Week 8 20032208.pdf (1943 kb)
    - Week 9 20032209.pdf (2120 kb)
    - Week 10 20032210.pdf (433 kb)
    - Week 11 20032211.pdf (476 kb)
    - Week 12 20032212.pdf (353 kb)
    41. 2004---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  41. 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)
---end of page---