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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.

Number of files: 373

    1950-01-01---------Jump to [Top]
  1. Simulation Software, by Wm.J. Garland, McMaster University, 1950-01-01. Doc type: Essay.
    Summary: Major endeavours such as a CANDU nuclear power plant involves extensive engineering calculations usually performed using large simulation tools.  However, to aid in conceptual BOE (back of envelope) evaluations and for education and training exercises, simplified and focused calculations are often done.  To aid students and working professional alike, a few such small tools (primarily spreadsheets) are linked below.  Go to Topics: Modelling to see the full list.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor Steam Generators and Auxiliaries [Discipline] General Engineering Mechanical Engineering Nuclear Engineering [Topic] Basic Equations Conceptual Heat Transfer Modelling Process Systems Reactor Physics Thermalhydraulics [Phase] Concept Design Analysis [Audience] College Engineer Grad Technician Ugrad
    - SimulationSoftware.pdf (267 kb)
    2. 1962-09-01---------Jump to [Top]
  2. Reactor Loops at Chalk River, by Ronald Needham, AECL, 1962-09-01. Doc type: Paper.
    Summary: Description of the Chalk River NRX and NRU in-reactor test loops for materials testing under simulated reactor power conditions.
    Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Materials Engineering Nuclear Engineering [Topic] Radiation Reactor Physics Thermalhydraulics [Phase] Concept [Audience] Engineer Technician Ugrad
    - CRL-Loops1962.pdf (1547 kb)
    3. 1966-11-01---------Jump to [Top]
  3. Reactor, Boiler and Auxiliaries, Course 133, Nuclear Training Center, OPG, 1966-11-01. 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)
    4. 1967-07-01---------Jump to [Top]
  4. Nuclear Theory, Course 227, Nuclear Training Centre, OPG, 1967-07-01. 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)
    5. 1968-11-01---------Jump to [Top]
  5. Reactor Boiler and Auxiliaries, Course 433, Nuclear Training Centre, OPG, 1968-11-01. 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)
    6. 1972-05-25---------Jump to [Top]
  6. An Introduction to the CANDU Nuclear Energy Conversion System, by Archie Harms, McMaster University, 1972-05-25. 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, by Archie Harms, 19750102.pdf (493 kb)
    - Chapter 3: Neutron Physics, by Archie Harms, 19750103.pdf (567 kb)
    - Chapter 4: Reactor Statics, by Archie Harms, 19750104.pdf (650 kb)
    - Chapter 5: Reactor Dynamics, by Archie Harms, 19750105.pdf (428 kb)
    - Chapter 6: Control and Operations, by Archie Harms, 19750106.pdf (499 kb)
    - Chapter 7: Thermal-hydraulic Analysis, by Archie Harms, 19750107.pdf (439 kb)
    - Chapter 8: Nuclear Reactor Materials, by Archie Harms, 19750108.pdf (781 kb)
    - Chapter 9: Safety Analysis, by Archie Harms, 19750109.pdf (152 kb)
    - Chapter 10: CANDU Reactors part 1, by Archie Harms, 19750110.pdf (764 kb)
    - Chapter 10: CANDU Reactors part 2, by Archie Harms, 19750111.pdf (686 kb)
    7. 1974-07-01---------Jump to [Top]
  7. Nuclear Theory, Course 127, Nuclear Training Centre, OPG, 1974-07-01. 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)
    8. 1977-04-01---------Jump to [Top]
  8. Reactor, Boilers and Auxiliaries, Nuclear Training Course 133, OPG, 1977-04-01. 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)
    9. 1980-01-01---------Jump to [Top]
  9. Fundamentals of CANDU Reactor Nuclear Design (TDAI-244), by A.A. Pasanen, AECL, 1980-01-01. 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, by A.A. Pasanen, 20042001.pdf (35 kb)
    - Chapter 2 - Physical Description of the CANDU-600, by A.A. Pasanen, 20042002.pdf (672 kb)
    - Chapter 3 - Methodology for Reactor Physics Analysis In Core Design, by A.A. Pasanen, 20042003.pdf (1922 kb)
    - Chapter 4 - Initial Fuel Loading Determination, by A.A. Pasanen, 20042004.pdf (379 kb)
    - Chapter 5 - Physics Analysis and Tests Related to Commissioning, by A.A. Pasanen, 20042005.pdf (764 kb)
    - Bibliography, by A.A. Pasanen, 20042006.pdf (111 kb)
    10. 1980-08-01---------Jump to [Top]
  10. Nuclear Theory, Course 227, Nuclear Training Centre 20053700, by J.E. Crist, J. U. Burnham, A. Broughton, D. Winfield, OPG, 1980-08-01. 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, by J. Crist, 20053701.pdf (443 kb)
    - 227.00-01 Nuclear Structure, by J. U. Burnham, J.E. Crist, A. Broughton, 20053702.pdf (274 kb)
    - 227.00-02 Neutron Reactions, by J. U. Burnham, J.E. Crist, 20053703.pdf (662 kb)
    - 227.00-03 Neutron Cross Sections, Neutron Density and Neutron Flux, by J. U. Burnham, J.E. Crist, A. Broughton, 20053704.pdf (318 kb)
    - 227.00-04 Thermal Reactors (Basic Design), by J.E. Crist, A. Broughton, 20053705.pdf (342 kb)
    - 227.00-05 Neutron Multiplication Factor and Reactivity, by J.E. Crist, 20053706.pdf (196 kb)
    - 227.00-06 Neutron Flux Distribution, by J.E. Crist, 20053707.pdf (324 kb)
    - 227.00-07 Effect of Fuel Burnup, by J.E. Crist, 20053708.pdf (361 kb)
    - 227.00-08 Changes in Reactor Power with Time, by J.E. Crist, 20053709.pdf (328 kb)
    - 227.00-09 Source Neuron Effects, by J.E. Crist, A. Broughton, 20053710.pdf (217 kb)
    - 227.00-10 Power and Power Measurement, by J.E. Crist, A. Broughton, 20053711.pdf (356 kb)
    - 227.00-11 Fission Product Poisoning, by J. U. Burnham, J.E. Crist, 20053712.pdf (866 kb)
    - 227.00-12 Reactivity Effects Due to Temperature Changes, by J.E. Crist, 20053713.pdf (454 kb)
    - 227.00-13 Reactivity Control, by J.E. Crist, A. Broughton, 20053714.pdf (875 kb)
    - 227.00-14 The Approach to Critical, by J.E. Crist, A. Broughton, 20053715.pdf (148 kb)
    - 227.00-15 Failed Fuel Monitoring, by D. Winfield, A. Broughton, 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)
    11. 1987-03-01---------Jump to [Top]
  11. Nuclear Journal of Canada, 1987 Vol 1 No. 1, by E.M.A. Hussein, D.R. OConnor and M.E. Mosher, CNS-, 1987-03-01. Doc type: Paper.
    Summary: A neutron reflection method is developed for measuring the concentration of the neutron absorbing gadolinium in the tanks of the liquid poison injection shutdown system of a CANDU reactor. The feasibility of the method is demonstrated experimentally, and Monte Carlo simulations are utilized to design and model the performance of a proposed device.
    Keywords: [Concept] Reactor Physics [SI] 32700 Moderator Liquid Poison System [Discipline] Nuclear Engineering Physics [Topic] Reactor Physics [Phase] Concept [Audience] College Grad Technician Ugrad
    - A Non-Intrusive Neutron Method for Poison Concentration Monitoring in CANDU Reactors NJC-1-1-07.pdf (427 kb)
    - Gestion du cycle de combustible a la Centrale Nucleaire Gentilly-2, by G. Hotte, G. Parent, L. Cloutier, A. Aubin and N. Macici, NJC-1-1-10.pdf (762 kb)
    12. 1987-12-01---------Jump to [Top]
  12. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by Alain Hebert, CNS-, 1987-12-01. Doc type: Paper.
    Summary: A new three-dimensional neutron diffusion code named TRIVAC was set up using advanced discretization algorithms and improved iteration strategies. The two variable order discretization algorithms used in TRIVAC will be presented.
    Keywords: [Concept] Reactor Physics [SI] 03000 Engineering Science and Technology 31000 Reactor [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis Operation [Audience] Engineer Grad Ugrad
    - Trivac: A Modular Diffusion Code for Fuel Management and Design Applications NJC-1-4-06.pdf (472 kb)
    13. 1989-05-01---------Jump to [Top]
  13. CANDU Advanced Plutonium Burner - The Canadian Response to the ALWR, by A.R. Dastur and A.C. Mao, AECL, 1989-05-01. 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)
    14. 1990-01-01---------Jump to [Top]
  14. Nuclear Theory, Course PI 27 , Nuclear Training Centre, OPG, 1990-01-01. 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)
    15. 1990-07-01---------Jump to [Top]
  15. Nuclear Theory, Course 427, Nuclear Training Centre, OPG, 1990-07-01. 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)
    16. 1992-06-01---------Jump to [Top]
  16. Reactor Boiler and Auxiliaries, Course 233, Nuclear Training, OPG, 1992-06-01. 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)
    17. 1992-08-01---------Jump to [Top]
  17. Nuclear Theory, Nuclear Training Course 227 20031001, OPG, 1992-08-01. 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)
    18. 1993-01-01---------Jump to [Top]
  18. Principes de Science et de Fonctionnement des Réacteurs, CNSC, 1993-01-01. 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)
    19. 1993-02-01---------Jump to [Top]
  19. Reactor, Boiler and Accessories, Course 233, OPG, 1993-02-01. 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)
    20. 1995-06-25---------Jump to [Top]
  20. Effects Contributing to Positive Coolant Void Reactivity in CANDU, by J. J. Whitlock, Wm.J. Garland, M.S. Milgram, McMaster University, 1995-06-25. Doc type: Paper.
    Summary: The lattice cell properties leading to positive coolant void reactivity in the CANDU reactor are described. The effect is subdivided into spectral, spatial, and isotopic components, and described in terms of criticality factors based on the six-factor fo
    Keywords: [Concept] Reactor Physics [SI] 03000 Engineering Science and Technology 31000 Reactor [Discipline] Nuclear Engineering [Topic] Reactor Physics3 [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Whitlock_ANS_1995.pdf (777 kb)
    21. 1996-01-01---------Jump to [Top]
  21. Reactor Physics & Fuelling Strategies 1.4, by R.D. Page, Chulalongkorn University, 1996-01-01. 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, by A.G. Lee and G.B. Wilkin, 20042117.pdf (482 kb)
    22. 1996-02-01---------Jump to [Top]
  22. Nuclear Physics and Reactor Theory 1.1, by Ian Cameron, Chulalongkorn University, 1996-02-01. 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, by Ian Cameron, 20041101.pdf (451 kb)
    - Module 2 - Neutron Reactions, by Ian Cameron, 20041102.pdf (783 kb)
    - Module 3 - Neutron Cross-Sections, Neutron Density and Neutron Flux, by Ian Cameron, 20041103.pdf (488 kb)
    - Module 4 - Thermal Reactors (Basic Design), by Ian Cameron, 20041104.pdf (413 kb)
    - Module 5 - Neutron Multiplication Factor and Reactivity, by Ian Cameron, 20041105.pdf (384 kb)
    - Module 6 - Neutron Flux Distribution, by Ian Cameron, 20041106.pdf (313 kb)
    - Module 7 - Effects of Fuel Burnup, by Ian Cameron, 20041107.pdf (472 kb)
    - Module 8 - Reactor Power Response to Changes in Reactivity, by Ian Cameron, 20041108.pdf (574 kb)
    - Module 9 - Source Neutron Effects, by Ian Cameron, 20041109.pdf (278 kb)
    - Module 10 - Power and Power Measurement, by Ian Cameron, 20041110.pdf (421 kb)
    - Module 11 - Fission Product Poisoning, by Ian Cameron, 20041111.pdf (695 kb)
    - Module 12 - Reactivity Effects Due to Temperature Changes and Coolant Voiding, by Ian Cameron, 20041112.pdf (678 kb)
    - Module 13 - Reactivity Control, by Ian Cameron, 20041113.pdf (678 kb)
    - Module 14 - The Approach To Critical, by Ian Cameron, 20041114.pdf (315 kb)
    - Module 15 - Neutron Detectors And Reactor Instrumentation, by Ian Cameron, 20041115.pdf (639 kb)
    - Appendix A, by Ian Cameron, 20041116.pdf (72 kb)
  23. Nuclear Theory II (Kinetics) 1.2, by John L. Groh, Chulalongkorn University, 1996-02-01. 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, by John L. Groh, 20041202.pdf (218 kb)
    - Supplement to Chapter 10, by John L. Groh, 20041203.pdf (147 kb)
    - Supplement to Chapter 11, by John L. Groh, 20041204.pdf (263 kb)
    - Supplement to Chapter 12, by John L. Groh, 20041205.pdf (96 kb)
    - Supplement to Chapter 13, by John L. Groh, 20041206.pdf (139 kb)
    - Supplement to Chapter 14, by John L. Groh, 20041207.pdf (147 kb)
    - Workbook, Chapter 8, by John L. Groh, 20041208.pdf (449 kb)
    - Workbook, Chapter 9, by John L. Groh, 20041209.pdf (183 kb)
    - Workbook, Chapter 10, by John L. Groh, 20041210.pdf (128 kb)
    - Workbook, Chapter 11, by John L. Groh, 20041211.pdf (403 kb)
    - Workbook, Chapter 12, by John L. Groh, 20041212.pdf (525 kb)
    - Workbook, Chapter 13, by John L. Groh, 20041213.pdf (128 kb)
    - Workbook, Chapter 14, by John L. Groh, 20041214.pdf (301 kb)
  24. Introduction to Nuclear Reactor Kinetics 1.3, by Daniel Rozon, Chulalongkorn University, 1996-02-01. 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, by Daniel Rozon, 20041801.pdf (1008 kb)
    - Chapter 2 - The Diffusion Equation and the Steady State, by Daniel Rozon, 20041802.pdf (1840 kb)
    - Chapter 3 - The Point Kinetics Equation, by Daniel Rozon, 20041803.pdf (1190 kb)
    - Workbook to Chapter 1 - Neutron/Nucleus Interactions and Fission, by Daniel Rozon, 20041804.pdf (447 kb)
    - Workbook to Chapter 2 - The Diffusion Equation and the Steady State, by Daniel Rozon, 20041805.pdf (709 kb)
    - Workbook to Chapter 3 - The Point Kinetics Equations, by Daniel Rozon, 20041806.pdf (385 kb)
    - Workbook to Chapter 4 - Elementary Solutions to the Kinetics Equations, by Daniel Rozon, 20041807.pdf (398 kb)
    - Workbook to Chapter 5 - Approximate Solutions for Reactivity Ramps, by Daniel Rozon, 20041808.pdf (276 kb)
  25. Reactor Physics & Fuelling Strategies 1.4, by John Brenciaglia, Chulalongkorn University, 1996-02-01. 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, by John Brenciaglia, 20042102.pdf (137 kb)
    - Lecture 3 - Lattice Parameter Calculations, by John Brenciaglia, 20042103.pdf (531 kb)
    - Lecture 4 - Core Design Analysis, by John Brenciaglia, 20042104.pdf (332 kb)
    - Lecture 5 - Time Dependence Simulation, by John Brenciaglia, 20042105.pdf (600 kb)
    - Lecture 6 - Initial Fuel Load, by John Brenciaglia, 20042106.pdf (253 kb)
    - Lecture 7 - Startup Physics Tests, by John Brenciaglia, 20042107.pdf (531 kb)
    - Lecture 8 - Power Distribution Control, by John Brenciaglia, 20042108.pdf (720 kb)
    - Lecture 9 - Safety Analysis Requirements, by John Brenciaglia, 20042109.pdf (392 kb)
    - Chapter 10 - Fuel Design Analysis, by John Brenciaglia, 20042110.pdf (187 kb)
    - Lecture 11 - Fueling Strategies and Cycles, by John Brenciaglia, 20042111.pdf (745 kb)
    - Lecture 12 - Research Reactors Requirements, by John Brenciaglia, 20042112.pdf (138 kb)
    - Reference to Lecture 8 - In-Core Fuel Management, by D.A. Jenkins, 20042113.pdf (1105 kb)
    - Reference to Lecture 9 - Role of Physics Analysis in Safety and Licensing, by H.C. Chow, 20042114.pdf (1389 kb)
    - Reference to Lecture 11 - Fuel Management & Reactor Operation - Review of Operating Experience, by G.M. Frescura and A.L. Wight, 20042116.pdf (1501 kb)
    26. 1997-01-01---------Jump to [Top]
  26. Nuclear Theory I (Statics), or Introduction to Nuclear Technology 1.1a, by Robin Chaplin, Chulalongkorn University, 1997-01-01. 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, by Robin Chaplin, 20041701.pdf (461 kb)
    - Section 1 - Nuclear Physics (Figures), by Robin Chaplin, 20041702.pdf (346 kb)
    - Section 2 - Nuclear Interactions, by Robin Chaplin, 20041703.pdf (727 kb)
    - Section 2 - Nuclear Interactions (Figures), by Robin Chaplin, 20041704.pdf (775 kb)
    - Section 3 - Neutron Diffusion, by Robin Chaplin, 20041705.pdf (255 kb)
    - Section 4 - Reactor Theory, by Robin Chaplin, 20041706.pdf (534 kb)
    - Section 4 - Reactor Theory (Figures), by Robin Chaplin, 20041707.pdf (456 kb)
    - Section 5 - Reactor Kinetics, by Robin Chaplin, 20041708.pdf (1075 kb)
    - Question Bank, by Robin Chaplin, 20041709.pdf (1095 kb)
    - Reference Data, by Robin Chaplin, 20041710.pdf (537 kb)
    27. 1997-04-08---------Jump to [Top]
  27. Monte Carlo Method for Particle Transport Simulation, Course 1.6, by E. Hussein, Chulalongkorn University, 1997-04-08. 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, by E. Hussein, 20043502.pdf (30 kb)
    - Chapter 2 - Monte Carlo Method, by E. Hussein, 20043503.pdf (283 kb)
    - Chapter 3 - Boltzmann Transport Equation, by E. Hussein, 20043504.pdf (79 kb)
    - Chapter 4 - MCNP Input Structure, by E. Hussein, 20043505.pdf (29 kb)
    - Chapter 5 - Geometry in MCNP, by E. Hussein, 20043506.pdf (105 kb)
    - Chapter 6 - MCNP Source Parameters, by E. Hussein, 20043507.pdf (173 kb)
    - Chapter 7 - Physics & Material Cross-Sections, by E. Hussein, 20043508.pdf (67 kb)
    - Chapter 8 - Termination Parameters, by E. Hussein, 20043509.pdf (30 kb)
    - Chapter 9 - Importance Sampling, by E. Hussein, 20043510.pdf (122 kb)
    - Chapter 10 - Tallying, by E. Hussein, 20043511.pdf (163 kb)
    - Chapter 11 - Uncertainty Analysis, by E. Hussein, 20043512.pdf (177 kb)
    - Chapter 12 - Criticality in MCNP, by E. Hussein, 20043513.pdf (42 kb)
    - Workbook, Chapter 1, by E. Hussein, 20043514.pdf (60 kb)
    - Workbook, Chapter 2, by E. Hussein, 20043515.pdf (460 kb)
    - Workbook, Chapter 3, by E. Hussein, 20043516.pdf (103 kb)
    - Workbook, Chapter 4, by E. Hussein, 20043517.pdf (45 kb)
    - Workbook, Chapter 5, by E. Hussein, 20043518.pdf (167 kb)
    - Workbook, Chapter 6, by E. Hussein, 20043519.pdf (270 kb)
    - Workbook, Chapter 7, by E. Hussein, 20043520.pdf (95 kb)
    - Workbook, Chapter 8, by E. Hussein, 20043521.pdf (41 kb)
    - Workbook, Chapter 9, by E. Hussein, 20043522.pdf (195 kb)
    - Workbook, Chapter 10, by E. Hussein, 20043523.pdf (265 kb)
    - Workbook, Chapter 11, by E. Hussein, 20043524.pdf (281 kb)
    - Workbook, Chapter 12, by E. Hussein, 20043525.pdf (68 kb)
    28. 1997-08-01---------Jump to [Top]
  28. Reactor Core Analysis & Fuel Management, Course 1.5, by D. Rozon, Chulalongkorn University, 1997-08-01. 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, by B. Rouben, 20043401.pdf (970 kb)
    - Chapter 2 - Core Physics Aspects of Safety Analysis, by B. Rouben, 20043402.pdf (1188 kb)
    - Chapter 4 - Fuel Management in CANDU, by B. Rouben, 20043404.pdf (1542 kb)
    - Workbook, Chapter 1 - Neutronics-Thermalhydraulics Overheads, by B. Rouben, 20043406.pdf (330 kb)
    - Workbook, Chapter 2 - Core Physics Overheads, by B. Rouben, 20043407.pdf (567 kb)
    - Chapter 3 - Fuel Management and Advanced Fuel Cycles, by D. Rozon, 20043403.pdf (1436 kb)
    29. 1999-02-23---------Jump to [Top]
  29. Decay Heat Estimates for MNR, by Wm.J. Garland, McMaster University, 1999-02-23. Doc type: Other.
    Summary: Decay heat removal is essential in preventing fuel overheating and possible fission product release.  This
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Basic Equations Modelling Reactor Physics [Phase] Concept Design Safety Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - decayhe1.xls (521 kb)
    30. 1999-03-01---------Jump to [Top]
  30. CANDU Fuel Management Course, by Ben Rouben, AECL, 1999-03-01. 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, by Ben Rouben, 20031101.pdf (286 kb)
    - Basic Characteristics of the CANDU Lattice, by Ben Rouben, 20031111.pdf (186 kb)
    - The CANDU Reactivity Devices, by Ben Rouben, 20031112.pdf (147 kb)
    - Detector Systems, by Ben Rouben, 20031113.pdf (141 kb)
    - Computational Scheme for CANDU Neutronics, by Ben Rouben, 20031114.pdf (182 kb)
    - General Discussion on CANDU Fuel Management, by Ben Rouben, 20031115.pdf (125 kb)
    - Equilibrium-Core Design, by Ben Rouben, 20031116.pdf (217 kb)
    - Ongoing Reactor Operation with Channel Refuellings, by Ben Rouben, 20031117.pdf (252 kb)
    - Effects of 135Xe, by Ben Rouben, 20031118.pdf (151 kb)
    - Summary, by Ben Rouben, 20031119.pdf (61 kb)
    - Basic Characteristics of the CANDU Lattice - Figures, by Ben Rouben, 20031121.pdf (324 kb)
    - The CANDU Reactivity Devices - Figures, by Ben Rouben, 20031122.pdf (404 kb)
    - Detector Systems - Figures, by Ben Rouben, 20031123.pdf (418 kb)
    - Computational Scheme for CANDU Neutronics - Figures, by Ben Rouben, 20031124.pdf (83 kb)
    - General Discussion on CANDU Fuel Management - Figures, by Ben Rouben, 20031125.pdf (78 kb)
    - Equilibrium-Core Design - Figures, by Ben Rouben, 20031126.pdf (309 kb)
    - Ongoing Reactor Operation with Channel Refuellings - Figures, by Ben Rouben, 20031127.pdf (323 kb)
    - Effects of 135Xe - Figures, by Ben Rouben, 20031128.pdf (99 kb)
    31. 2000-03-29---------Jump to [Top]
  31. RFSP Training Course, by Benoit Arsenault, AECL, 2000-03-29. 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, by Benoit Arsenault, 20054302.pdf (381 kb)
    - Chapter 03 - The RFSP Direct-Access File, by Benoit Arsenault, 20054303.pdf (274 kb)
    - Chapter 04 - RFSP Model, by Benoit Arsenault, 20054304.pdf (400 kb)
    - Chapter 05 - Time-Average Model, by Benoit Arsenault, 20054305.pdf (322 kb)
    - Chapter 06 - Spatial Kinetics, by Benoit Arsenault, 20054306.pdf (272 kb)
    - Chapter 07 - Powderpufs-V, by Benoit Arsenault, 20054307.pdf (348 kb)
    - Chapter 08 - *Simulate and *Intrep, by Benoit Arsenault, 20054308.pdf (494 kb)
    - Chapter 09 - Flux and Power Mapping in RFSP, by Benoit Arsenault, 20054309.pdf (375 kb)
    - Chapter 10 - RRS Modelling in RFSP, by Benoit Arsenault, 20054310.pdf (275 kb)
    - Chapter 11 - *INSTANTAN, by Benoit Arsenault, 20054311.pdf (127 kb)
    - Chapter 12 - RFSP Code Development, by Benoit Arsenault, 20054312.pdf (336 kb)
    32. 2001-07-20---------Jump to [Top]
  32. Starting Up a CANDU Reactor, by D.A. Meneley, AECL, 2001-07-20. 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)
    33. 2002-01-01---------Jump to [Top]
  33. Reactor Physics Course, CNSC, 2002-01-01. 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)
    34. 2002-09-01---------Jump to [Top]
  34. Introduction to Reactor Physics, by Ben Rouben, AECL, 2002-09-01. 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, by Ben Rouben, 20040502.pdf (13610 kb)
    35. 2004-07-17---------Jump to [Top]
  35. Point kinetics simulation, by Wm.J. Garland, McMaster University, 2004-07-17. Doc type: Other.
    Summary: A point kinetics simulation using Excel spreadsheet and VBA. Easy to play with and modify.
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual Modelling Reactor Physics [Phase] Concept Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - pk.xls (465 kb)
    36. 2015-01-01---------Jump to [Top]
  36. The Essential CANDU, by Wm.J. Garland, Editor-in-Chief, UNENE, 2015-01-01. Doc type: Book.
    Summary: The Essential CANDU is a textbook about nuclear science and engineering pertaining to CANDU reactors using CANDU as the reference design. This distinguishes it from comparable textbooks based on PWR reactors. This is not a product description of CANDU per se. The book emphasizes theory over other aspects of nuclear science. This is a textbook about CANDU nuclear reactor and power plant engineering, not just the reactor physics of the core.
    Keywords: [Concept] General [SI] 30000 Reactor, Steam Generators and Auxiliaries 35000 Fuel Transfer and Storage 36000 Steam Generator Steam and Water Systems 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Chemistry General Engineering Health Physics Nuclear Engineering [Topic] Corrosion Fluid Mechanics Fuel Management Heat Transfer Important Parameters Physical Description Process Systems Radiation Reactor Physics Safety Thermalhydraulics Thermodynamics Waste Handling [Phase] Design Design Analysis Design Description Design Evolution Safety Safety Analysis [Audience] Engineer Grad Ugrad
    - A textbook on the CANDU nuclear power plant technology. press_release-Jan2016.pdf (382 kb)
    37. 2017-02-13---------Jump to [Top]
  37. Xenon and iodine kinetics simulation, by Wm.J. Garland, McMaster University, 2017-02-13. Doc type: Other.
    Summary: Xenon and iodine kinetics simulation using Excel spreadsheet and VBA. Easy to play with and modify.
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual Modelling Reactor Physics [Phase] Concept Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - Xe.xls (91 kb)
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