[Discipline]: Nuclear Engineering Documents
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Documents below are listed chronologically. Use the links on the left or below to filter documents by keyword. Use the links above to jump to a specific year on this page.
804 files
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The Pressurized Water Reactor as a Source of Heat for Steam Power Plants, by J.M. Kay and F.J. Hutchinson, IMechE, 01/01/1956. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 09000 Special Studies [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Conceptual Heat Transfer Thermodynamics [Phase] Concept Design Operation [Audience] Engineer Ugrad Vendor
- Published in the Proceedings of the Institution of Mechanical Engineers Volume 170 1956 pps 281 - 296 20054600.pdf (2333 kb) -
Reactor, Boiler and Auxiliaries, Course 133, Nuclear Training Center, OPG, 01/11/1966. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
- Full Course 20050900.pdf (10930 kb)
- 133.00-00 Index 20050901.pdf (252 kb)
- 133.10-01 The Function of a Reactor 20050902.pdf (262 kb)
- 133.10-02 Reactor Classification - Fast and Thermal Reactors 20050903.pdf (306 kb)
- 133.10-03 Reactor Classification - Types of Thermal Reactors 20050904.pdf (791 kb)
- 133.10-04 Reactor Construction 20050905.pdf (622 kb)
- 133.20-01 Moderator Requirements 20050906.pdf (227 kb)
- 133.20-02 Moderator Materials Properties and Comparison 20050907.pdf (459 kb)
- 133.20-03 Moderator System and Equipment Considerations 20050908.pdf (930 kb)
- 133.30-01 Heat Transport Fluid Requirements 20050909.pdf (401 kb)
- 133.30-02 Heat Transport Fluid Comparisons 20050910.pdf (600 kb)
- 133.30-03 Main Circuit Considerations 20050911.pdf (845 kb)
- 133.30-04 Auxiliary Circuits 20050912.pdf (708 kb)
- 133.40-01 Reflector Systems 20050913.pdf (367 kb)
- 133.40-02 Shield Cooling Systems 20050914.pdf (318 kb)
- 133.50-01 Functions of Reactivity Mechanisms 20050915.pdf (191 kb)
- 133.50-02 Comparisons of Reactivity Mechanisms 20050916.pdf (711 kb)
- 133.62-01 Upgrading Requirements and Processes 20050917.pdf (170 kb)
- 133.62-02 Principles of Isotope Separation 20050918.pdf (126 kb)
- 133.62-03 The Distillation Upgrading Process 20050919.pdf (258 kb)
- 133.62-04 The Electrolytic Process 20050920.pdf (149 kb)
- 133.62-05 Common Problems 20050921.pdf (183 kb)
- 133.71-01 General Fuel Considerations 20050922.pdf (190 kb)
- 133.71-02 Fuel Preparation and Manufacture 20050923.pdf (233 kb)
- 133.71-03 Canadian Designs and Their Performance 20050924.pdf (294 kb)
- 133.91-01 Safety Standards and Safety Measures 20050925.pdf (198 kb)
- 133.91-02 Emergency Injection and Containment Systems 20050926.pdf (160 kb)
- 133.91-03 Safety System Performance 20050927.pdf (199 kb)
- 133.92-01Chemistry of Water Circuits 20050928.pdf (940 kb) -
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) -
Reactor Boiler and Auxiliaries, Course 433, Nuclear Training Centre, OPG, 01/11/1968. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
- Full Course 20051200.pdf (1786 kb)
- 433.00-00 Index 20051201.pdf (241 kb)
- 433.10-01 Nuclear Power 20051202.pdf (121 kb)
- 433.10-02 Power Reactor Construction 20051203.pdf (179 kb)
- 433.20-01 Moderator Systems 20051204.pdf (141 kb)
- 433.30-01 Heat Transport Systems 20051205.pdf (239 kb)
- 433.40-01 Auxiliary Circuits 20051206.pdf (205 kb)
- 433.50-01 Fuel 20051207.pdf (247 kb)
- 433.50-02 Fuel Handling and Storage 20051208.pdf (172 kb)
- 433.60-01 Boiler Steam and Water Systems 20051209.pdf (291 kb) -
Nuclear Heated Steam Generators, by D. J. Stelliga and J.M. Dyke, Babcock & Wilcox Canada, 09/03/1970. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- Presented to the Canadian Electrical Association, Toronto, Ontario, March 9-12, 1970 20053900.pdf (928 kb) -
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) -
Commissioning and Operating Experience with Canadian Nuclear Electric Stations, by L. W. Woodhead, D. C. Milley, K. E. Elston, E.P. Horton, A. Dahlinger and R.C. Johnston, AECL, 06/09/1971. Doc type: Report.
Summary:
Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Performance [Phase] Commissioning Operation [Audience] Engineer Manager Technician
- Paper No. A/Conf. 49/A/148 presented at the Fourth U.N. International Conference on the Peaceful Uses of Atomic Energy, Geneva, 6-16 September, 1971 19710101.pdf (965 kb) -
AECL Lectures on Nuclear Power Symposium, by G.A. Pon, AECL, 25/05/1972. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems [Phase] Concept Design Design Analysis Safety Safety Analysis [Audience] College Engineer Ugrad
- Lecture 1 - Introduction 19720101.pdf (1091 kb)
- Lecture 2 - Radiation 19720102.pdf (1025 kb)
- Lecture 3 - Power Reactor Types 19720103.pdf (3378 kb)
- Lecture 4 - Reactor Physics 19720104.pdf (1755 kb)
- Lecture 5 - Canadian Reactor Fuel 19720105.pdf (3924 kb)
- Lecture 8 - System Analysis 19720108.pdf (1770 kb)
- Lecture 9 - Reactor and Station Control 19720109.pdf (2715 kb)
- Lecture 10 - Plant Layout 19720110.pdf (3190 kb)
- Lecture 11 - Accident Analysis 19720111.pdf (1418 kb)
- Lecture 12 - Licensing 19720112.pdf (1755 kb)
- Lecture 13 - Training 19720113.pdf (1432 kb)
- Lecture 14 - Canadian Power Reactor Fuel. See AECL 5609 doc#19760101 for an updated version. 19720114.pdf (2844 kb)
- Lecture 15 - Construction 19720115.pdf (3542 kb)
- Lecture 16 - Costs 19720116.pdf (764 kb)
- Lecture 17 - Development Potential 19720117.pdf (1390 kb)
- Lectures 6 and 7 - Heat Transport and Auxiliary Systems 19720167.pdf (2431 kb) -
An Introduction to the CANDU Nuclear Energy Conversion System, by Archie Harms, McMaster University, 25/05/1972. Doc type: Book.
Summary:
Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Nuclear Engineering [Topic] Basic Equations Conceptual Intro and Overview Reactor Physics Thermalhydraulics [Phase] Concept Design Safety [Audience] College Engineer Technician Ugrad
- Table of Contents and Chapter 1: Introduction 19750101.pdf (622 kb)
- Chapter 2: Nuclear Processes 19750102.pdf (493 kb)
- Chapter 3: Neutron Physics 19750103.pdf (567 kb)
- Chapter 4: Reactor Statics 19750104.pdf (650 kb)
- Chapter 5: Reactor Dynamics 19750105.pdf (428 kb)
- Chapter 6: Control and Operations 19750106.pdf (499 kb)
- Chapter 7: Thermal-hydraulic Analysis 19750107.pdf (439 kb)
- Chapter 8: Nuclear Reactor Materials 19750108.pdf (781 kb)
- Chapter 9: Safety Analysis 19750109.pdf (152 kb)
- Chapter 10: CANDU Reactors part 1 19750110.pdf (764 kb)
- Chapter 10: CANDU Reactors part 2 19750111.pdf (686 kb) -
Nuclear Theory, Course 127, Nuclear Training Centre, OPG, 01/07/1974. Doc type: Course.
Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
- Full Course 20050300.pdf (5869 kb)
- 127.00-00 Index and Objectives 20050301.pdf (244 kb)
- 127.10-01 Nuclear Structure 20050302.pdf (571 kb)
- 127.10-02 Neutron Reactions 20050303.pdf (156 kb)
- 127.10-03 Fission 20050304.pdf (264 kb)
- 127.10-04 Neutron Cross Sections and Neutron Flux 20050305.pdf (305 kb)
- 127.10-05 The Chain Reaction 20050306.pdf (240 kb)
- 127.10-06 Moderator Properties 20050307.pdf (296 kb)
- 127.10-05b Neutron Balance and the Four Factor Formula 20050308.pdf (270 kb)
- 127.10-06b Effect of Enrichment, Fuel Arrangement and Fuel Burnup on the Four Factor Formula 20050309.pdf (287 kb)
- 127.10-07 Flux Distribution and Critical Size 20050310.pdf (203 kb)
- 127.10-08 Function and Properties of the Reflector 20050311.pdf (219 kb)
- 127.20-01 Review of Terms 20050312.pdf (201 kb)
- 127.20-02 Low Power Considerations 20050313.pdf (341 kb)
- 127.20-03 Effects Due to Temperature Changes and Void Formation 20050314.pdf (330 kb)
- 127.20-04 Effects Due to Fission Product Accumulation 20050315.pdf (295 kb)
- 127.20-05 Effects Due to Fuel Burnup 20050316.pdf (245 kb)
- 127.20-06 Reactor Control 20050317.pdf (303 kb)
- 127.20-07 The Approach to Critical and the Raising of Power 20050318.pdf (534 kb)
- 127.20-08 Examples of Practical Reactor Behaviour 20050319.pdf (262 kb)
- 127.20-09 Reactor Stability 20050320.pdf (135 kb)
- 127.20-10 Safety Considerations 20050321.pdf (308 kb) -
Reactor, Boilers and Auxiliaries, Nuclear Training Course 133, OPG, 01/04/1977. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
- Cover Page, Table of Contents, Basic Moderator Requirements 20041301.pdf (194 kb)
- Moderator System & Equipment 20041302.pdf (911 kb)
- Basic Heat Transport Fluid Requirements 20041303.pdf (274 kb)
- Main Heat Transport Circuit Considerations 20041304.pdf (1476 kb)
- Auxiliary PHT System Features 20041305.pdf (477 kb)
- Shield Systems 20041306.pdf (446 kb)
- Annulus Gas System 20041307.pdf (97 kb)
- Containment Systems 20041308.pdf (522 kb)
- Reactivity Mechanisms 20041309.pdf (233 kb)
- Practical Reactivity Mechanisms 20041310.pdf (161 kb)
- Choice of Reactivity Mechanisms 20041311.pdf (855 kb)
- Fuel - Design and Manufacturing Features 20041312.pdf (447 kb)
- Fuel Performance and Operating Experience 20041313.pdf (213 kb) -
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) -
Nuclear Theory, Course 227, Nuclear Training Centre 20053700, by J.E. Crist, J. U. Burnham, A. Broughton, D. Winfield, OPG, 01/08/1980. Doc type: Course.
Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
- Full Course 20053700.pdf (8430 kb)
- 227.00-00 Index and Objectives 20053701.pdf (443 kb)
- 227.00-01 Nuclear Structure 20053702.pdf (274 kb)
- 227.00-02 Neutron Reactions 20053703.pdf (662 kb)
- 227.00-03 Neutron Cross Sections, Neutron Density and Neutron Flux 20053704.pdf (318 kb)
- 227.00-04 Thermal Reactors (Basic Design) 20053705.pdf (342 kb)
- 227.00-05 Neutron Multiplication Factor and Reactivity 20053706.pdf (196 kb)
- 227.00-06 Neutron Flux Distribution 20053707.pdf (324 kb)
- 227.00-07 Effect of Fuel Burnup 20053708.pdf (361 kb)
- 227.00-08 Changes in Reactor Power with Time 20053709.pdf (328 kb)
- 227.00-09 Source Neuron Effects 20053710.pdf (217 kb)
- 227.00-10 Power and Power Measurement 20053711.pdf (356 kb)
- 227.00-11 Fission Product Poisoning 20053712.pdf (866 kb)
- 227.00-12 Reactivity Effects Due to Temperature Changes 20053713.pdf (454 kb)
- 227.00-13 Reactivity Control 20053714.pdf (875 kb)
- 227.00-14 The Approach to Critical 20053715.pdf (148 kb)
- 227.00-15 Failed Fuel Monitoring 20053716.pdf (322 kb)
- 227 Appendix A Symbols 20053717.pdf (22 kb)
- 227 Appendix B Properties of Elements and Certain Molecules 20053718.pdf (120 kb)
- 227 Appendix C Nuclides and Isotopes 20053719.pdf (1921 kb) -
Memories of my Life as a Professional Engineer in the Royal Navy and the Canadian Boiler Industry, by J.M. Dyke, Individual Contributions, 01/01/1981. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- Fran Gregory, Ed 20054000.pdf (2139 kb) -
Safety and Licensing Philosophy and Experience at Ontario Hydro Nuclear Generating Stations, by W. Lee, OPG, 01/01/1986. Doc type: Paper.
Summary: As published in the Canadian Nuclear Society Bulletin Vol. 7, No. 1, 1986 with the kind permission of the CNS: The safely and licensing philosophy adopted by Ontario Hydro in establishing the need for retrofit design modifications to CANDU nuclear generating stations in operation since the early 1970's is discussed. This philosophy was developed in response to regulatory requests to determine whether this need exists in view of the more extensive safely and licensing design features incorporated in recent CANDU nuclear generating stations compared to the earlier designs. These addition features generally reflect evolving safety knowledge and licensing requirements over time.
Keywords: [Concept] Safety [SI] 03600 Nuclear Safety (Reactor) 10000 Site and Improvements [Discipline] Nuclear Engineering [Topic] Safety [Phase] Operation Safety [Audience] Engineer Grad Manager Technician Ugrad
- 19860101.pdf (2661 kb) -
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) -
Nuclear Theory, Course PI 27 , Nuclear Training Centre, OPG, 01/01/1990. Doc type: Course.
Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
- Full Course 20050600.pdf (6624 kb)
- PI 27.00-00 Index and Objectives 20050601.pdf (389 kb)
- 427.00-02 Radioactivity - Spontaneous Nuclear Processes 20050602.pdf (282 kb)
- 227.00-01 Nuclear Structure 20050603.pdf (217 kb)
- 227.00-02 Neutron Reactions 20050604.pdf (559 kb)
- 227.00-03 Neutron Cross Sections, Neutron Density and Neutron Flux 20050605.pdf (300 kb)
- 227.00-04 Thermal Reactors (Basic Design) 20050606.pdf (338 kb)
- 227.00-05 Neutron Multiplication Factor and Reactivity 20050607.pdf (193 kb)
- 227.00-06 Neutron Flux Distribution 20050608.pdf (314 kb)
- 227.00-07 Effect of Fuel Burnup 20050609.pdf (467 kb)
- 227.00-08 Changes in Reactor Power with Time 20050610.pdf (357 kb)
- 227.00-09 Source Neutron Effects 20050611.pdf (294 kb)
- 227.00-10 Reactor and Power Measurement 20050612.pdf (509 kb)
- 227.00-11 Fission Product Poisoning 20050613.pdf (999 kb)
- 227.00-12 Reactivity Effects Due to Temperature Changes 20050614.pdf (409 kb)
- 227.00-13 Reactivity Control 20050615.pdf (782 kb)
- 227.00-14 The Approach to Critical 20050616.pdf (295 kb) -
Nuclear Theory, Course 427, Nuclear Training Centre, OPG, 01/07/1990. Doc type: Course.
Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
- Full Course 20050500.pdf (2088 kb)
- 427.00-00 Index and Objectives 20050501.pdf (246 kb)
- 427.00-01 Atomic Structures 20050502.pdf (108 kb)
- 427.00-02 Radioactivity 20050503.pdf (212 kb)
- 427.00-03 Nuclear Stability and Instability 20050504.pdf (150 kb)
- 427.00-04 Activity 20050505.pdf (117 kb)
- 427.00-05 Neutrons and Neutron Interactions 20050506.pdf (107 kb)
- 427.00-06 Fission 20050507.pdf (220 kb)
- 427.00-07 Fuel, Moderator and Reactor Arrangement 20050508.pdf (141 kb)
- 427.00-08 Neutron Life Cycle 20050509.pdf (101 kb)
- 427.00-09 Criticality and Neutron Multiplication 20050510.pdf (183 kb)
- 427.00-10 Changes in Reactor Power with Time 20050511.pdf (149 kb)
- 427.00-11 Xenon : A Fission Product Poison 20050512.pdf (124 kb)
- 427.00-12 Reactivity Effects Due to Temperature Changes 20050513.pdf (133 kb)
- 427.00-13 Neutron Flux Control 20050514.pdf (156 kb) -
Chernobyl – A Canadian Perspective, by V.G. Snell and J.Q. Howieson, AECL, 01/08/1991. Doc type: Report.
Summary: This brochure looks at the Canadian CANDU (CANada Deuterium Uranium) reactor to see how it stacks up in its ability to tolerate the sorts of mistakes that were made at Chernobyl.
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Concept Design Operation Safety [Audience] Engineer Manager Vendor
- 19910101.pdf (398 kb) -
Reactor Boiler and Auxiliaries, Course 233, Nuclear Training, OPG, 01/06/1992. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
- Full Course 20053800.pdf (13185 kb)
- Abstract and Table of Contents 20053801.pdf (162 kb)
- Module 0 - Introduction 20053802.pdf (269 kb)
- Module 1 - Moderator Heavy Water 20053803.pdf (359 kb)
- Module 2 - Moderator Circulation System 20053804.pdf (418 kb)
- Module 3 - Moderator Cover Gas System 20053805.pdf (387 kb)
- Module 4 - The Moderator Liquid Poison System 20053806.pdf (578 kb)
- Module 5 - The Moderator Purification System 20053807.pdf (486 kb)
- Module 6 - HTS Heat Sources and Heat Transfer Paths 20053808.pdf (362 kb)
- Module 7 - HTS Pressure and Inventory Control 20053809.pdf (1482 kb)
- Module 8 - Heat Transport System Shutdown Operation 20053810.pdf (609 kb)
- Module 9 - HTS Heavy Water 20053811.pdf (602 kb)
- Module 10 - Heat Transport System Auxiliaries 20053812.pdf (755 kb)
- Module 11 - Shutdown Systems 20053813.pdf (704 kb)
- Module 12 - Emergency Coolant Injection 20053814.pdf (663 kb)
- Module 13 - Containment 20053815.pdf (1004 kb)
- Module 14 - Annulus Gas System 20053816.pdf (407 kb)
- Module 15 - Shield Cooling Systems 20053817.pdf (528 kb)
- Module 16 - Fuel Performance 20053818.pdf (751 kb)
- Module 17 - Fuel Handling 20053819.pdf (616 kb)
- Module 18 - Unit Upsets 20053820.pdf (1950 kb) -
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) -
Principes de Science et de Fonctionnement des Réacteurs - 20070500, CNSC, 01/01/1993. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] - [Phase] Concept Design [Audience] College Engineer Manager Technician Ugrad
- Réacteurs à Neutrons Intermédiaires et Auxiliaires 20070500.pdf (2850 kb)
- Réacteurs à Neutrons Intermédiaires et Auxiliaires - Systèmes Spéciaux de Sûreté 20070501.pdf (237 kb)
- Réacteurs à Neutrons Intermédiaires et Auxiliaires - Combustible 20070502.pdf (280 kb)
- Réacteurs à Neutrons Intermédiaires et Auxiliaires - CC 20070503.pdf (1500 kb)
- Réacteurs à Neutrons Intermédiaires et Auxiliaires - Réacteurs à Neutrons Intermédiaires et Auxiliaires 20070504.pdf (961 kb)
- Réacteurs à Neutrons Intermédiaires et Auxiliaires - Circuits du Réacteur 20070505.pdf (421 kb) -
Principes de Science et de Fonctionnement des Réacteurs, CNSC, 01/01/1993. Doc type: Course.
Summary:
Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design [Audience] Engineer Ugrad
- Physique du Réacteur 20070800.pdf (1388 kb) -
Reactor, Boiler and Accessories, Course 233, OPG, 01/02/1993. Doc type: Course.
Summary: Table of contents and Objectives for Course 233, Reactor, Boiler, and Auxiliaries.
Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
- Table of Contents and Objectives 20042200.pdf (640 kb)
- 233.20-1 Moderator and Main Moderator System 20042201.pdf (485 kb)
- 233.20-2 Moderator Purification 20042202.pdf (241 kb)
- 233.20-3 Moderator Cover Gas System 20042203.pdf (202 kb)
- 233.20-4 Moderator D2O Collection 20042204.pdf (117 kb)
- 233.20-5 Moderator Liquid Poison System 20042205.pdf (343 kb)
- 233.30-1 Heat Transport D2O and Heat Transport Main System 20042206.pdf (284 kb)
- 233.30-2 Heat Transport Pressurizing System 20042207.pdf (277 kb)
- 233.30-3 Heat Transport Purification 20042208.pdf (235 kb)
- 233.30-4 Heat Transport Gland Seal Circuit 20042209.pdf (165 kb)
- 233.30-5 Heat Transport Shutdown Cooling 20042210.pdf (144 kb)
- 233.30-6 Heat Transport Maintenance Cooling System 20042211.pdf (56 kb)
- 233.30-7 Heat Transport H2 Addition 20042212.pdf (132 kb)
- 233.30-8 Heat Transport Pressure Relief 20042213.pdf (204 kb)
- 233.30-9 Heat Transport D2O Collection 20042214.pdf (100 kb)
- 233.30-10 Heat Transport D2O Recovery 20042215.pdf (113 kb)
- 233.30-11 Emergency Coolant Injection System 20042216.pdf (197 kb)
- 233.30-12 Heat Sources and Transfer Paths 20042217.pdf (271 kb)
- 233.40-1 Shield Cooling Systems 20042218.pdf (250 kb)
- 233.40-2 Containment System 20042219.pdf (462 kb)
- 233.40-3 Annulus Gas System 20042220.pdf (95 kb)
- 233.60-1 Steam Supply System 20042221.pdf (383 kb)
- 233.70-1 Fuel Design and Manufacturing Features 20042222.pdf (377 kb)
- 233.70-2 Fuel Performance and Operating Features 20042223.pdf (521 kb) -
Synergistic Nuclear Fuel Cycles of the Future, by D.A. Meneley, A.R. Dastur, P.J. Fehrenbach and K.H. Talbot, AECL, 11/09/1995. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Fuel Management [Phase] Concept Design Operation [Audience] Engineer Manager
- Global 1995, International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France 20054701.pdf (504 kb)
- Global 1995, International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France 20054702.pdf (443 kb) -
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) -
Nuclear Physics and Reactor Theory 1.1, by Ian Cameron, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
- Title and Table of Contents 20041100.pdf (132 kb)
- Module 1 - Nuclear Structure 20041101.pdf (451 kb)
- Module 2 - Neutron Reactions 20041102.pdf (783 kb)
- Module 3 - Neutron Cross-Sections, Neutron Density and Neutron Flux 20041103.pdf (488 kb)
- Module 4 - Thermal Reactors (Basic Design) 20041104.pdf (413 kb)
- Module 5 - Neutron Multiplication Factor and Reactivity 20041105.pdf (384 kb)
- Module 6 - Neutron Flux Distribution 20041106.pdf (313 kb)
- Module 7 - Effects of Fuel Burnup 20041107.pdf (472 kb)
- Module 8 - Reactor Power Response to Changes in Reactivity 20041108.pdf (574 kb)
- Module 9 - Source Neutron Effects 20041109.pdf (278 kb)
- Module 10 - Power and Power Measurement 20041110.pdf (421 kb)
- Module 11 - Fission Product Poisoning 20041111.pdf (695 kb)
- Module 12 - Reactivity Effects Due to Temperature Changes and Coolant Voiding 20041112.pdf (678 kb)
- Module 13 - Reactivity Control 20041113.pdf (678 kb)
- Module 14 - The Approach To Critical 20041114.pdf (315 kb)
- Module 15 - Neutron Detectors And Reactor Instrumentation 20041115.pdf (639 kb)
- Appendix A 20041116.pdf (72 kb) -
Nuclear Theory II (Kinetics) 1.2, by John L. Groh, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
- Supplement to Chapter 8 20041201.pdf (428 kb)
- Supplement to Chapter 9 20041202.pdf (218 kb)
- Supplement to Chapter 10 20041203.pdf (147 kb)
- Supplement to Chapter 11 20041204.pdf (263 kb)
- Supplement to Chapter 12 20041205.pdf (96 kb)
- Supplement to Chapter 13 20041206.pdf (139 kb)
- Supplement to Chapter 14 20041207.pdf (147 kb)
- Workbook, Chapter 8 20041208.pdf (449 kb)
- Workbook, Chapter 9 20041209.pdf (183 kb)
- Workbook, Chapter 10 20041210.pdf (128 kb)
- Workbook, Chapter 11 20041211.pdf (403 kb)
- Workbook, Chapter 12 20041212.pdf (525 kb)
- Workbook, Chapter 13 20041213.pdf (128 kb)
- Workbook, Chapter 14 20041214.pdf (301 kb) -
Introduction to Nuclear Reactor Kinetics 1.3, by Daniel Rozon, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary: Predicting the evolution in time of the neutron population in a multiplying medium. Time variation of the reactor power (proportional to the total neutron population) is presented.
Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
- Table of Contents 20041800.pdf (31 kb)
- Chapter 1 - Neutron/Nucleus Interactions and Fission 20041801.pdf (1008 kb)
- Chapter 2 - The Diffusion Equation and the Steady State 20041802.pdf (1840 kb)
- Chapter 3 - The Point Kinetics Equation 20041803.pdf (1190 kb)
- Workbook to Chapter 1 - Neutron/Nucleus Interactions and Fission 20041804.pdf (447 kb)
- Workbook to Chapter 2 - The Diffusion Equation and the Steady State 20041805.pdf (709 kb)
- Workbook to Chapter 3 - The Point Kinetics Equations 20041806.pdf (385 kb)
- Workbook to Chapter 4 - Elementary Solutions to the Kinetics Equations 20041807.pdf (398 kb)
- Workbook to Chapter 5 - Approximate Solutions for Reactivity Ramps 20041808.pdf (276 kb) -
Reactor 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) -
Reactor Thermalhydraulics Design, Course 2.1, by W.J. Garland, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary: This course is concerned with the thennalhydraulic design of the process systems that are required to transport heat energy away from the nuclear reactor source and transform this heat energy into useful work (generally electrical energy).
Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Basic Equations Important Parameters Process Systems Thermalhydraulics [Phase] Concept Design Design Analysis Design Evolution Design Process [Audience] Engineer Ugrad
- Title and Table of Contents 20043701.pdf (170 kb)
- Foreword and Glossary 20043702.pdf (74 kb)
- Chapter 1 - Introduction 20043703.pdf (130 kb)
- Chapter 2 - Design Requirements and Engineering Considerations 20043704.pdf (1189 kb)
- Chapter 3 - Heat Transport System Thermalhydrauilics 20043705.pdf (447 kb)
- Chapter 4 - Thermodynamics 20043706.pdf (309 kb)
- Chapter 5 - Fuel Coolant Heat Transfer 20043707.pdf (245 kb)
- Chapter 6 - Control 20043708.pdf (313 kb)
- Chapter 7 - The Design Process 20043709.pdf (419 kb)
- Chapter 8 - Process Design and Optimization 20043710.pdf (441 kb)
- Appendix 1 - Comparison of Bruce A, B, & Darlington 20043711.pdf (223 kb) -
Introduction to Nuclear Reactor Engineering, Course 3.1, by J. Koclas, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Nuclear Engineering [Topic] Basic Equations [Phase] Concept Design [Audience] College Manager Technician Ugrad
- Introduction to Nuclear Engineering 20044101.pdf (1855 kb)
- A Guidebook to Nuclear Reactors by Anthony V. Nero 20044102.pdf (1874 kb)
- Miscellaneous CANDU-Related Viewgraphs 20044103.pdf (1045 kb) -
Nuclear Reactor 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) -
Reactor Licensing & Siting, Course 4.1, by F.C. Boyd, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Safety [Phase] Licensing [Audience] Engineer Manager Vendor
- Section 01 - Schedules Made Persuant to the Nuclear Liability Act 20051501.pdf (299 kb)
- Section 02 - Atomic Energy Control Regulations 20051502.pdf (1000 kb)
- Section 03 - Liability Act 20051503.pdf (1128 kb)
- Section 04 - Bill C-125 Physical Security 20051504.pdf (1341 kb)
- Section 05 - Transport Packaging, U and Th Mining 20051505.pdf (2067 kb)
- Section 06 - R-7 Containment, R-8 Shutdown, R-9 Emergency Cooling 20051506.pdf (1114 kb)
- Section 07 - R-10, R-58, R-75 20051507.pdf (656 kb)
- Section 08 - R-76, R-85, R-90 20051508.pdf (653 kb)
- Section 09 - R-99, R-104 20051509.pdf (1128 kb)
- Section 10 - AECB 1139 The Licensing Process 20051510.pdf (937 kb)
- Section 11 - Licensing Systems & Inspection 20051511.pdf (1703 kb)
- Workbook 01 - Licensing of Nuclear Facilities 20051512.pdf (982 kb)
- Workbook 02 - Siting of NPP 20051513.pdf (624 kb)
- Workbook 03 - Containment & Siting Requirements from IAEA Conference, 1967 20051514.pdf (2248 kb) -
Principles of Nuclear Safety, Course 4.3, by L. Haacke, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety [Audience] Engineer Manager Vendor
- Module 01 - Introduction to the Course 20051701.pdf (70 kb)
- Module 02 - Safety Management & Safety Culture 20051702.pdf (367 kb)
- Module 03 - Defence in Depth 20051703.pdf (599 kb)
- Module 04 - Control/Cool/Contain 20051704.pdf (324 kb)
- Module 05 - Guaranteed Shutdown State 20051705.pdf (212 kb)
- Module 06 - Reliability Concepts 20051706.pdf (807 kb)
- Module 07 - Licensing Principles & Safety Assumptions 20051707.pdf (593 kb)
- Module 08 - Operating Policies & Procedures 20051708.pdf (150 kb)
- Module 09 - Hierarchy of Documents 20051709.pdf (82 kb)
- Module 10 - Authorizations & Approvals 20051710.pdf (302 kb)
- Module 11 - Change Control 20051711.pdf (193 kb)
- Module 12 - Emergency Procedures 20051712.pdf (177 kb)
- Module 13 - Quality Assurance 20051713.pdf (239 kb)
- Module 14 - Surveillance 20051714.pdf (177 kb)
- Module 15 - Impairments 20051715.pdf (195 kb)
- Module 16 - Emissions Compliance Monitoring 20051716.pdf (148 kb)
- Module 17 - Maintenance 20051717.pdf (462 kb)
- Module 18 - Investigating & Reporting Incidents 20051718.pdf (326 kb)
- Appendix I - Definitions 20051719.pdf (371 kb)
- Appendix II - Acronyms 20051720.pdf (55 kb)
- Appendix III - References 20051721.pdf (11 kb)
- Workbook 01 - Introduction to Ontario Hydro 20051722.pdf (95 kb)
- Workbook 02 - Safety Management & Safety Culture 20051723.pdf (254 kb)
- Workbook 03 - Defence in Depth 20051724.pdf (206 kb)
- Workbook 04 - Control/Cool/Contain 20051725.pdf (93 kb)
- Workbook 05 - Guaranteed Shutdown State 20051726.pdf (68 kb)
- Workbook 06 - Reliability Concepts 20051727.pdf (144 kb)
- Workbook 07 - Licensing Principles & Safety Assumptions 20051728.pdf (190 kb)
- Workbook 08 - Operating Policies & Principles 20051729.pdf (39 kb)
- Workbook 09 - Hierarchy of Documents 20051730.pdf (24 kb)
- Workbook10 - Authorizations & Approvals 20051731.pdf (58 kb)
- Workbook11 - Change Control 20051732.pdf (32 kb)
- Workbook 12 - Emergency Procedures 20051733.pdf (60 kb)
- Workbook 13 - Quality Assurance 20051734.pdf (48 kb)
- Workbook 14 - Surveillance 20051735.pdf (39 kb)
- Workbook 15 - Impairments 20051736.pdf (48 kb)
- Workbook 16 - Emissions Compliance Monitoring 20051737.pdf (66 kb)
- Workbook 17 - Maintenance 20051738.pdf (124 kb)
- Workbook 18 - Investigating & Reporting Incidents 20051739.pdf (113 kb) -
Operation & Maintenance of a Nuclear Power Plant, Course 4.4, by D. McQuade, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Maintainability [Phase] Operation [Audience] Engineer Manager Technician
- Title, Objectives, Text Index 20051801.pdf (374 kb)
- Workbook 01 - Management of a Nuclear Power Plant 20051802.pdf (591 kb)
- Workbook 02 - Principles of Operation & Maintenance 20051803.pdf (1187 kb)
- Workbook 03 - Configuration Management 20051804.pdf (620 kb)
- Workbook 04 - Maintenance of an NPP 20051805.pdf (1093 kb)
- Workbook 05 - Outage Management 20051806.pdf (1108 kb)
- Workbook 06 - Specialist Requirements in Maintenance 20051807.pdf (348 kb)
- Workbook 07 - Operator and Maintenance Standards 20051808.pdf (1048 kb)
- Workbook 08 - System Surveillance 20051809.pdf (795 kb)
- Workbook 09 - Building the Total Team 20051810.pdf (771 kb) -
Natural Analogs for Nuclear Fuel Disposal, Course 5.2, by J. Cramer, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Workbook 00 - Introduction to Natural Analogs 20052101.pdf (102 kb)
- Workbook 01 - Copper Corrosion 20052102.pdf (396 kb)
- Workbook 02 - Clay Sealing 20052103.pdf (249 kb)
- Workbook 03 - Clay Sealing 2 20052104.pdf (268 kb)
- Workbook 04 - Clay Sealing - Avonlea Bentonite 20052105.pdf (230 kb)
- Workbook 05 - Concrete Stability 20052106.pdf (99 kb)
- Workbook 06 - Concrete & Ground Water 20052107.pdf (48 kb)
- Workbook 07 - Radionuclide Migration in Soils 20052108.pdf (228 kb)
- Workbook 08 - Natural Nuclear Reactor 20052109.pdf (479 kb)
- Workbook 09 - Disposal System Analog 20052110.pdf (1381 kb)
- Workbook 10 - Summary 20052111.pdf (50 kb) -
Hydrogeology of Nuclear Fuel Disposal, Course 5.4, by D. Stevenson, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Workbook 01 - Hydrogeology 20052301.pdf (1408 kb)
- Workbook 02 - Structural Geology & Borehole Studies 20052302.pdf (1036 kb)
- Workbook 03 - Groundwater Sampling 20052303.pdf (1231 kb)
- Workbook 04 - Candidate Site Characterization 20052304.pdf (734 kb) -
Environmental Issues in Nuclear Fuel Disposal, Course 5.5, by S. Sheppard, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Workbook 01 - Environmental Issues in Waste Management 20052401.pdf (2604 kb)
- Workbook 02 - Lakes and Rivers 20052402.pdf (1445 kb)
- Workbook 03 - Atmosphere 20052403.pdf (815 kb)
- Workbook 04 - Natural Realm 20052404.pdf (906 kb)
- Workbook 05 - Sensitivity Analysis 20052405.pdf (1734 kb)
- Workbook 06 - Monte Carlo Models 20052406.pdf (1234 kb) -
Nuclear Fuel Disposal Performance Assessment, Course 5.6, by J. Cramer, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Workbook 00 - Performance Assessment Modeling 20052501.pdf (65 kb)
- Workbook 01 - Introduction & System Variability Analysis 20052502.pdf (2055 kb)
- Workbook 02 - I/O and Systems Model Interfaces 20052503.pdf (1567 kb)
- Workbook 03 - Complex & Large System Models 20052504.pdf (412 kb)
- Workbook 04 - Sensitivity Analysis & SYVAC3 Applications 20052505.pdf (592 kb)
- Workbook 05 - Canadian System Model & SYVAC3-CC3 20052506.pdf (880 kb) -
Radiation Processing, Course 6.1, by A. Sigh and H. Singh, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Workbook 01 - Basics, Current & Emerging Applications 20052701.pdf (360 kb)
- Workbook 02 - Potential Concerns Associated with Irradiated Foods 20052702.pdf (598 kb)
- Workbook 03 - Irradiated Foods (cont'd) 20052703.pdf (392 kb)
- Workbook 04 - Sterilization of Medical Products 20052704.pdf (494 kb)
- Workbook 05 - Dosimetry 20052705.pdf (223 kb)
- Workbook 06 - Radiation Polymerization - Coatins & Links 20052706.pdf (111 kb)
- Workbook 07 - Radiation Polymerization - Grafting 20052707.pdf (110 kb)
- Workbook 08 - Radiation Polymerization - Bioengineering 20052708.pdf (188 kb)
- Workbook 09 - Polymerization - Material Composites 20052709.pdf (93 kb)
- Workbook 10 - Radiation Protection 20052710.pdf (100 kb)
- Workbook 11 - Dose Rate Effect in Food Irradiation 20052711.pdf (1661 kb)
- Workbook 12 - Radiation Processing - Basic Aspects 20052712.pdf (691 kb)
- Workbook 13 - Industrial Irradiators 20052713.pdf (628 kb)
- Workbook 14 - The Environment 20052714.pdf (66 kb)
- Workbook 15 - Chemical Wastes - PCBs 20052715.pdf (62 kb)
- Workbook 16 - Radiation Processing of Sewage 20052716.pdf (194 kb)
- Workbook 17 - Radiation Processing of Flue Gases 20052717.pdf (91 kb)
- Workbook 18 - Electron Processing in the Pulping Industry 20052718.pdf (360 kb)
- Workbook 19 - Chemical Effects 20052719.pdf (274 kb)
- Workbook 20 - Manufacturing of Chemicals 20052720.pdf (50 kb)
- Workbook 21 - Food Irradiation - Dose Rate Effect 20052721.pdf (301 kb)
- Workbook 22 - Electron Processing - Composites 20052722.pdf (887 kb)
- Workbook 23 - Dosimetry Procedures in Electron Processing 20052723.pdf (248 kb)
- Workbook 24 - Safety in Industrial Accelerator Facility 20052724.pdf (467 kb)
- Workbook 25 - Effects on Polymeric Systems - Polymerization 20052725.pdf (68 kb)
- Workbook 26 - Effects on Polymeric Systems - Crosslinking and Scission 20052726.pdf (232 kb)
- Workbook 27 - Effects on Polymeric Systems - Polyethylene Crosslinking 20052727.pdf (91 kb)
- Workbook 28 - Effects on Polymeric Systems - Elastomers 20052728.pdf (138 kb)
- Workbook 29 - Spices, Herbs, Other Vegetable Seasonings 20052729.pdf (236 kb)
- Workbook 30 - Successful Applications in Food Irradiation 20052730.pdf (316 kb)
- Workbook 31 - Irradiation of Fresh Fruits 20052731.pdf (273 kb)
- Workbook 32 - Radiation Processing of Advanced Composites 20052732.pdf (670 kb)
- Workbook 33 - Micronutrients 20052733.pdf (210 kb)
- Workbook 34 - Irradiation of Red Meats 20052734.pdf (157 kb) -
Neutron Activation Analysis, Course 6.2, by L. Zikovsky, Chulalongkorn University, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Nuclear Engineering [Topic] Conceptual [Phase] Concept [Audience] College Engineer Technician Ugrad
- Chapter 00 - Title and TOC 20052801.pdf (286 kb)
- Chapter 01 - Activation Analysis 20052802.pdf (231 kb)
- Chapter 02 - General Aspects in Trace Analysis 20052803.pdf (198 kb)
- Chapter 03 - Neutron Induced Reactions 20052804.pdf (1636 kb)
- Chapter 04 - Neutron Sources 20052805.pdf (791 kb)
- Chapter 05 - Growth & Decay of Radioactivity During & After Irradiation 20052806.pdf (735 kb)
- Chapter 06 - Nuclear Disintegration & Radiation Detection 20052807.pdf (1459 kb)
- Chapter 07 - Preparation of Samples & Standards 20052808.pdf (1695 kb)
- Chapter 08 - Activation Analysis with Radiochemical Separations 20052809.pdf (1291 kb)
- Chapter 09 - Analysis Without Chemical Separation 20052810.pdf (893 kb)
- Chapter 10 - Systematic Errors in Activation Analysis 20052811.pdf (1410 kb)
- Chapter 11 - Statistical Interpretation of Results 20052812.pdf (1455 kb)
- Workbook 01 - Activation Analysis = Elemental & Isotopic Analysis 20052813.pdf (55 kb)
- Workbook 02 - Structure of Chlorophyll 20052814.pdf (74 kb)
- Workbook 03 - The Nuclear Reaction & Types of Nuclear Particles Employed 20052815.pdf (175 kb)
- Workbook 04 - Irradiation Sources 20052816.pdf (238 kb)
- Workbook 05 - Quantitative Relationships 20052817.pdf (115 kb)
- Workbook 06 - Nuclear Disintegration & Radiation Detection 20052818.pdf (289 kb)
- Workbook 07 - Apparatus to Avoid Contamination 20052819.pdf (37 kb)
- Workbook 08 - Application of HAP to Activation Analysis of Urine 20052820.pdf (52 kb)
- Workbook 09 - Decay Curve of Chlorine in a Terphenyl Sample 20052821.pdf (188 kb)
- Workbook 10 - Sources of Errors in NAA 20052822.pdf (224 kb)
- Workbook 11 - Optimum Counting Time as Function of Counting Rate and Background Rate 20052823.pdf (90 kb)
- Workbook 12 - Typical analysis schemes for fluids and solids 20052824.pdf (148 kb) -
Intermediate Reactors, Boilers and Auxiliaries, CNSC, 01/02/1996. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] - [Phase] Concept Design [Audience] College Engineer Manager Technician Ugrad
- 20052900.pdf (14193 kb) -
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) -
Nuclear Theory I (Statics), or Introduction to Nuclear Technology 1.1a, by Robin Chaplin, Chulalongkorn University, 01/01/1997. Doc type: Course.
Summary: This lecture material is supplementary to Chulalongkorn University Training Program Course # 1.1, Nuclear Physics and Reactor Theory by Ian Cameron (Course 22106), Modules 1 to 7]
Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
- Introduction 20041700.pdf (177 kb)
- Section 1 - Nuclear Physics 20041701.pdf (461 kb)
- Section 1 - Nuclear Physics (Figures) 20041702.pdf (346 kb)
- Section 2 - Nuclear Interactions 20041703.pdf (727 kb)
- Section 2 - Nuclear Interactions (Figures) 20041704.pdf (775 kb)
- Section 3 - Neutron Diffusion 20041705.pdf (255 kb)
- Section 4 - Reactor Theory 20041706.pdf (534 kb)
- Section 4 - Reactor Theory (Figures) 20041707.pdf (456 kb)
- Section 5 - Reactor Kinetics 20041708.pdf (1075 kb)
- Question Bank 20041709.pdf (1095 kb)
- Reference Data 20041710.pdf (537 kb) -
Radioactive Waste Management, Course 5.1, by L. Zikovsky, Chulalongkorn University, 01/01/1997. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Chapter 00 - Table of Contents 20052001.pdf (312 kb)
- Chapter 01 - Introduction 20052002.pdf (1537 kb)
- Chapter 02 - Gaseous Waste 20052003.pdf (1137 kb)
- Chapter 03 - Liquid and Wet Waste 20052004.pdf (2459 kb)
- Chapter 04 - Solid Medium & Low Level 20052005.pdf (2018 kb)
- Chapter 05 - Transport 20052006.pdf (542 kb)
- Chapter 06 - Solid High Level Waste 20052007.pdf (846 kb)
- Chapter 07 - Disposal of High Level Waste 20052008.pdf (3282 kb)
- Chapter 08 - Management of Radioactive Waste in Canada 20052009.pdf (2503 kb)
- Workbook 01 - Radioactive Waste Management 20052010.pdf (374 kb)
- Workbook 02 - Gaseous Radwaste 20052011.pdf (378 kb)
- Workbook 03 - Liquid Radwaste 20052012.pdf (642 kb)
- Workbook 04 - Solid LLW 20052013.pdf (720 kb)
- Workbook 05 - Transport 20052014.pdf (193 kb)
- Workbook 06 - Solid HLW 20052015.pdf (350 kb)
- Workbook 07 - Disposal Principles 20052016.pdf (1066 kb)
- Workbook 08 - Canada's Radwaste 20052017.pdf (1015 kb) -
Engineered Barriers for Fuel Disposal, Course 5.3, by L.H. Johnson, Chulalongkorn University, 18/03/1997. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
- Workbook 01 - Introduction 20052201.pdf (1579 kb)
- Workbook 02 - Detailed Chemistry Considerations 20052202.pdf (700 kb)
- Workbook 03 - Container Failure Predictions 20052203.pdf (924 kb)
- Workbook 04 - Container Design Considerations 20052204.pdf (829 kb)
- Workbook 05 - Seal Materials, Design, & Performance 20052205.pdf (757 kb)
- Workbook 06 - Large Scale In Situ Testing 20052206.pdf (1582 kb)
- Workbook 07 - Vault Model 20052207.pdf (322 kb) -
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) -
Steam Generators for CANDU, Engineering Memoirs, by J.M. Dyke, Individual Contributions, 01/06/1997. Doc type: Essay.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- 20054100.pdf (19 kb) -
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) -
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) -
Peer Evaluation Techniques, Course 4.5, by R.B. Taylor, Chulalongkorn University, 01/11/1997. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Performance [Phase] Operation [Audience] Engineer Manager Technician
- Section 01 - Self-Assessment 20051901.pdf (410 kb)
- Section 02 - Operational Safety Review 20051902.pdf (394 kb)
- Section 03 - Control of Plant Operations 20051903.pdf (432 kb)
- Section 04 - Operations 20051904.pdf (474 kb)
- Section 05 - Maintenance 20051905.pdf (631 kb)
- Section 06 - Housekeeping, Material Conditions, Industrial Safety 20051906.pdf (246 kb)
- Section 07 - Configuration Management 20051907.pdf (218 kb)
- Workbook 01 - Self-Assessment 20051908.pdf (286 kb)
- Workbook 02 - IAEA-OSART 20051909.pdf (468 kb)
- Workbook 03 - Control of Plant Activities 20051910.pdf (228 kb)
- Workbook 04 - Operations 20051911.pdf (459 kb)
- Workbook 05 - Maintenance 20051912.pdf (515 kb)
- Workbook 06 - Housekeeping, Material Conditions, Industrial Safety 20051913.pdf (324 kb)
- Workbook 07 - Configuration Management 20051914.pdf (309 kb) -
Reactor Core Analysis & Fuel Management, Course 1.5, by B. Rouben, Chulalongkorn University, 01/12/1997. Doc type: Course.
Summary: A coupled neutronics-thermalhydraulics analysis of a loss-of-coolants accident (LOCA) in CANDU is presented. The calculation is performed with the CERBERUS (spatial-kinetics) module of the finite-core code RFSP, coupled to the thermalhydraulics code FIREBIRD. The power pulse which results fiom the hypothetical LOCA is assumed terminated by Shutdown System 1 (SDSl). The calculational methodology and the physics model used in the LOCA analysis are detailed. The significant parameters which govern the results of the calculation are discussed.
Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
- Chapter 1 - Coupled Neutronics-Thermalhydaulics LOCA Analysis 20043401.pdf (970 kb)
- Chapter 2 - Core Physics Aspects of Safety Analysis 20043402.pdf (1188 kb)
- Chapter 4 - Fuel Management in CANDU 20043404.pdf (1542 kb)
- Workbook, Chapter 1 - Neutronics-Thermalhydraulics Overheads 20043406.pdf (330 kb)
- Workbook, Chapter 2 - Core Physics Overheads 20043407.pdf (567 kb)
- Chapter 3 - Fuel Management and Advanced Fuel Cycles 20043403.pdf (1436 kb) -
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) -
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) -
CANDU Fuel Management Course, by Ben Rouben, AECL, 01/03/1999. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
- Cover Page 20031100.pdf (91 kb)
- Complete Course 20031101.pdf (286 kb)
- Basic Characteristics of the CANDU Lattice 20031111.pdf (186 kb)
- The CANDU Reactivity Devices 20031112.pdf (147 kb)
- Detector Systems 20031113.pdf (141 kb)
- Computational Scheme for CANDU Neutronics 20031114.pdf (182 kb)
- General Discussion on CANDU Fuel Management 20031115.pdf (125 kb)
- Equilibrium-Core Design 20031116.pdf (217 kb)
- Ongoing Reactor Operation with Channel Refuellings 20031117.pdf (252 kb)
- Effects of 135Xe 20031118.pdf (151 kb)
- Summary 20031119.pdf (61 kb)
- Basic Characteristics of the CANDU Lattice - Figures 20031121.pdf (324 kb)
- The CANDU Reactivity Devices - Figures 20031122.pdf (404 kb)
- Detector Systems - Figures 20031123.pdf (418 kb)
- Computational Scheme for CANDU Neutronics - Figures 20031124.pdf (83 kb)
- General Discussion on CANDU Fuel Management - Figures 20031125.pdf (78 kb)
- Equilibrium-Core Design - Figures 20031126.pdf (309 kb)
- Ongoing Reactor Operation with Channel Refuellings - Figures 20031127.pdf (323 kb)
- Effects of 135Xe - Figures 20031128.pdf (99 kb) -
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) -
RFSP Training Course, by Benoit Arsenault, AECL, 29/03/2000. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
- Chapter 01 - Course Agenda 20054301.pdf (106 kb)
- Chapter 02 - General Intro to Methods of Physics Analysis & Physics Computer Codes 20054302.pdf (381 kb)
- Chapter 03 - The RFSP Direct-Access File 20054303.pdf (274 kb)
- Chapter 04 - RFSP Model 20054304.pdf (400 kb)
- Chapter 05 - Time-Average Model 20054305.pdf (322 kb)
- Chapter 06 - Spatial Kinetics 20054306.pdf (272 kb)
- Chapter 07 - Powderpufs-V 20054307.pdf (348 kb)
- Chapter 08 - *Simulate and *Intrep 20054308.pdf (494 kb)
- Chapter 09 - Flux and Power Mapping in RFSP 20054309.pdf (375 kb)
- Chapter 10 - RRS Modelling in RFSP 20054310.pdf (275 kb)
- Chapter 11 - *INSTANTAN 20054311.pdf (127 kb)
- Chapter 12 - RFSP Code Development 20054312.pdf (336 kb) -
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) -
A Reactor Cannot Explode Like a Nuclear Bomb, by Dan Meneley, Individual Contributions, 01/11/2000. Doc type: Lecture.
Summary:
Keywords: [Concept] - [SI] 03600 Nuclear Safety (Reactor) [Discipline] Nuclear Engineering [Topic] Conceptual Performance [Phase] Concept Design Operation Safety [Audience] College Engineer Manager Technician Vendor
- 20000201.pdf (237 kb) -
How and Why is CANDU designed the way it is, by Bill Garland, CANTEACH, 01/12/2000. Doc type: Paper.
Summary: Why we need nuclear power; A look at the nuclear reactor in a nutshell; The engineering approach - CANDUs are engineered systems, typified by functional decomposition; A quick overview of CANDU vs PWR vs BWR and others.
Keywords: [Concept] Overview [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] Concept Design [Audience] High
- 20000101.pdf (819 kb) -
Why a Chernobyl-type accident cannot happen in CANDU reactors, AECL, 03/01/2001. Doc type: Presentation.
Summary:
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Concept Design Operation Safety [Audience] Engineer Manager Vendor
- 20010701.pdf (1026 kb) -
CANDU Origins and Evolution, by Gordon L.Brooks and John S. Foster, AECL, 01/02/2001. Doc type: Paper.
Summary: While the name 'CANDU' was not adopted until the 1960's, the CANDU program can be considered to have started in early 1954. At that time, a team, called the Nuclear Power Group, was established to undertake studies intended to identify a potential Canadian nuclear power system. While the team operated under the auspices of AECL and was located in Building 456 at AECL's Chalk River Laboratory, its membership was drawn from a cross-section of Canadian utility and industrial organizations supported, as required, with "nuclear" expertise provided by AECL staff.
Keywords: [Concept] Overview [SI] 03000 Engineering Science and Technology 31000 Reactor [Discipline] General Engineering Nuclear Engineering [Topic] Conceptual Important Parameters Intro and Overview [Phase] Concept Design Design Evolution [Audience] Manager
- Overview 20010301.pdf (132 kb)
- Why CANDU 20010302.pdf (99 kb)
- Figure of 8 20010303.pdf (111 kb)
- Emergency Core Cooling System 20010304.pdf (107 kb)
- The Origin and Evolution of the Second Shutdown System 20010305.pdf (101 kb) -
Fuel for the Next Millennia, by Dan Meneley, AECL, 06/03/2001. Doc type: Presentation.
Summary:
Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Fuel Management [Phase] Concept Design Operation [Audience] Engineer Manager
- 20010201.pdf (906 kb) -
Starting Up a CANDU Reactor, by Dan Meneley, AECL, 20/07/2001. Doc type: Paper.
Summary: CANDU power reactor designers and operators are fully aware of the need for caution in starting up power reactors. However, the open literature describing these established methods is quite sparse, especially with regard to the unique advantages in operability and safety that arise from the computer-driven Reactor Regulating System (RRS). The following text provides a general outline of one procedure appropriate for start-up of a CANDU 6 reactor.
Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Reactor Physics [Phase] Operation [Audience] College Engineer Manager Technician Ugrad
- Abbreviated Step-by Step Procedure 20010401.pdf (94 kb) -
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) -
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) -
Fretting in Nuclear Steam Generators - A New Approach, by J.M. Dyke, Individual Contributions, 20/04/2003. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- 11th International Conference on Nuclear Engineering, Tokyo, Japan 20054500.pdf (2821 kb) -
Preserving CANDU Technical Knowledge – The CANTEACH Project, by Bill Garland, Yulia Kosarenko, Malcolm Lightfoot, Dan Meneley, CANTEACH, 10/05/2003. Doc type: Paper.
Summary:
Keywords: [Concept] General [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High K-8 Manager Technician Ugrad Vendor
- 20031401.pdf (245 kb) -
Preservation and Dissemination of CANDU® Technical Knowledge (The CANTEACH Project), by Bill Garland, Yulia Kosarenko, Malcolm Lightfoot, Dan Meneley, CANTEACH, 10/05/2003. Doc type: Paper.
Summary:
Keywords: [Concept] General [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High K-8 Manager Technician Ugrad Vendor
- 20031501.pdf (299 kb) -
CANTEACH Flyer, by CANTEACH, CANTEACH, 01/06/2003. Doc type: Presentation.
Summary:
Keywords: [Concept] General [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High K-8 Manager Technician Ugrad Vendor
- 20031601.pdf (156 kb) -
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) -
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) -
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) -
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) -
The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators, by J.M. Dyke, Individual Contributions, 20/04/2004. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- 12th International Conference on Nuclear Engineering, Washington, DC 20054201.pdf (1714 kb)
- 12th International Conference on Nuclear Engineering, Washington, DC 20054202.pdf (1558 kb) -
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) -
Fretting Failures in Early Canadian Nuclear Steam Generators, by J.M. Dyke and W.J. Garland, CANTEACH, 01/03/2006. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- 20060201.pdf (140 kb) -
Evolution of CANDU Steam Generators – A Historical View, by J.M. Dyke and W.J. Garland, CANTEACH, 01/04/2006. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
- 20060101.pdf (702 kb) -
Lecture Presentations on Heavy Water Reactors at 2010 Frederic Joliot / Otto Hahn Summer School (FJOHSS) on Nuclear Reactors held in Aix-en-Provence, France, August 25 to September 3, 2010, by Blair P. Bromley, FJOHSS, 07/09/2010. Doc type: Lecture.
Summary:
Keywords: [Concept] - [SI] 00000 General Project [Discipline] History Nuclear Engineering Physics [Topic] Conceptual Important Parameters Intro and Overview Physical Description [Phase] Concept Design Design Description Design Evolution [Audience] College Engineer Manager Ugrad
- Main Lecture - Short Version 20110201.pdf (3441 kb)
- Main Lecture - Long Version 20110202.pdf (10737 kb)
- Supplement 1: R&D Activities for HWR Design and Safety Analysis 20110203.pdf (8280 kb)
- Supplement 2: Alternative Concepts and Early HWR Prototypes 20110204.pdf (8403 kb) -
Concept Maps, by Bill Garland, CANTEACH, 01/01/2011. Doc type: Other.
Summary: Illustrated are the overall concepts and topics in the various disciplines involved in the design and operation of CANDU reactors. This provides some guidance for the detailed study of CANDU reactors.
Keywords: [Concept] Overview [SI] - [Discipline] Nuclear Engineering [Topic] Conceptual Intro and Overview [Phase] Concept [Audience] College Engineer Grad High Manager Technician Ugrad
- Overview of Concepts and Topics 20110101.pdf (264 kb) -
Design and Safety of Canadian Nuclear Reactors, by V. Snell, UNENE, 25/01/2012. Doc type: Presentation.
Summary:
Keywords: [Concept] Safety [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety [Audience] Engineer Grad Manager Technician Ugrad
- 20120101.pdf (11620 kb)
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