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[Topic]: Reactor Physics 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.

363 files

    1966---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  1. 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)
    2. 1967---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  2. Nuclear Theory, Course 227, Nuclear Training Centre, OPG, 01/07/1967. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Full Course 20050400.pdf (2650 kb)
    - 227.00-01 Prompt, Delayed and Photo-Neutron Production 20050401.pdf (153 kb)
    - 227.00-02 Neutron Balance During Steady Reactor Operation 20050402.pdf (206 kb)
    - 227.00-03 Neutron Density, Neutron Power and Neutron Flux 20050403.pdf (103 kb)
    - 227.00-04 Neutron Flux Distribution and its Effect on Power 20050404.pdf (274 kb)
    - 227.00-05 Meaning of Criticality, Multiplication Factor, Reactivity and Neutron Lifetime 20050405.pdf (140 kb)
    - 227.00-06 Change of Reactor Power with Reactivity Change 20050406.pdf (198 kb)
    - 227.00-07 Change of Reactor Power with Time 20050407.pdf (112 kb)
    - 227.00-08 Effects of Prompt and Delayed Neutrons on Reactor Power Changes 20050408.pdf (282 kb)
    - 227.00-09 Effect of Photoneutrons on Reactor Power Changes 20050409.pdf (150 kb)
    - 227.00-10 Methods of Reactor Control 20050410.pdf (160 kb)
    - 227.00-11 Starting Up a Reactor and Increasing Power 20050411.pdf (197 kb)
    - 227.00-12 Decreasing Power and Shutting Down a Reactor 20050412.pdf (146 kb)
    - 227.00-13 Xenon Poison and its Effects on Reactor Operation 20050413.pdf (241 kb)
    - 227.00-14 Examples of Practical Reactor Behaviour 20050414.pdf (156 kb)
    3. 1968---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  3. 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)
    4. 1972---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  4. An Introduction to the CANDU Nuclear Energy Conversion System, by Archie Harms, McMaster University, 25/05/1972. Doc type: Book.
    Summary:
    Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Nuclear Engineering [Topic] Basic Equations Conceptual Intro and Overview Reactor Physics Thermalhydraulics [Phase] Concept Design Safety [Audience] College Engineer Technician Ugrad
    - Table of Contents and Chapter 1: Introduction 19750101.pdf (622 kb)
    - Chapter 2: Nuclear Processes 19750102.pdf (493 kb)
    - Chapter 3: Neutron Physics 19750103.pdf (567 kb)
    - Chapter 4: Reactor Statics 19750104.pdf (650 kb)
    - Chapter 5: Reactor Dynamics 19750105.pdf (428 kb)
    - Chapter 6: Control and Operations 19750106.pdf (499 kb)
    - Chapter 7: Thermal-hydraulic Analysis 19750107.pdf (439 kb)
    - Chapter 8: Nuclear Reactor Materials 19750108.pdf (781 kb)
    - Chapter 9: Safety Analysis 19750109.pdf (152 kb)
    - Chapter 10: CANDU Reactors part 1 19750110.pdf (764 kb)
    - Chapter 10: CANDU Reactors part 2 19750111.pdf (686 kb)
    5. 1974---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  5. Nuclear Theory, Course 127, Nuclear Training Centre, OPG, 01/07/1974. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Full Course 20050300.pdf (5869 kb)
    - 127.00-00 Index and Objectives 20050301.pdf (244 kb)
    - 127.10-01 Nuclear Structure 20050302.pdf (571 kb)
    - 127.10-02 Neutron Reactions 20050303.pdf (156 kb)
    - 127.10-03 Fission 20050304.pdf (264 kb)
    - 127.10-04 Neutron Cross Sections and Neutron Flux 20050305.pdf (305 kb)
    - 127.10-05 The Chain Reaction 20050306.pdf (240 kb)
    - 127.10-06 Moderator Properties 20050307.pdf (296 kb)
    - 127.10-05b Neutron Balance and the Four Factor Formula 20050308.pdf (270 kb)
    - 127.10-06b Effect of Enrichment, Fuel Arrangement and Fuel Burnup on the Four Factor Formula 20050309.pdf (287 kb)
    - 127.10-07 Flux Distribution and Critical Size 20050310.pdf (203 kb)
    - 127.10-08 Function and Properties of the Reflector 20050311.pdf (219 kb)
    - 127.20-01 Review of Terms 20050312.pdf (201 kb)
    - 127.20-02 Low Power Considerations 20050313.pdf (341 kb)
    - 127.20-03 Effects Due to Temperature Changes and Void Formation 20050314.pdf (330 kb)
    - 127.20-04 Effects Due to Fission Product Accumulation 20050315.pdf (295 kb)
    - 127.20-05 Effects Due to Fuel Burnup 20050316.pdf (245 kb)
    - 127.20-06 Reactor Control 20050317.pdf (303 kb)
    - 127.20-07 The Approach to Critical and the Raising of Power 20050318.pdf (534 kb)
    - 127.20-08 Examples of Practical Reactor Behaviour 20050319.pdf (262 kb)
    - 127.20-09 Reactor Stability 20050320.pdf (135 kb)
    - 127.20-10 Safety Considerations 20050321.pdf (308 kb)
    6. 1977---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  6. 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)
    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. 1989---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  9. CANDU Advanced Plutonium Burner - The Canadian Response to the ALWR, by A.R. Dastur and A.C. Mao , AECL, 01/05/1989. Doc type: Paper.
    Summary: As published in the Canadian Nuclear Society Bulletin Vol. 10, No. 3, 1989 with the kind permission of the CNS: It is demonstrated that the prescnt CANDU design concept has potential for increased conversion and resource utilization compared with other reactor concepts. Discussed here is a CANDU based concept thau utilizes energy produced by subcritical multiplication in a fertile region designed for accelerated plutonium production is presented. Its feasibility is based on incorporating the channels with fertile material into the primary heal transport circuit. Calculations with multigroup transport codes predict very high fuel utilization due to the production and burnup of fissile plutonium in the fertile region.
    Keywords: [Concept] Reactor Physics [SI] 03300 Nuclear Engineering 31000 Reactor 37000 Fuel [Discipline] Nuclear Engineering [Topic] Conceptual Reactor Physics [Phase] Concept [Audience] Engineer Grad Manager Ugrad Vendor
    - 19890101.pdf (299 kb)
    10. 1990---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  10. 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)
  11. 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)
    12. 1992---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  12. 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)
  13. Nuclear Theory, Nuclear Training Course 227 20031001, OPG, 01/08/1992. Doc type: Course.
    Summary: Introductory reactor physics covering the basic phenomena without extensive use of equations. Revised by N. Ritter.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - Cover pages and table of contents 20031001.pdf (76 kb)
    - Objectives 20031002.pdf (164 kb)
    - Chapter 1: Nuclear Structure 20031003.pdf (213 kb)
    - Chapter 2: Neutron Reactions 20031004.pdf (631 kb)
    - Chapter 3: Neutron Cross Sections, Neutron Density and Neutron Flux 20031005.pdf (289 kb)
    - Chapter 4: Thermal Reactors (Basic Design) 20031006.pdf (317 kb)
    - Chapter 5: Neutron Multiplication Factor and Reactivity 20031007.pdf (184 kb)
    - Chapter 6: Neutron Flux Distribution 20031008.pdf (321 kb)
    - Chapter 7: Effect of Fuel Burnup 20031009.pdf (395 kb)
    - Chapter 8: Changes in Reactor Power with Time 20031010.pdf (314 kb)
    - Chapter 9: Source Neutron Effects 20031011.pdf (307 kb)
    - Chapter 10: Power and Power Measurements 20031012.pdf (356 kb)
    - Chapter 11: Fission Product Measurement 20031013.pdf (838 kb)
    - Chapter 12: Reactivity Effects due to Temperature Changes 20031014.pdf (406 kb)
    - Chapter 13: Reactivity Control 20031015.pdf (732 kb)
    - Chapter 14: The Approach to Critical 20031016.pdf (384 kb)
    - Appendix: A: Symbols 20031017.pdf (23 kb)
    - Appendix: B: Properties of Elements and Certain Molecules 20031018.pdf (105 kb)
    - Appendix: C: Nuclides and Isotopes 20031019.pdf (1547 kb)
    14. 1993---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  14. Principes de Science et de Fonctionnement des Réacteurs, CNSC, 01/01/1993. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Conceptual Reactor Physics [Phase] Concept Design [Audience] Engineer Ugrad
    - Physique du Réacteur 20070800.pdf (1388 kb)
  15. 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)
    16. 1996---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  16. 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)
  17. 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)
  18. 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)
  19. 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)
  20. 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)
    21. 1997---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  21. 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)
  22. 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)
  23. 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)
    24. 1999---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  24. 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)
    25. 2000---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  25. 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)
    26. 2001---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  26. 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)
    27. 2002---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  27. 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)
  28. 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)
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