| | Count= 1603 | | | | | | | | | | | | | | | | | | | | | |
|  | | Page, R.D. | The Performance of Zirconium Alloy Clad UO2 Fuel for Canadian Pressurized and Boiling Water Power Reactors | | R. D. Page and A. D. Lane | AECL | 5/1/1968 | Report | 37000 Fuel | Materials Engineering | Collections, Function, Performance | Design, Development, Operation | Engineer | This paper presents the most recent information (as of 1968) on the performance of CANDU fuel, and goes on to summarize the results of an extensive irradiation program to develop fuels for boiling water cooled reactors. | 2284 KB
| 12/8/2010 11:43 AM |  Mersedeh Safa | 12/29/2017 2:30 PM | System Account | | 2010 - 12 | Page, R.D. - Selected Works |
| | | | Commissioning and Operating Experience with Canadian Nuclear Electric Stations | Paper No. A/Conf. 49/A/148 presented at the Fourth U.N. International Conference on the Peaceful Uses of Atomic Energy, Geneva, 6-16 September, 1971 | L. W. Woodhead, D. C. Milley, K. E. Elston, E.P. Horton, A. Dahlinger and R.C. Johnston | AECL | 9/6/1971 | Report | 90000 Operations and Commissioning | Nuclear Engineering | Performance | Commissioning, Operation | Engineer, Manager, Technician | | 943 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 10/10/2017 5:24 PM | Mersedeh Safa | | 2010 - 12 | Commissioning and Operating Experience with Canadian Nuclear Electric Stations |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 1 - Introduction | G.A. Pon | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 1066 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 12/22/2023 1:24 PM | It Admin | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 2 - Radiation | G. Cowper | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 1002 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 10/10/2017 5:24 PM | Mersedeh Safa | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 3 - Power Reactor Types | G.L. Brooks | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 3300 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/26/2011 12:10 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 4 - Reactor Physics | E. Critoph | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 1715 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:30 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | Page, R.D. | AECL Lectures on Nuclear Power Symposium | Lecture 5 - Canadian Reactor Fuel | R.D. Page | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Collections, Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 3833 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 12/29/2017 2:30 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 8 - System Analysis | D.B. Primeau | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 1729 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:30 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 9 - Reactor and Station Control | E.M. Yaremy | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 2652 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:32 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 10 - Plant Layout | R.B.V. Simmons | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 3116 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:32 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 11 - Accident Analysis | J.D. Sainsbury | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 1386 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:32 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 12 - Licensing | L. Pease | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 1715 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:32 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 13 - Training | G.R. Howey | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 1400 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:34 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | Page, R.D. | AECL Lectures on Nuclear Power Symposium | Lecture 14 - Canadian Power Reactor Fuel. See AECL 5609 doc#19760101 for an updated version. | R. D. Page | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Collections, Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 2779 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 12/29/2017 2:29 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 15 - Construction | V.A. Harrison | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 3460 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:34 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 16 - Costs | D.L.S. Bate | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 747 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:34 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lecture 17 - Development Potential | W.B. Lewis | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 1359 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:34 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | AECL Lectures on Nuclear Power Symposium | Lectures 6 and 7 - Heat Transport and Auxiliary Systems | R.H. Renshaw | AECL | 5/25/1972 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Design Analysis, Safety, Safety Analysis | College, Engineer, Ugrad | | 2375 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:34 PM | System Account | | 2010 - 12 | AECL Lectures on Nuclear Power Symposium |
| | | | An Introduction to the CANDU Nuclear Energy Conversion System | Table of Contents and Chapter 1: Introduction | Archie Harms | McMaster University | 5/25/1972 | Book | 03300 Nuclear Engineering | Nuclear Engineering | Basic Equations, Conceptual, Intro and Overview, Reactor Physics, Thermalhydraulics | Concept, Design, Safety | College, Engineer, Technician, Ugrad | | 608 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:37 PM | System Account | | 2010 - 12 | An Introduction to the CANDU Nuclear Energy Conversion System |
| | | | An Introduction to the CANDU Nuclear Energy Conversion System | Chapter 2: Nuclear Processes | Archie Harms | McMaster University | 5/25/1972 | Book | 03300 Nuclear Engineering | Nuclear Engineering | Basic Equations, Conceptual, Intro and Overview, Reactor Physics, Thermalhydraulics | Concept, Design, Safety | College, Engineer, Technician, Ugrad | | 482 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:37 PM | System Account | | 2010 - 12 | An Introduction to the CANDU Nuclear Energy Conversion System |
| | | | An Introduction to the CANDU Nuclear Energy Conversion System | Chapter 3: Neutron Physics | Archie Harms | McMaster University | 5/25/1972 | Book | 03300 Nuclear Engineering | Nuclear Engineering | Basic Equations, Conceptual, Intro and Overview, Reactor Physics, Thermalhydraulics | Concept, Design, Safety | College, Engineer, Technician, Ugrad | | 555 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:37 PM | System Account | | 2010 - 12 | An Introduction to the CANDU Nuclear Energy Conversion System |
| | | | An Introduction to the CANDU Nuclear Energy Conversion System | Chapter 4: Reactor Statics | Archie Harms | McMaster University | 5/25/1972 | Book | 03300 Nuclear Engineering | Nuclear Engineering | Basic Equations, Conceptual, Intro and Overview, Reactor Physics, Thermalhydraulics | Concept, Design, Safety | College, Engineer, Technician, Ugrad | | 636 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:37 PM | System Account | | 2010 - 12 | An Introduction to the CANDU Nuclear Energy Conversion System |
| | | | An Introduction to the CANDU Nuclear Energy Conversion System | Chapter 5: Reactor Dynamics | Archie Harms | McMaster University | 5/25/1972 | Book | 03300 Nuclear Engineering | Nuclear Engineering | Basic Equations, Conceptual, Intro and Overview, Reactor Physics, Thermalhydraulics | Concept, Design, Safety | College, Engineer, Technician, Ugrad | | 419 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:37 PM | System Account | | 2010 - 12 | An Introduction to the CANDU Nuclear Energy Conversion System |
| | | | An Introduction to the CANDU Nuclear Energy Conversion System | Chapter 6: Control and Operations | Archie Harms | McMaster University | 5/25/1972 | Book | 03300 Nuclear Engineering | Nuclear Engineering | Basic Equations, Conceptual, Intro and Overview, Reactor Physics, Thermalhydraulics | Concept, Design, Safety | College, Engineer, Technician, Ugrad | | 488 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:37 PM | System Account | | 2010 - 12 | An Introduction to the CANDU Nuclear Energy Conversion System |
| | | | An Introduction to the CANDU Nuclear Energy Conversion System | Chapter 7: Thermal-hydraulic Analysis | Archie Harms | McMaster University | 5/25/1972 | Book | 03300 Nuclear Engineering | Nuclear Engineering | Basic Equations, Conceptual, Intro and Overview, Reactor Physics, Thermalhydraulics | Concept, Design, Safety | College, Engineer, Technician, Ugrad | | 430 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:37 PM | System Account | | 2010 - 12 | An Introduction to the CANDU Nuclear Energy Conversion System |
| | | | An Introduction to the CANDU Nuclear Energy Conversion System | Chapter 8: Nuclear Reactor Materials | Archie Harms | McMaster University | 5/25/1972 | Book | 03300 Nuclear Engineering | Nuclear Engineering | Basic Equations, Conceptual, Intro and Overview, Reactor Physics, Thermalhydraulics | Concept, Design, Safety | College, Engineer, Technician, Ugrad | | 764 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:37 PM | System Account | | 2010 - 12 | An Introduction to the CANDU Nuclear Energy Conversion System |
| | | | An Introduction to the CANDU Nuclear Energy Conversion System | Chapter 9: Safety Analysis | Archie Harms | McMaster University | 5/25/1972 | Book | 03300 Nuclear Engineering | Nuclear Engineering | Basic Equations, Conceptual, Intro and Overview, Reactor Physics, Thermalhydraulics | Concept, Design, Safety | College, Engineer, Technician, Ugrad | | 149 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:37 PM | System Account | | 2010 - 12 | An Introduction to the CANDU Nuclear Energy Conversion System |
| | | | An Introduction to the CANDU Nuclear Energy Conversion System | Chapter 10: CANDU Reactors part 1 | Archie Harms | McMaster University | 5/25/1972 | Book | 03300 Nuclear Engineering | Nuclear Engineering | Basic Equations, Conceptual, Intro and Overview, Reactor Physics, Thermalhydraulics | Concept, Design, Safety | College, Engineer, Technician, Ugrad | | 747 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:37 PM | System Account | | 2010 - 12 | An Introduction to the CANDU Nuclear Energy Conversion System |
| | | | An Introduction to the CANDU Nuclear Energy Conversion System | Chapter 10: CANDU Reactors part 2 | Archie Harms | McMaster University | 5/25/1972 | Book | 03300 Nuclear Engineering | Nuclear Engineering | Basic Equations, Conceptual, Intro and Overview, Reactor Physics, Thermalhydraulics | Concept, Design, Safety | College, Engineer, Technician, Ugrad | | 671 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 9/15/2011 5:37 PM | System Account | | 2010 - 12 | An Introduction to the CANDU Nuclear Energy Conversion System |
| | | Page, R.D. | Canadian Power Reactor Fuel | AECL 5609, updated version of Lecture 14 of the 1974 Nuclear Power Symposium Series, doc#19720114 | R.D. Page | AECL | 3/1/1976 | Report | 03000 Engineering Science and Technology, 37000 Fuel | Materials Engineering, Mechanical Engineering | Collections, Heat Transfer, Thermalhydraulics | Design Description | College, Engineer, Technician, Ugrad | | 8380 KB
| 12/8/2010 11:43 AM | Mersedeh Safa | 12/29/2017 2:30 PM | System Account | | 2010 - 12 | Page, R.D. - Selected Works |
| | | | Safety and Licensing Philosophy and Experience at Ontario Hydro Nuclear Generating Stations | | W. Lee | OPG | 1/1/1986 | Paper | 03600 Nuclear Safety (Reactor), 10000 Site and Improvements | Nuclear Engineering | Safety | Operation, Safety | Engineer, Grad, Manager, Technician, Ugrad | As published in the Canadian Nuclear Society Bulletin Vol. 7, No. 1, 1986 with the kind permission of the CNS: The safely and licensing philosophy adopted by Ontario Hydro in establishing the need for retrofit design modifications to CANDU nuclear generating stations in operation since the early 1970's is discussed. This philosophy was developed in response to regulatory requests to determine whether this need exists in view of the more extensive safely and licensing design features incorporated in recent CANDU nuclear generating stations compared to the earlier designs. These addition features generally
reflect evolving safety knowledge and licensing requirements over time. | 2600 KB
| 5/14/2012 10:50 AM | System Account | 12/21/2017 4:46 PM | System Account | | 2012 - 05 | Safety and Licensing Philosophy and Experience at Ontario Hydro Nuclear Generating Stations |
| | | | CANDU Advanced Plutonium Burner - The Canadian Response to the ALWR | | A.R. Dastur and A.C. Mao | AECL | 5/1/1989 | Paper | 03300 Nuclear Engineering, 31000 Reactor, 37000 Fuel | Nuclear Engineering | Conceptual, Reactor Physics | Concept | Engineer, Grad, Manager, Ugrad, Vendor | 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. | 293 KB
| 5/14/2012 9:11 AM | System Account | 12/21/2017 4:34 PM | System Account | | 2012 - 05 | CANDU Advanced Plutonium Burner - The Canadian Response to the ALWR |
| | | | Chernobyl – A Canadian Perspective | | V.G. Snell and J.Q. Howieson | AECL | 8/1/1991 | Report | 31000 Reactor | Nuclear Engineering | Safety | Concept, Design, Operation, Safety | Engineer, Manager, Vendor | This brochure looks at the Canadian CANDU (CANada Deuterium Uranium) reactor to see how it stacks up in its ability to tolerate the sorts of mistakes that were made at Chernobyl. | 390 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 11/23/2011 2:36 PM | Mersedeh Safa | | 2010 - 12 | Chernobyl – A Canadian Perspective |
| | | | A Short History of the CANDU Nuclear Power System | | Gordon L. Brooks | AECL | 2/1/1993 | Paper | 03000 Engineering Science and Technology | General Engineering | Intro and Overview | Concept, Design, Operation | College, Engineer, Manager, Ugrad | This paper provides a short historical summary of the evolution of the CANDU nuclear power system with emphasis on the roles played by Ontario Hydro and private sector companies in Ontario in collaboration with Atomic Energy of Canada Limited (AECL). | 210 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 11/23/2011 2:36 PM | Mersedeh Safa | | 2010 - 12 | A Short History of the CANDU Nuclear Power System |
| | | | Fundamentals of Power Reactors | Science & Engineering Fundamentals - Part 1 | | CNSC | 1/1/1993 | Course | 03000 Engineering Science and Technology | General Engineering | Intro and Overview | Concept, Operation | College, Engineer, Ugrad | Fundamentals of power reactors covering basic nuclear processes, basic thermodynamics, thermalhydraulics, materials, nuclear systems and radiation protection. | 5791 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 11/23/2011 2:36 PM | Mersedeh Safa | | 2010 - 12 | Fundamentals of Power Reactors |
| | | | Fundamentals of Power Reactors | Science & Engineering Fundamentals - Part 2 | | CNSC | 1/1/1993 | Course | 03000 Engineering Science and Technology | General Engineering | Intro and Overview | Concept, Operation | College, Engineer, Ugrad | | 7478 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 9/15/2011 5:43 PM | System Account | | 2010 - 12 | Fundamentals of Power Reactors |
| | | | Fundamentals of Power Reactors | Nuclear Reactor System - Part 1 | | CNSC | 1/1/1993 | Course | 03000 Engineering Science and Technology | General Engineering | Intro and Overview | Concept, Operation | College, Engineer, Ugrad | | 6165 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 9/15/2011 5:46 PM | System Account | | 2010 - 12 | Fundamentals of Power Reactors |
| | | | Fundamentals of Power Reactors | Nuclear Reactor System - Part 2 | | CNSC | 1/1/1993 | Course | 03000 Engineering Science and Technology | General Engineering | Intro and Overview | Concept, Operation | College, Engineer, Ugrad | | 8118 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 9/15/2011 5:46 PM | System Account | | 2010 - 12 | |
| | | | Fundamentals of Power Reactors | Nuclear Reactor System - Part 3 | | CNSC | 1/1/1993 | Course | 03000 Engineering Science and Technology | General Engineering | Intro and Overview | Concept, Operation | College, Engineer, Ugrad | | 3703 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 9/15/2011 5:46 PM | System Account | | 2010 - 12 | Fundamentals of Power Reactors |
| | | | Fundamentals of Power Reactors | Nuclear Reactor System - Part 4 | | CNSC | 1/1/1993 | Course | 03000 Engineering Science and Technology | General Engineering | Intro and Overview | Concept, Operation | College, Engineer, Ugrad | | 4227 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 9/15/2011 5:53 PM | System Account | | 2010 - 12 | Fundamentals of Power Reactors |
| | | | Fundamentals of Power Reactors | Radiation Protection | | CNSC | 1/1/1993 | Course | 03000 Engineering Science and Technology | General Engineering | Intro and Overview | Concept, Operation | College, Engineer, Ugrad | | 5338 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 9/15/2011 5:53 PM | System Account | | 2010 - 12 | Fundamentals of Power Reactors |
| | | | Canada's Nuclear Achievement: Technical and Economic Perspectives | | T.E. RUMMERY and J.A. MACPHERSON | AECL | 7/1/1995 | Paper | 00000 General Project | History | Intro and Overview | | College, Engineer, Grad, High, Manager, Technician, Ugrad, Vendor | As published in the Canadian Nuclear Society Bulletin Vol. 16, No. 2, 1995 with the kind permission of the CNS: Canada's leading role and eminent accomplishments in nuclear development now span more than half a century. They encompass aspects as diverse as the design and sale of nuclear power reactors and research reactor technology, to the establishment of a corps of scientists, engineers and technologists with the expertise to address a wide scope of important nuclear science issues. To address the many facets of Canada's nuclear activities over the past 50 years would obviously require space far beyond that available in this paper. We have therefore limited this review to highlights we judge to be the most pertinent and interesting from an historical, technical and economic perspective. We also indicate briefly our view of the future of nuclear power in the overall context of energy needs in a world that is becoming more industrial and increasingly environmentally conscious. | 854 KB
| 3/4/2012 9:56 AM | System Account | 12/21/2017 4:15 PM | System Account | 3/4/2012 | 2012 - 03 | Canada's Nuclear Achievement: Technical and Economic Perspectives |
| | | | Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 | Comparison of PHWR and PWR | D.A. Meneley and Y.Q. Ruan | AECL | 9/22/1998 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Safety | College, Engineer, Ugrad | | 1831 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 9/15/2011 5:53 PM | System Account | | 2010 - 12 | Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 |
| | | | Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 | Reactor and Fuel Handling | D.A. Meneley and Y.Q. Ruan | AECL | 9/22/1998 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Safety | College, Engineer, Ugrad | | 2589 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 11/21/2011 8:40 PM | System Account | | 2010 - 12 | Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 |
| | | | Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 | Moderator, HTS, Heavy Water | D.A. Meneley and Y.Q. Ruan | AECL | 9/22/1998 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Safety | College, Engineer, Ugrad | | 2398 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 11/21/2011 8:40 PM | System Account | | 2010 - 12 | Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 |
| | | | Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 | Main Steam & T/G Systems | D.A. Meneley and Y.Q. Ruan | AECL | 9/22/1998 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Safety | College, Engineer, Ugrad | | 2566 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 11/21/2011 8:41 PM | System Account | | 2010 - 12 | Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 |
| | | | Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 | Special Safety Systems | D.A. Meneley and Y.Q. Ruan | AECL | 9/22/1998 | Course | 03000 Engineering Science and Technology | Nuclear Engineering | Conceptual, Function, Intro and Overview, Process Systems | Concept, Design, Safety | College, Engineer, Ugrad | | 928 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 11/21/2011 8:41 PM | System Account | | 2010 - 12 | Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 |
| | | | Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 | CANDU Reactor Control | D.A. Meneley and Y.Q. Ruan | AECL | 9/22/1998 | Course | 03000 Engineering Science and Technology | Electrical Engineering, Nuclear Engineering | Conceptual, Function, Process Systems | Concept, Design, Safety | College, Engineer, Ugrad | | 1014 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 11/21/2011 8:41 PM | System Account | | 2010 - 12 | Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | CANDU Nuclear Power Plant Design | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 1608 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Risk from Nuclear Power Plants | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 83 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Nuclear Safety Characteristics | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 281 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Thermalhydraulic Safety Characteristics of CANDU Reactors | F.J. Doria | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 1156 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Safety Functions - Shutdown Systems | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 505 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Heat Removal | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 750 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Emergency Core Cooling | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 1155 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Containment | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 683 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Grouping and Separation | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 65 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Design and Analysis Process | F.J. Doria | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 513 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Reactivity Control | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 404 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Large Loss of Coolant Accident | F.J. Doria | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 566 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Small Loss of Coolant Accident | F.J. Doria | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 637 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Loss of Heat Sink | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 196 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Loss of Forced Circulation | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 1482 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Large Loss of Coolant Accident with Coincident Loss of Emergency Core Cooling | F.J. Doria | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 542 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Severe Core Damage Accidents | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 468 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Safety Research and Development | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 1809 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Safety Research and Development Programs | F.J. Doria | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 883 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Safety Analysis Tools | F.J. Doria | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 595 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Probabilistic Safety Analysis | V.G. Snell and R. Jaitly | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 80 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Regulation of CANDU | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 1196 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Regulatory Requirements for Design | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 159 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | Regulatory Requirements for Accident Analysis | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 59 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | CANDU 9 Design Overview | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 616 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
| | | | CANDU Safety - presentations in Shanghai, 1999 | CANDU 9 Safety and Licensability | V. Snell | AECL | 6/21/1999 | Presentation | 31000 Reactor | Nuclear Engineering | Conceptual | Design, Safety | Engineer, Manager | | 567 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/25/2011 6:42 AM | System Account | | 2010 - 12 | CANDU Safety - presentations in Shanghai, 1999 |
|  | | Simulation software | Single Phase Friction Factors for MNR Thermalhydraulic Modelling | | Wm. J. Garland | McMaster University | 2/23/1999 | Report | 03200 Mechanical Engineering, 33000 Primary Heat Transport System | Mechanical Engineering | Collections, Fluid Mechanics | Concept, Design | College, Engineer, Grad, Technician, Ugrad | This report documents a review of selected literature to determine the appropriate correlations to use for McMaster Nuclear Reactor safety analysis. It was found that the standard Moody diagram (which is based on the transcendental Colebrook equation) is sufficiently accurate for pipe flow but problematic to program, whereas simple approximations do not account for pipe wall roughness. Herein, a very simple function is offered that returns an accurate estimate of f as a function of Reynolds Number, Re, and relative roughness e/D in a non-iterative fashion. In addition, a simple correction factor for channel flow is offered. | 522 KB
| 2/13/2019 2:56 PM | System Account | 2/13/2019 2:56 PM | System Account | | 2019 - 02 | Simulation Software |
| | | | * How and Why is CANDU designed the way it is | | Bill Garland | CANTEACH | 12/1/2000 | Paper | 03000 Engineering Science and Technology | Nuclear Engineering | Intro and Overview | Concept, Design | High | Why we need nuclear power; A look at the nuclear reactor in a nutshell; The engineering approach - CANDUs are engineered systems, typified by functional decomposition; A quick overview of CANDU vs PWR vs BWR and others. | 801 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:42 PM | System Account | | 2010 - 12 | * How and Why is CANDU designed the way it is |
| | | | A Reactor Cannot Explode Like a Nuclear Bomb | | Dan Meneley | Individual Contributions | 11/1/2000 | Lecture | 03600 Nuclear Safety (Reactor) | Nuclear Engineering | Conceptual, Performance | Concept, Design, Operation, Safety | College, Engineer, Manager, Technician, Vendor | | 233 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 9/15/2011 7:32 PM | System Account | | 2010 - 12 | A Reactor Cannot Explode Like a Nuclear Bomb |
| | | | Safety Analysis Technology: Evolution, Revolution and the Drive to Re-Establish Margins | | John C Luxat | OPG | 9/13/2000 | Presentation | 31000 Reactor | Nuclear Engineering | Performance | Commissioning, Design, Operation, Safety | Engineer, Technician | A historical perspective of the evolution of safety analysis technology at OPG is presented below. The key elements of the new safety analysis methodology are then described together with its relationship to other components of Canadian nuclear safety technology. This development is placed in context with similar work being conducted in the international Light Water Reactor (LWR) community. | 251 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 9/26/2011 2:10 PM | System Account | | 2010 - 12 | Safety Analysis Technology: Evolution, Revolution and the Drive to Re-Establish Margins |
| | | | The CANDU System: A Canadian Achievement | | Adam McLean | University of Toronto | 11/15/2000 | Presentation | 00000 General Project | General Engineering | Intro and Overview | Operation | College | A presentation on CANDU, its history and its achievements. | 32 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 11/23/2011 2:38 PM | Mersedeh Safa | | 2010 - 12 | The CANDU System: A Canadian Achievement |
| | | | A Human Turning Point – Nuclear Energy | | Dan Meneley | Individual Contributions | 3/6/2001 | Lecture | 00000 General Project | General Engineering | Intro and Overview | Operation | College | | 531 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 9/15/2011 7:32 PM | System Account | | 2010 - 12 | A Human Turning Point – Nuclear Energy |
| | | | Fuel for the Next Millennia | | Dan Meneley | AECL | 3/6/2001 | Presentation | 37000 Fuel | Nuclear Engineering | Fuel Management | Concept, Design, Operation | Engineer, Manager | | 885 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 9/15/2011 7:32 PM | System Account | | 2010 - 12 | Fuel for the Next Millennia |
| | | | CANDU Origins and Evolution | Overview | Gordon L.Brooks and John S. Foster | AECL | 2/1/2001 | Paper | 03000 Engineering Science and Technology, 31000 Reactor | General Engineering, Nuclear Engineering | Conceptual, Important Parameters, Intro and Overview | Concept, Design, Design Evolution | Manager | 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. | 130 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:41 PM | System Account | | 2010 - 12 | CANDU Origins and Evolution |
| | | | CANDU Origins and Evolution | Why CANDU | Gordon L.Brooks | AECL | 2/1/2001 | Paper | 03000 Engineering Science and Technology, 31000 Reactor | General Engineering, Nuclear Engineering | Conceptual, Important Parameters, Intro and Overview | Concept, Design, Design Evolution | Manager | This monograph is intended to answer, in simple terms, the question of "Why CANDU"; that is, why the CANDU nuclear power reactor is the way it is and why it differs from other commercially developed nuclear power reactors, particularly the light water type of reactors originally developed in the United States and now used in many countries. | 98 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:44 PM | System Account | | 2010 - 12 | CANDU Origins and Evolution |
| | | | CANDU Origins and Evolution | Figure of 8 | Gordon L.Brooks | AECL | 2/1/2001 | Paper | 03000 Engineering Science and Technology, 33100 Main Heat Transport System | Nuclear Engineering | Conceptual, Important Parameters, Intro and Overview | Concept, Design, Design Evolution | Manager | This monograph discusses the origins and early evolution of the basic "figure of 8" heat transport system arrangement that has been employed in most CANDU reactors to date. | 110 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:44 PM | System Account | | 2010 - 12 | CANDU Origins and Evolution |
| | | | CANDU Origins and Evolution | Emergency Core Cooling System | Gordon L.Brooks | AECL | 2/1/2001 | Paper | 03000 Engineering Science and Technology, 34000 Auxiliary System | Nuclear Engineering | Conceptual, Important Parameters, Intro and Overview | Design, Design Evolution | Manager | This monograph discusses the origins and evolution of the emergency core cooling systems provided for CANDU reactors. | 105 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:44 PM | System Account | | 2010 - 12 | CANDU Origins and Evolution |
| | | | CANDU Origins and Evolution | The Origin and Evolution of the Second Shutdown System | Gordon L.Brooks | AECL | 2/1/2001 | Paper | 03000 Engineering Science and Technology, 31000 Reactor | Nuclear Engineering | Conceptual, Important Parameters, Intro and Overview | Concept, Design, Design Evolution | Manager | The historical origins of the second shutdown system, as applied to Bruce-A and all subsequent CANDU reactors, are discussed in two parts. The first deals with the evolution of licensing requirements for a second shutdown system and the second deals with the origins of the fast liquid poison injection system chosen for the second shutdown system.
| 100 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:44 PM | System Account | | 2010 - 12 | CANDU Origins and Evolution |
| | | | Starting Up a CANDU Reactor | Abbreviated Step-by Step Procedure | Dan Meneley | AECL | 7/20/2001 | Paper | 90000 Operations and Commissioning | Nuclear Engineering | Reactor Physics | Operation | College, Engineer, Manager, Technician, Ugrad | 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. | 93 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 11/23/2011 2:40 PM | Mersedeh Safa | | 2010 - 12 | Starting Up a CANDU Reactor |
| | | | CANDU Poster | | | AECL | 1/1/2001 | Presentation | 03000 Engineering Science and Technology | General Engineering | Intro and Overview | Operation | High | Handy overview poster showing the major components and concepts of CANDU. | 924 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 11/23/2011 2:41 PM | Mersedeh Safa | | 2010 - 12 | CANDU Poster |
| | | | CANDU - How a Reactor Works | | | AECL | 1/2/2001 | Presentation | 03000 Engineering Science and Technology | General Engineering | Intro and Overview | Operation | High | A handy overview poster showing how a CANDU reactor works. | 565 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:44 PM | System Account | | 2010 - 12 | CANDU - How a Reactor Works |
| | | | Why a Chernobyl-type accident cannot happen in CANDU reactors | | | AECL | 1/3/2001 | Presentation | 31000 Reactor | Nuclear Engineering | Safety | Concept, Design, Operation, Safety | Engineer, Manager, Vendor | | 1003 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 9/15/2011 7:32 PM | System Account | | 2010 - 12 | Why a Chernobyl-type accident cannot happen in CANDU reactors |
| | | | Reactor Physics Course | Cover Page | | CNSC | 1/1/2002 | Course | 31000 Reactor | Nuclear Engineering, Physics | Conceptual, Reactor Physics | Concept, Design | Engineer, Ugrad | | 86 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:34 PM | System Account | | 2010 - 12 | Reactor Physics Course |
| | | | Reactor Physics Course | | | CNSC | 1/1/2002 | Course | 31000 Reactor | Nuclear Engineering, Physics | Conceptual, Reactor Physics | Concept, Design | Engineer, Ugrad | This Training Manual assumes prior knowledge of Nuclear Theory. It extends this information into a discussion of Reactor Physics, particularly as it relates to CANDU reactors. The course begins with the general principles of reactor configuration required to maintain a selfsustaining chain reaction. It continues with reactor dynamics (in both the critical and subcritical core), reactivity feedback effects (temperature effects, fission product poisoning, and fuel burnup), and ends with operational considerations (at low and high power). | 1435 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:34 PM | System Account | | 2010 - 12 | Reactor Physics Course |
| | | | Reactor Physics Course | Review questions (English) | | CNSC | 1/1/2002 | Course | 31000 Reactor | Nuclear Engineering, Physics | Conceptual, Reactor Physics | Concept, Design | Engineer, Ugrad | | 136 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:34 PM | System Account | | 2010 - 12 | Reactor Physics Course |
| | | | Reactor Physics Course | Review questions (French) | | CNSC | 1/1/2002 | Course | 31000 Reactor | Nuclear Engineering, Physics | Conceptual, Reactor Physics | Concept, Design | Engineer, Ugrad | | 140 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:34 PM | System Account | | 2010 - 12 | Reactor Physics Course |
| | | | Mechanical Equipment Course | Cover Page | | CNSC | 1/1/2002 | Course | | Mechanical Engineering | Conceptual | Concept, Design, Operation | College, Engineer, Ugrad | | 85 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:33 PM | System Account | | 2010 - 12 | Mechanical Equipment Course |
| | | | Mechanical Equipment Course | | | CNSC | 1/1/2002 | Course | | Mechanical Engineering | Conceptual | Concept, Design, Operation | College, Engineer, Ugrad | This course covers the following areas pertaining to mechanical equipment: Vibrations, Valves, Steam Traps, Flow sheets | 1430 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:33 PM | System Account | | 2010 - 12 | Mechanical Equipment Course |
| | | | Mechanical Equipment Course | Vibrations | | CNSC | 1/1/2002 | Course | | Mechanical Engineering | Conceptual | Concept, Design, Operation | College, Engineer, Ugrad | | 1098 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:33 PM | System Account | | 2010 - 12 | Mechanical Equipment Course |
| | | | Mechanical Equipment Course | Valves | | CNSC | 1/1/2002 | Course | | Mechanical Engineering | Conceptual | Concept, Design, Operation | College, Engineer, Ugrad | | 2883 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:33 PM | System Account | | 2010 - 12 | Mechanical Equipment Course |
| | | | Mechanical Equipment Course | Flowsheets | | CNSC | 1/1/2002 | Course | | Mechanical Engineering | Conceptual | Concept, Design, Operation | College, Engineer, Ugrad | | 1654 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 4:33 PM | System Account | | 2010 - 12 | Mechanical Equipment Course |
| | | | Materials Course | Cover Page | | CNSC | 1/1/2002 | Course | | Materials Engineering | Corrosion, Radiation | Concept, Design, Operation | College, Engineer, Ugrad | This course covers the following areas pertaining to Mechanical Properties: Mechanical and Thermal Stress, Corrosion, Pressure Tubes and Fuel Bundles | 85 KB
| 12/8/2010 11:44 AM | Mersedeh Safa | 12/21/2017 5:02 PM | System Account | | 2010 - 12 | Materials Course |
