Jump to year -> [1950-01-01] [1956-01-01] [1967-07-01] [1969-01-02] [1971-05-01] [1972-05-25] [1974-07-01] [1980-04-01] [1980-08-01] [1981-07-01] [1985-04-24] [1987-03-01] [1987-12-01] [1989-05-01] [1990-01-01] [1990-07-01] [1992-08-01] [1993-01-01] [1993-06-01] [1995-08-01] [1996-02-01] [1996-11-01] [1996-12-05] [1997-01-01] [1997-08-01] [1997-10-01] [1998-09-22] [1999-06-21] [2000-11-01] [2001-02-01] [2002-01-01] [2002-09-01] [2003-01-01] [2003-06-24] [2003-06-30] [2004-07-17] [2005-07-01] [2010-09-07] [2011-01-01] [2017-02-13]
[Topic]: Conceptual Documents

Documents below are listed chronologically. Use the links on the left or below to filter documents by keyword. Use the links above to jump to a specific year on this page.

Number of files: 510

    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. 1956-01-01---------Jump to [Top]
  2. The Pressurized Water Reactor as a Source of Heat for Steam Power Plants, by J.M. Kay and F.J. Hutchinson, IMechE, 1956-01-01. Doc type: Paper.
    Summary: Published in the Proceedings of the Institution of Mechanical Engineers Volume 170 1956 pps 281 - 297
    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)
    3. 1967-07-01---------Jump to [Top]
  3. 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)
    4. 1969-01-02---------Jump to [Top]
  4. The Effect of Bypass Characteristics on Parallel Channel Flow Instabilities, by M.B. Carver, AECL, 1969-01-02. Doc type: Paper.
    Summary: This article is definitive because nobody could figure out why all the instability codes gave stability thresholds well below the measured threshold power in the experiments done at Canadian Westinghouse. The paper determines analytically that this is because the small bypass stabilized the experimental system as it could not maintain a constant pressure drop, which all the codes assumed at step 1.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics Mechanical Engineering [Topic] Basic Equations Collections Conceptual Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Proceedings of the Institution of Mechanical Engineers, Volume 184, 1969 BYPASS PIME_CONF_1969_184_083_02.pdf (703 kb)
    5. 1971-05-01---------Jump to [Top]
  5. Do the Universities Prepare the Type of Engineers that our Nuclear Industry Needs, by Gordon L. Brooks, AECL, 1971-05-01. Doc type: Presentation.
    Summary: Author suggests the more emphasis on systems engineering is needed in the university training of engineers, including design oriented graduate degrees.
    Keywords: [Concept] General [SI] Not assigned [Discipline] General Engineering [Topic] Conceptual [Phase] - [Audience] Engineer Grad Technician Ugrad
    - CNA Annual Meeting Panel Presentation CNA-UnivEngineers-BrooksMay1971.pdf (149 kb)
    6. 1972-05-25---------Jump to [Top]
  6. AECL Lectures on Nuclear Power Symposium, by G.A. Pon, AECL, 1972-05-25. 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, by G. Cowper, 19720102.pdf (1025 kb)
    - Lecture 3 - Power Reactor Types, by Gordon L. Brooks, 19720103.pdf (3378 kb)
    - Lecture 4 - Reactor Physics, by E. Critoph, 19720104.pdf (1755 kb)
    - Lecture 5 - Canadian Reactor Fuel, by R.D. Page, 19720105.pdf (3924 kb)
    - Lecture 8 - System Analysis, by D.B. Primeau, 19720108.pdf (1770 kb)
    - Lecture 9 - Reactor and Station Control, by E.M. Yaremy, 19720109.pdf (2715 kb)
    - Lecture 10 - Plant Layout, by R.B.V. Simmons, 19720110.pdf (3190 kb)
    - Lecture 11 - Accident Analysis, by J.D. Sainsbury, 19720111.pdf (1418 kb)
    - Lecture 12 - Licensing, by L. Pease, 19720112.pdf (1755 kb)
    - Lecture 13 - Training, by G.R. Howey, 19720113.pdf (1432 kb)
    - Lecture 14 - Canadian Power Reactor Fuel. See AECL 5609 doc#19760101 for an updated version., by R.D. Page, 19720114.pdf (2844 kb)
    - Lecture 15 - Construction, by V.A. Harrison, 19720115.pdf (3542 kb)
    - Lecture 16 - Costs, by D.L.S. Bate, 19720116.pdf (764 kb)
    - Lecture 17 - Development Potential, by W.B. Lewis, 19720117.pdf (1390 kb)
    - Lectures 6 and 7 - Heat Transport and Auxiliary Systems, by R.H. Renshaw, 19720167.pdf (2431 kb)
  7. 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)
    8. 1974-07-01---------Jump to [Top]
  8. 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)
    9. 1980-04-01---------Jump to [Top]
  9. Mathematics, Course 221, OPG, 1980-04-01. Doc type: Course.
    Summary: This course proves an introduction to two topics: equipment reliability evaluation, and calculus.
    Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept Operation [Audience] Engineer Manager
    - Full Course 20043000.pdf (3593 kb)
    - 221.00-1 Index and Objectives, 20043001.pdf (124 kb)
    - 221.00-2 Indroduction, 20043002.pdf (132 kb)
    - 421.10-4 Standard Notation, 20043003.pdf (122 kb)
    - 421.20-1 Algebra Fundamentals, 20043004.pdf (239 kb)
    - 421.40-1 Graphs, 20043005.pdf (153 kb)
    - 421.40-2 Graphing Functions, 20043006.pdf (80 kb)
    - 321.10-3 Logarithms and Exponentials, 20043007.pdf (210 kb)
    - 321.10-4 Use of Logarithmic Scaled Graph Paper, 20043008.pdf (347 kb)
    - 221.10-1 Basic Reliability Concepts, 20043009.pdf (154 kb)
    - 221.20-1 The Straight Line, 20043010.pdf (166 kb)
    - 221.20-2 The Derivative, 20043011.pdf (259 kb)
    - 221.20-3 Simple Applications of Derivatives, 20043012.pdf (127 kb)
    - 221.20-4 Differentiating Exponential Functions, 20043013.pdf (193 kb)
    - 221.20-5 The Derivative in Science and Technology, 20043014.pdf (213 kb)
    - 221.30-1 The Integral, 20043015.pdf (194 kb)
    - 221.30-2 Application of the Integral as an Infinite Sum, 20043016.pdf (371 kb)
    - 221.40-1 Appendix 1 : Review Exercises, 20043017.pdf (202 kb)
    - 221.40-2 Appendix 2 : Questions Bearing Directly on Course 221 Content from Recent AECB Nuclear General Examinations, 20043018.pdf (75 kb)
    - 221.40-3 Appendix 3 : Solving Quadratic Equations, 20043019.pdf (84 kb)
    - 221.40-4 Answers to Assignments and Review Exercises, 20043020.pdf (268 kb)
    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. 1981-07-01---------Jump to [Top]
  11. Mathematics, Nuclear Training Course 121, OPG, 1981-07-01. Doc type: Course.
    Summary: Probability and reliability concepts applied to station operation.
    Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept [Audience] Engineer Manager
    - Cover page, Table of contents, Objectives 20040101.pdf (167 kb)
    - Introduction, 20040102.pdf (194 kb)
    - Probability, 20040103.pdf (610 kb)
    - Safety Systems Analysis, 20040104.pdf (404 kb)
    - Safety Systems Analysis - Solutions to Sample Problems, 20040105.pdf (455 kb)
    - The Binomial Distribution and Power System Reliability, 20040106.pdf (302 kb)
    - The Normal Distribution and Applications, 20040107.pdf (193 kb)
    - Basic Reliability Concepts, 20040108.pdf (638 kb)
    - Operation in the Wearout Mode, 20040109.pdf (237 kb)
    - Some Modern Reliability Topics, 20040110.pdf (634 kb)
    - Appendix 1: Confidence Limits, 20040111.pdf (219 kb)
    - Appendix 2: Solutions to Assignments, 20040112.pdf (636 kb)
    12. 1985-04-24---------Jump to [Top]
  12. CANDU 6 Heat balance, by Wm.J. Garland, McMaster University, 1985-04-24. Doc type: Other.
    Summary: CANDU 6 heat balance / power calculation based on measured temperatures, pressures and flows, with error propagation estimates.
    Keywords: [Concept] - [SI] 30000 Reactor Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Conceptual; #Heat Transfer; #Modelling; #Process Systems [Phase] Concept; #Design [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - CANDU2.xls (88 kb)
    13. 1987-03-01---------Jump to [Top]
  13. Nuclear Journal of Canada, 1987 Vol 1 No. 1, by W.G. Morison, W. J. Penn, K. Hassmann, J.D. Stevenson, K. Elisson, CNS-, 1987-03-01. Doc type: Paper.
    Summary: This paper provides a summary of the designs and capabilities of principal containment systems associated with BWR, PWR, and PHWR reactors in operation and under construction in the United States, Canada, West Germany, and Sweden. The many conceptual differences in design and modes of operation following accidents are briefly described, with commentary on their evolution and alternatives considered.
    Keywords: [Concept] Component Design Details [SI] 20000 Buildings and Structures [Discipline] Civil Engineering Nuclear Engineering [Topic] Conceptual [Phase] Concept Construction Design [Audience] College Engineer Grad Ugrad
    - Containment Systems Capability NJC-1-1-08.pdf (1131 kb)
    14. 1987-12-01---------Jump to [Top]
  14. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by J.F. Lafortune, C.A. McDevitt and S. Poolpol, CNS-, 1987-12-01. Doc type: Paper.
    Summary: CANDU reactor containment buildings are checked for integrity every five years. An on-line test could be performed more often, thereby reducing long-term unavailability of the containment system. A test procedure which accounts for operational factors is proposed.
    Keywords: [Concept] Component Design Details [SI] 20000 Buildings and Structures [Discipline] Civil Engineering Nuclear Engineering [Topic] Conceptual [Phase] Concept Construction Design [Audience] College Engineer Grad Ugrad
    - Suitability Study of On-Line Leak Tests for CANDU Single-Unit Containment Buildings NJC-1-4-05.pdf (846 kb)
    - Fusion Materials Issues, by P.c. Stangeby and A.A. Haasz, NJC-1-4-08.pdf (916 kb)
    15. 1989-05-01---------Jump to [Top]
  15. 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)
    16. 1990-01-01---------Jump to [Top]
  16. Reliability for Management and Professional Staff , Course PI 21, Nuclear Training Centre, OPG, 1990-01-01. Doc type: Course.
    Summary: A six part introductory reliability course for management and professional staff.
    Keywords: [Concept] Mathematics [SI] - [Discipline] Mathematics [Topic] Basic Equations Conceptual [Phase] Concept Operation [Audience] Engineer Manager
    - Full Course 20043300.pdf (1585 kb)
    - Course Table of Contents, 20043301.pdf (219 kb)
    - PI 21.00 Intro to the Course, 20043302.pdf (104 kb)
    - PI 21.01 An Introduction to Reliability, 20043303.pdf (166 kb)
    - PI 21.02 Reliability Concepts, 20043304.pdf (384 kb)
    - PI 21.03 Process Systems, 20043305.pdf (185 kb)
    - PI 21.04 Availability of Safety Systems, 20043306.pdf (250 kb)
    - PI 21.05 Modern Reliability Techniques, 20043307.pdf (208 kb)
    - PI 21.06 Reporting and Administration, 20043308.pdf (111 kb)
  17. 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)
    18. 1990-07-01---------Jump to [Top]
  18. 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)
    19. 1992-08-01---------Jump to [Top]
  19. 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)
    20. 1993-01-01---------Jump to [Top]
  20. 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)
    21. 1993-06-01---------Jump to [Top]
  21. Materials, Nuclear Training Course 228, OPG, 1993-06-01. Doc type: Course.
    Summary: General material properties and the approach to material selection for CANDU reactors. Failure modes of materials, both mechanical and radiation induced. Pressure tube problems.
    Keywords: [Concept] Materials [SI] 31000 Reactor [Discipline] Materials Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Material Properties and Selection: Cover page, Table of contents, Introduction 20040900.pdf (140 kb)
    - Material Properties and Selection: Basic Material Properties and How They Can Be Altered, 20040901.pdf (553 kb)
    - Material Properties and Selection: Common Mechanical-Based Failure Modes, 20040902.pdf (870 kb)
    - Material Properties and Selection: Selection and Specification of Materials for Nuclear Applications, 20040903.pdf (514 kb)
    - Effect of Radiation on Materials: Radiation Damage to Materials, 20040904.pdf (547 kb)
    - Effect of Radiation on Materials: Problems with Pressure Tubes, 20040905.pdf (612 kb)
    22. 1995-08-01---------Jump to [Top]
  22. Numerical Solution of the Thermalhydraulic Conservation Equations from Fundamental Concepts to Multidimensional Analysis, by M.B. Carver, , 1995-08-01. Doc type: Report.
    Summary: This material was presented as part of a short course in Two-Phase Flow and Heat Transfer at McMaster University and is documented in report form for further reference. The discussion briefly establishes some requisite concepts of differential equation theory, and applies these to describe methods for numerical solution of the thennalhydraulic conservation equations in their various forms. The intent is to cover the general methodology without obscuring the principles with details. As a short overview of computational thermalhydraulics, the material provides an introductory foundation, so that those working on the application of thennalhydraulic codes can begin to understand the many intricacies involved without having to locate and read the references given. Those intending to work in code development will need to read and understand all the references.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Basic Equations Collections Conceptual Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Grad
    - AECL-11387, ARD-TD-550, Revision 1 (2017) to the original (1995) Carver AECL-11387[3628]-WithAddendum.pdf (6457 kb)
    23. 1996-02-01---------Jump to [Top]
  23. 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)
  24. 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)
  25. 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)
  26. Nuclear Reactor Containment, Course 3.5, by J. Daams, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 20000 Buildings and Structures [Discipline] Civil Engineering [Topic] Conceptual Modelling [Phase] Concept Design [Audience] Engineer Grad Ugrad
    - Reference 1 - Requirements for Containment Systems for Nuclear Power Plants - Doc R7 20044501.pdf (2064 kb)
    - Reference 2 - Real Time Simulation of the Containment by A. Hodhod, L. Vindigni, H. Dana, by J. Daams, 20044502.pdf (1353 kb)
    - Reference 3 - ANSI 3.5, by J. Daams, 20044503.pdf (591 kb)
    - Reference 4 - Recent Advances in Concrete Containment Vessels in Japan by T.Koroda, T.Ebine, S.Sato, M. Kato, by J. Daams, 20044504.pdf (1353 kb)
    - Workbook, Chapter 0 - Title, Objectives, by J. Daams, 20044505.pdf (38 kb)
    - Workbook, Chapter 1 - Modules A to D, by J. Daams, 20044506.pdf (1317 kb)
    - Workbook, Chapter 2 - Modules A to C, by J. Daams, 20044507.pdf (1045 kb)
    - Workbook, Chapter 3 - Modules Ato E, by J. Daams, 20044508.pdf (1723 kb)
    - Workbook, Chapter 4 - Modules A to F, by J. Daams, 20044509.pdf (1628 kb)
  27. Neutron Activation Analysis, Course 6.2, by L. Zikovsky, Chulalongkorn University, 1996-02-01. 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, by L. Zikovsky, 20052802.pdf (231 kb)
    - Chapter 02 - General Aspects in Trace Analysis, by L. Zikovsky, 20052803.pdf (198 kb)
    - Chapter 03 - Neutron Induced Reactions, by L. Zikovsky, 20052804.pdf (1636 kb)
    - Chapter 04 - Neutron Sources, by L. Zikovsky, 20052805.pdf (791 kb)
    - Chapter 05 - Growth & Decay of Radioactivity During & After Irradiation, by L. Zikovsky, 20052806.pdf (735 kb)
    - Chapter 06 - Nuclear Disintegration & Radiation Detection, by L. Zikovsky, 20052807.pdf (1459 kb)
    - Chapter 07 - Preparation of Samples & Standards, by L. Zikovsky, 20052808.pdf (1695 kb)
    - Chapter 08 - Activation Analysis with Radiochemical Separations, by L. Zikovsky, 20052809.pdf (1291 kb)
    - Chapter 09 - Analysis Without Chemical Separation, by L. Zikovsky, 20052810.pdf (893 kb)
    - Chapter 10 - Systematic Errors in Activation Analysis, by L. Zikovsky, 20052811.pdf (1410 kb)
    - Chapter 11 - Statistical Interpretation of Results, by L. Zikovsky, 20052812.pdf (1455 kb)
    - Workbook 01 - Activation Analysis = Elemental & Isotopic Analysis, by L. Zikovsky, 20052813.pdf (55 kb)
    - Workbook 02 - Structure of Chlorophyll, by L. Zikovsky, 20052814.pdf (74 kb)
    - Workbook 03 - The Nuclear Reaction & Types of Nuclear Particles Employed, by L. Zikovsky, 20052815.pdf (175 kb)
    - Workbook 04 - Irradiation Sources, by L. Zikovsky, 20052816.pdf (238 kb)
    - Workbook 05 - Quantitative Relationships, by L. Zikovsky, 20052817.pdf (115 kb)
    - Workbook 06 - Nuclear Disintegration & Radiation Detection, by L. Zikovsky, 20052818.pdf (289 kb)
    - Workbook 07 - Apparatus to Avoid Contamination, by L. Zikovsky, 20052819.pdf (37 kb)
    - Workbook 08 - Application of HAP to Activation Analysis of Urine, by L. Zikovsky, 20052820.pdf (52 kb)
    - Workbook 09 - Decay Curve of Chlorine in a Terphenyl Sample, by L. Zikovsky, 20052821.pdf (188 kb)
    - Workbook 10 - Sources of Errors in NAA, by L. Zikovsky, 20052822.pdf (224 kb)
    - Workbook 11 - Optimum Counting Time as Function of Counting Rate and Background Rate, by L. Zikovsky, 20052823.pdf (90 kb)
    - Workbook 12 - Typical analysis schemes for fluids and solids, by L. Zikovsky, 20052824.pdf (148 kb)
  28. Welding Technology, Course 7.5, by I. Grant, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: Appreciation of metal joining techniques: wleding, welding processes, weldment quality, symbols on drawings, nondestructive examination, and codes and standards.
    Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Chapter 01 - Introduction 20053401.pdf (1359 kb)
    - Chapter 02 - Specification – Covered Carbon Steel Electrodes, by I. Grant, 20053402.pdf (2022 kb)
    - Chapter 03 - Submerged Arc Welding, by I. Grant, 20053403.pdf (1118 kb)
    - Chapter 04 - Gas Metal Arc Welding, by I. Grant, 20053404.pdf (949 kb)
    - Chapter 05 - Plasma Welding, by I. Grant, 20053405.pdf (119 kb)
    - Chapter 06 - Electrical Power Sources, by I. Grant, 20053406.pdf (551 kb)
    - Chapter 07 - Welding Stainless Steel Tubing, by I. Grant, 20053407.pdf (473 kb)
    - Chapter 08 - Thermal Efficiency of Arc Welding Processes, by I. Grant, 20053408.pdf (737 kb)
    - Chapter 09 - Solidification Structures & Properties of Fusion Welds, by I. Grant, 20053409.pdf (3163 kb)
    - Chapter 10 - Prediction of Welding Distortion, by I. Grant, 20053410.pdf (618 kb)
    - Chapter 11 - Material & Fabrication Considerations for CANDU Heat Transport Systems, by I. Grant, 20053411.pdf (1808 kb)
    - Chapter 13 - Fitness for Purpose, by I. Grant, 20053413.pdf (858 kb)
    - Chapter 14 - Welding Variables Procedure Specs, by I. Grant, 20053414.pdf (965 kb)
    - Chapter 17 - Calculating Force/Unit Length on Welds, by I. Grant, 20053417.pdf (773 kb)
    - Chapter 18 - Design for Welding, by I. Grant, 20053418.pdf (569 kb)
    - Chapter 19 - Design and Construction Methods for Welded Steel Merchant Vessels, by I. Grant, 20053419.pdf (313 kb)
    - Workbook 01 - Welding Technologyes), by I. Grant, 20053420.pdf (240 kb)
    - Workbook 02 - Flux Shielded Welding Processes, by I. Grant, 20053421.pdf (549 kb)
    - Workbook 03 - Submerged Arc Welding, by I. Grant, 20053422.pdf (636 kb)
    - Workbook 04 - Gas Metal Arc Welding, by I. Grant, 20053423.pdf (497 kb)
    - Workbook 05 - Plasma Arc Welding, by I. Grant, 20053424.pdf (169 kb)
    - Workbook 06 - Welding Power Supplies & Controls, by I. Grant, 20053425.pdf (262 kb)
    - Workbook 07 - Arc Physics and Weld Pool Behaviour, by I. Grant, 20053426.pdf (281 kb)
    - Workbook 08 - Heat Flow in Welding, by I. Grant, 20053427.pdf (262 kb)
    - Workbook 09 - Metallurgical Effects of the Weld Thermal Cycle, by I. Grant, 20053428.pdf (1172 kb)
    - Workbook 10 - Distortion, Residual Stress & Post-Weld Heat Treatment, by I. Grant, 20053429.pdf (361 kb)
    - Workbook 11 - Weldability of Structural Steels, by I. Grant, 20053430.pdf (535 kb)
    - Workbook 12 - Weld Discontinuities, by I. Grant, 20053431.pdf (923 kb)
    - Workbook 13 - Inspection & Testing, by I. Grant, 20053432.pdf (327 kb)
    - Workbook 14 - Welding Qualification & Certification, by I. Grant, 20053433.pdf (480 kb)
    - Workbook 15 - Design for Welding, by I. Grant, 20053434.pdf (605 kb)
    - Workbook 16 - Weld Symbols on Drawings, by I. Grant, 20053435.pdf (531 kb)
    - Workbook 17 Static Strength of Welded Joints, by I. Grant, 20053436.pdf (443 kb)
    - Workbook 18 - Fatigue Failure of Welded Joints, by I. Grant, 20053437.pdf (557 kb)
    - Workbook 19 - Fracture of Welded Structures, by I. Grant, 20053438.pdf (539 kb)
    29. 1996-11-01---------Jump to [Top]
  29. CANDU Overiew, Course 3.2, by G. Bereznai, Chulalongkorn University, 1996-11-01. 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, by G. Bereznai, 20044202.pdf (973 kb)
    - Chapter 2 - Reactor and Moderator, by G. Bereznai, 20044203.pdf (659 kb)
    - Chapter 3 - Reactor Control, by G. Bereznai, 20044204.pdf (881 kb)
    - Chapter 4 - Heat Transport, by G. Bereznai, 20044205.pdf (755 kb)
    - Chapter 5 - Steam, Turbine and Feedwater, by G. Bereznai, 20044206.pdf (666 kb)
    - Chapter 6 - Special Safety Systems, by G. Bereznai, 20044207.pdf (1131 kb)
    - Workbook, Chapter 0 - Table of Contents, Course Introduction, by G. Bereznai, 20044208.pdf (194 kb)
    - Workbook, Chapter 1 - Modules A to E, by G. Bereznai, 20044209.pdf (3559 kb)
    - Workbook, Chapter 2 - Modules A to C, by G. Bereznai, 20044210.pdf (688 kb)
    - Workbook, Chapter 3 - Modules A to C, by G. Bereznai, 20044211.pdf (2317 kb)
    - Workbook, Chapter 4 - Modules A to D, by G. Bereznai, 20044212.pdf (1115 kb)
    - Workbook, Chapter 5 - Modules A & B, by G. Bereznai, 20044213.pdf (1110 kb)
    - Workbook, Chapter 6 - Modules A to D, by G. Bereznai, 20044214.pdf (464 kb)
    30. 1996-12-05---------Jump to [Top]
  30. Non-Destructive Testing, Course 7.2, by E. Hussein, Chulalongkorn University, 1996-12-05. Doc type: Course.
    Summary: Nondestructive testing including ultrasonics, magnetic flux leakage, eddy current, radiography, acoustic emission, and microwaves.
    Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Chapter 00 - Table of Contents 20053101.pdf (162 kb)
    - Chapter 01 - Introduction, by E. Hussein, 20053102.pdf (220 kb)
    - Chapter 02 - Ultrasonics, by E. Hussein, 20053103.pdf (670 kb)
    - Chapter 03 - Magnetic Flux Leakage, by E. Hussein, 20053104.pdf (301 kb)
    - Chapter 04 - Eddy Current (pdf 340 kb, 20 pages), by E. Hussein, 20053105.pdf (369 kb)
    - Chapter 05 - Radiography, by E. Hussein, 20053106.pdf (409 kb)
    - Chapter 06 - Acoustic Emission, by E. Hussein, 20053107.pdf (305 kb)
    - Chapter 07 - Microwaves, by E. Hussein, 20053108.pdf (145 kb)
    31. 1997-01-01---------Jump to [Top]
  31. 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)
    32. 1997-08-01---------Jump to [Top]
  32. Nuclear Weapons and Nuclear Reactors, by Dan Meneley, OPG, 1997-08-01. 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)
    33. 1997-10-01---------Jump to [Top]
  33. Reactor Mechanical Design, Course 3.6, by R.S. Porter, Chulalongkorn University, 1997-10-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Mechanical Engineering [Topic] Conceptual Physical Description [Phase] Concept Design [Audience] Engineer Grad Ugrad
    - Section 0 - Title, Table of Contents 20044601.pdf (99 kb)
    - Section 1 - Overview, Reg. Req’ts, Codes & Standards, by R.S. Porter, 20044602.pdf (531 kb)
    - Section 2 - Design Philosophy, Rationale, Key Operating Parameters, by R.S. Porter, 20044603.pdf (481 kb)
    - Section 3 - Stress Analysis of Reactor Structures, by R.S. Porter, 20044604.pdf (253 kb)
    - Section 4 - Excitation Spectra Etc., by R.S. Porter, 20044605.pdf (374 kb)
    - Section 5 - Design of Fuel Channels, by R.S. Porter, 20044606.pdf (622 kb)
    - Section 6 - Design of Reactivity Control Units, by R.S. Porter, 20044607.pdf (1181 kb)
    - Section 7 - Design of Fuel Handling System, by R.S. Porter, 20044608.pdf (1121 kb)
    - Appendix 1 - Design Loads and Load Cases for CANDU 6, by R.S. Porter, 20044609.pdf (174 kb)
    - Appendix 2 - Stresses for Design Cases, by R.S. Porter, 20044610.pdf (316 kb)
    - Appendix 3 - Finite Element Analysis, by R.S. Porter, 20044611.pdf (96 kb)
    - Appendix 4 - Seismic Behaviour of CANDU 6, by R.S. Porter, 20044612.pdf (168 kb)
    - Workbook, Chapter 1 - Figures, by R.S. Porter, 20044613.pdf (208 kb)
    - Workbook, Chapter 2 - Figures, by R.S. Porter, 20044614.pdf (778 kb)
    - Workbook, Chapter 3 - Figures, by R.S. Porter, 20044615.pdf (355 kb)
    - Workbook, Chapter 4 - Figures, by R.S. Porter, 20044616.pdf (455 kb)
    - Workbook, Chapter 5 - Figures, by R.S. Porter, 20044617.pdf (150 kb)
    - Workbook, Chapter 6 - Figures, by R.S. Porter, 20044618.pdf (964 kb)
    - Workbook, Chapter 7 - Figures, by R.S. Porter, 20044619.pdf (1006 kb)
    34. 1998-09-22---------Jump to [Top]
  34. 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, 1998-09-22. 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, by D.A. Meneley and Y.Q. Ruan, 19980102.pdf (2650 kb)
    - Moderator, HTS, Heavy Water, by D.A. Meneley and Y.Q. Ruan, 19980103.pdf (2454 kb)
    - Main Steam & T/G Systems, by D.A. Meneley and Y.Q. Ruan, 19980104.pdf (2626 kb)
    - Special Safety Systems, by D.A. Meneley and Y.Q. Ruan, 19980105.pdf (949 kb)
    - CANDU Reactor Control, by D.A. Meneley and Y.Q. Ruan, 19980106.pdf (1038 kb)
    35. 1999-06-21---------Jump to [Top]
  35. CANDU Safety - presentations in Shanghai, 1999, by V. Snell, AECL, 1999-06-21. 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, by V. Snell, 19990102.pdf (84 kb)
    - Nuclear Safety Characteristics, by V. Snell, 19990103.pdf (286 kb)
    - Thermalhydraulic Safety Characteristics of CANDU Reactors, by F.J. Doria, 19990104.pdf (1183 kb)
    - Safety Functions - Shutdown Systems, by V. Snell, 19990105.pdf (517 kb)
    - Heat Removal, by V. Snell, 19990106.pdf (767 kb)
    - Emergency Core Cooling, by V. Snell, 19990107.pdf (1182 kb)
    - Containment, by V. Snell, 19990108.pdf (699 kb)
    - Grouping and Separation, by V. Snell, 19990109.pdf (65 kb)
    - Design and Analysis Process, by F.J. Doria, 19990110.pdf (524 kb)
    - Reactivity Control, by V. Snell, 19990111.pdf (412 kb)
    - Large Loss of Coolant Accident, by F.J. Doria, 19990112.pdf (578 kb)
    - Small Loss of Coolant Accident, by F.J. Doria, 19990113.pdf (651 kb)
    - Loss of Heat Sink, by V. Snell, 19990114.pdf (199 kb)
    - Loss of Forced Circulation, by V. Snell, 19990115.pdf (1517 kb)
    - Large Loss of Coolant Accident with Coincident Loss of Emergency Core Cooling, by F.J. Doria, 19990116.pdf (554 kb)
    - Severe Core Damage Accidents, by V. Snell, 19990117.pdf (478 kb)
    - Safety Research and Development, by V. Snell, 19990118.pdf (1851 kb)
    - Safety Research and Development Programs, by F.J. Doria, 19990119.pdf (903 kb)
    - Safety Analysis Tools, by F.J. Doria, 19990120.pdf (608 kb)
    - Probabilistic Safety Analysis, by V.G. Snell and R. Jaitly, 19990121.pdf (81 kb)
    - Regulation of CANDU, by V. Snell, 19990122.pdf (1223 kb)
    - Regulatory Requirements for Design, by V. Snell, 19990123.pdf (162 kb)
    - Regulatory Requirements for Accident Analysis, by V. Snell, 19990124.pdf (60 kb)
    - CANDU 9 Design Overview, by V. Snell, 19990125.pdf (630 kb)
    - CANDU 9 Safety and Licensability, by V. Snell, 19990126.pdf (580 kb)
    36. 2000-11-01---------Jump to [Top]
  36. A Reactor Cannot Explode Like a Nuclear Bomb, by Dan Meneley, Individual Contributions, 2000-11-01. 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)
    37. 2001-02-01---------Jump to [Top]
  37. CANDU Origins and Evolution, by Gordon L. Brooks and John S. Foster, AECL, 2001-02-01. 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, by Gordon L. Brooks, 20010302.pdf (99 kb)
    - Figure of 8, by Gordon L. Brooks, 20010303.pdf (111 kb)
    - Emergency Core Cooling System, by Gordon L. Brooks, 20010304.pdf (107 kb)
    - The Origin and Evolution of the Second Shutdown System, by Gordon L. Brooks, 20010305.pdf (101 kb)
    38. 2002-01-01---------Jump to [Top]
  38. 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)
  39. Mechanical Equipment Course, CNSC, 2002-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Cover Page 20030200.pdf (86 kb)
    - , 20030201.pdf (1463 kb)
    - Vibrations, 20030202.pdf (1123 kb)
    - Valves, 20030203.pdf (2952 kb)
    - Flowsheets, 20030204.pdf (1693 kb)
  40. Basic Instrumentation and Control Course, CNSC, 2002-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Conceptual Function [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Cover Page 20030400.pdf (87 kb)
    - , 20030401.pdf (850 kb)
    - Pressure Measurement, 20030402.pdf (350 kb)
    - Flow Measurement, 20030403.pdf (391 kb)
    - Level Measurement, 20030404.pdf (162 kb)
    - Temperature Measurement, 20030405.pdf (209 kb)
    - Neutron Flux Measurement, 20030406.pdf (282 kb)
    - Control, 20030407.pdf (539 kb)
    - I&C Diagrams, 20030408.pdf (98 kb)
  41. Electrical Course, CNSC, 2002-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Cover Page 20030800.pdf (83 kb)
    - Course, 20030801.pdf (2299 kb)
    - Electrical Module - Presentation, 20030802.pdf (1468 kb)
    - Transformers Module - Presentation, 20030803.pdf (664 kb)
    - Generators Module - Presentation, 20030804.pdf (2615 kb)
    - Electrical Protection Module - Presentation, 20030805.pdf (2756 kb)
    - Électricité, 20070200.pdf (1659 kb)
  42. Principes de Science et de Fonctionnement des Réacteurs - Instrumentation Fondamentale, CNSC, 2002-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Electrical, Instrumentation & Control [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Conceptual Function [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Instrumentation Fondamentale 20070400.pdf (869 kb)
    43. 2002-09-01---------Jump to [Top]
  43. 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)
    44. 2003-01-01---------Jump to [Top]
  44. Principes de Science et de Fonctionnement des Réacteurs - Équipement Mécanique, CNSC, 2003-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Équipement Mécanique 20070700.pdf (954 kb)
    45. 2003-06-24---------Jump to [Top]
  45. CANDU Fundamentals, CNSC, 2003-06-24. 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)
  46. Principes Fondamentaux des Réacteurs CANDU - CANDU Fundamentals, CNSC, 2003-06-24. 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)
    47. 2003-06-30---------Jump to [Top]
  47. Safer Nuclear Energy for the Future, by D.A. Meneley, AECL, 2003-06-30. 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, by D.A. Meneley, 20041001.pdf (115 kb)
    - Lecture 2 - Past Design Evolution, by D.A. Meneley, 20041002.pdf (103 kb)
    - Lecture 3 - Future Design Directions, by D.A. Meneley, 20041003.pdf (136 kb)
    - Lecture 4 - The Long Term, by D.A. Meneley, 20041004.pdf (205 kb)
    48. 2004-07-17---------Jump to [Top]
  48. 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)
    49. 2005-07-01---------Jump to [Top]
  49. Nuclear Power Plant Systems and Operation, by G. Bereznai, University of Ontario Institute of Technology, 2005-07-01. 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)
    50. 2010-09-07---------Jump to [Top]
  50. 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, 2010-09-07. 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, by Blair P. Bromley, 20110202.pdf (10737 kb)
    - Supplement 1: R&D Activities for HWR Design and Safety Analysis, by Blair P. Bromley, 20110203.pdf (8280 kb)
    - Supplement 2: Alternative Concepts and Early HWR Prototypes, by Blair P. Bromley, 20110204.pdf (8403 kb)
    51. 2011-01-01---------Jump to [Top]
  51. Concept Maps, by Wm.J. Garland, CANTEACH, 2011-01-01. 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)
    52. 2017-02-13---------Jump to [Top]
  52. 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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