|
Jump to year ->
[1950-01-01]
[1958-09-01]
[1960-01-01]
[1961-04-01]
[1961-05-01]
[1961-09-18]
[1962-09-01]
[1962-09-24]
[1962-11-01]
[1962-11-22]
[1963-07-01]
[1964-01-01]
[1964-11-01]
[1964-12-01]
[1965-01-01]
[1966-11-01]
[1968-01-01]
[1968-09-01]
[1968-11-01]
[1969-01-01]
[1971-05-01]
[1971-09-06]
[1972-05-25]
[1976-03-01]
[1976-09-01]
[1977-04-01]
[1980-11-01]
[1982-01-01]
[1982-02-01]
[1985-04-24]
[1986-01-01]
[1987-03-01]
[1987-06-01]
[1987-09-01]
[1987-12-01]
[1990-01-01]
[1992-02-01]
[1992-06-01]
[1992-07-01]
[1993-01-01]
[1993-02-01]
[1993-04-01]
[1994-07-01]
[1994-09-01]
[1995-07-01]
[1996-02-01]
[1996-08-01]
[1997-11-01]
[1998-09-18]
[1999-02-23]
[2000-06-01]
[2000-09-13]
[2000-11-01]
[2001-06-01]
[2001-07-20]
[2002-05-01]
[2003-02-01]
[2003-05-10]
[2003-06-01]
[2004-07-17]
[2009-05-30]
[2011-01-01]
[2012-01-25]
[2017-02-13]
[2017-12-27]
[Audience]: Technician 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: 521
1950-01-01---------Jump to [Top]
-
Dyke, J.M. - Selected Works, by J.M. Dyke, Individual Contributions, 1950-01-01. Doc type: Essay.
Summary: John M. Dyke B.A.Sc., P.Eng: John was involved in steam generator design for 35 years, from 1945 to 1980. He lead the design team for the Pickering A nuclear station in the mid 1960s. They were the first with internal economizer and integral steam drums. The 48 steam generators at this four-reactor station have had exemplary performance. John obtained his B.A.Sc. in Mechanical Engineering from the University of Toronto in 1943 and joined the Royal Canadian Navy Volunteer Reserve as an Engineering Officer posted with the Royal Navy doing convoy duty in the Atlantic and the Mediterranean. When he returned to Canada he worked at the Naval Research Establishment in Halifax developing anti-acoustic torpedo gear. Coincidentally, these were parallel rods that vibrated in water streams. After the war John did steam boiler engineering at several firms and became Chief Engineer of Dominion Bridge’s new boiler department in 1958. Here he attended a special course on nuclear design and submitted bids for early nuclear steam generators and reheaters. In 1964 he joined Babcock and Wilcox Canada, first as a project engineer on fossil-fired boilers and then to head up the new nuclear steam generating section where they developed a new 500 MWe design for Pickering A. He is a registered professional engineer with the province of Ontario. He has been honored by the American Society of Mechanical Engineering as a life member for outstanding lifetime achievement. The Canadian Nuclear Association also honored him with their Outstanding Contribution Award for designing the steam generators used in CANDU stations. John retired from BWC in 1980.
Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Design Operation [Audience] Engineer Grad Manager Technician Ugrad
- Introduction Dyke-intro.pdf (291 kb)
-
Page, R.D. - Selected Works, by R.D. Page, AECL, 1950-01-01. Doc type: Essay.
Summary: Ron Page (1925-2014). In 1958, Ron was posted on attachment to Atomic Energy of Canada Ltd.(AECL) at the Chalk River Nuclear Laboratories from Orenda. In September 1959, he joined Atomic Energy of Canada Ltd. to form Power Reactor Fuel Engineering. He was responsible for all the development of CANDU nuclear power reactor fuel. (NPD-2, Douglas Point, Indian RAPP I, Pickering A&B, Gentilly-1 BLW, Bruce A&B, Gentilly-2 600 MWe reactors). In 1970, he was transferred to AECL Engineering Co., Sheridan Park near Toronto, Ont. to form a new branch of Fuel Engineering. In 1980 he became the R & D program manager for all the combined AECL/Ontario Hydro R&D programs and later CANDU Owners Group (COG) R&D programs. He was a Associate Fellow of the Royal Aeronautical Society, a Professional Engineer of Ontario, a director of the Canadian Aviation Historical Society, a member of AECL CANDU Retirees Association, Federal Superannuates National Association and a member of CANDU Origins and Evolution working group. He retired in January 1987.
Keywords: [Concept] - [SI] 37000 Fuel [Discipline] - [Topic] - [Phase] - [Audience] College Engineer Grad High Manager Technician Ugrad
- Introduction Page-intro.pdf (320 kb)
-
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)
1958-09-01---------Jump to [Top]
-
NPD-2 Design Description, OPG, 1958-09-01. Doc type: Report.
Summary: This booklet presents a detailed design description of the NPD-2 station, a joint project of AECL, CGE and the Hydro-Electric Power Commission of Ontario.
Keywords: [Concept] General [SI] 00000 General Project 30000 Reactor, Steam Generators and Auxiliaries 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Description [Audience] College Engineer High Technician Ugrad
- Canada's First Nuclear Power Station CGE-NPD-DD-Sept1958.pdf (2766 kb)
1960-01-01---------Jump to [Top]
-
Nuclear Power Demonstration, OPG, 1960-01-01. Doc type: Other.
Summary: Cutaway drawings and a flow diagram of NPD-2. Date unknown.
Keywords: [Concept] General [SI] 00000 General Project [Discipline] General Engineering [Topic] Layout [Phase] Design [Audience] College High Technician
- a brochure NPD-brochure.pdf (7439 kb)
1961-04-01---------Jump to [Top]
-
NDP-2 Systems - Calandria Assembly, Course T.T.01-312, OPG, 1961-04-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heavy Water Physical Description Process Systems [Phase] Design [Audience] College Engineer Technician Ugrad
- NPD-TT01-312-1961.pdf (2972 kb)
1961-05-01---------Jump to [Top]
-
NDP-2 Systems - Moderator, Course T.T.4-4.320, OPG, 1961-05-01. Doc type: Course.
Summary:
Keywords: [Concept] General [SI] 32000 Moderator System [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] Design [Audience] College Engineer Technician Ugrad
- General description only, 3 pages. NPD-TT4-4-320-1961.pdf (138 kb)
1961-09-18---------Jump to [Top]
-
NPD, a Description of, by J.L Olsen, OPG, 1961-09-18. Doc type: Presentation.
Summary: Nuclear Power Demonstration. An illustrated talk presented at the Seventh AECL Symposium on Atomic Energy, Chalk River, September 18, 1961.
Keywords: [Concept] General [SI] 00000 General Project 30000 Reactor, Steam Generators and Auxiliaries 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Description [Audience] College Engineer High Technician Ugrad
- Canada's First Nuclear Power Station CAPD10--Sept1961NPD-Description.pdf (5637 kb)
1962-09-01---------Jump to [Top]
-
Reactor Loops at Chalk River, by Ronald Needham, AECL, 1962-09-01. Doc type: Paper.
Summary: Description of the Chalk River NRX and NRU in-reactor test loops for materials testing under simulated reactor power conditions.
Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Materials Engineering Nuclear Engineering [Topic] Radiation Reactor Physics Thermalhydraulics [Phase] Concept [Audience] Engineer Technician Ugrad
- CRL-Loops1962.pdf (1547 kb)
-
NDP Startup Trouble Spots, OPG, 1962-09-01. Doc type: Paper.
Summary: Short report on the main trouble spots in NPD startup.
Keywords: [Concept] Generic Design Issues [SI] 90000 Operations and Commissioning [Discipline] General Engineering [Topic] Performance [Phase] Commissioning [Audience] Engineer Manager Technician
- Pumps, instrument tubing main trouble spots NDP-Startup1962.pdf (92 kb)
1962-09-24---------Jump to [Top]
-
Douglas Point Project, by D.L.S. Bate, OPG, 1962-09-24. Doc type: Report.
Summary: Description of the progress in designing and constructing the Douglas Point Project, a 200 MW nuclear power plant.
Keywords: [Concept] General [SI] 00000 General Project [Discipline] General Engineering [Topic] Intro and Overview [Phase] Construction Design [Audience] Engineer Manager Technician
- Status Report DP-Status-Sept1962.pdf (2380 kb)
1962-11-01---------Jump to [Top]
-
NPD Nucleonics Description, by Nucleonics, OPG, 1962-11-01. Doc type: Other.
Summary:
Keywords: [Concept] - [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] - [Phase] Design Operation [Audience] College Engineer Grad Manager Technician Ugrad
- NPD on the Line - a foldout description with layout diagrams and design date. NDP-NucleonicsNov1962.PDF (4922 kb)
1962-11-22---------Jump to [Top]
-
NPD Generatig Station Index, OPG, 1962-11-22. Doc type: Other.
Summary: Numerical system index and subject index for the NPD nuclear power plant.
Keywords: [Concept] General [SI] 00000 General Project [Discipline] General Engineering [Topic] Index [Phase] Concept [Audience] Engineer Technician
- System Index, General Subject Index NPD-Index-1962.pdf (231 kb)
1963-07-01---------Jump to [Top]
-
NDP-2 Systems - Reactor, Course T.T.4-5.310, OPG, 1963-07-01. Doc type: Course.
Summary:
Keywords: [Concept] General [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] Design [Audience] College Engineer Technician Ugrad
- General description only, 9 pages. NPD-TT4-5-310-1963.pdf (511 kb)
1964-01-01---------Jump to [Top]
-
NDP Systems - I&C General - Annunciation, Course T.T.0-5.603, OPG, 1964-01-01. Doc type: Course.
Summary:
Keywords: [Concept] Electrical, Instrumentation & Control [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Intro and Overview [Phase] Design [Audience] College Engineer Technician Ugrad
- NPD-TT-0-5-603-1964.pdf (293 kb)
1964-11-01---------Jump to [Top]
-
Turbine, Generator and Auxiliaries, Course 3-3.4, Nuclear Electric GS Technical Training Course, by D.Dueck, OPG, 1964-11-01. Doc type: Course.
Summary:
Keywords: [Concept] Mechanical [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Full course, sections 1 to 9 NEGS-TT3-3-4-1964.pdf (6102 kb)
-
Turbine, Generator and Auxiliaries, Course 4-3.4, Nuclear Electric GS Technical Training Course, by D.Dueck, OPG, 1964-11-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Full course, sections 1 to 7 NEGS-TT4-3-4-1964.pdf (2375 kb)
1964-12-01---------Jump to [Top]
-
Turbine, Generator and Auxiliaries, Course 2-3.4, Nuclear Electric GS Technical Training Course, by D.Dueck, OPG, 1964-12-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Full course, sections 1 to 10 NEGS-TT2-3-4-1964.pdf (7516 kb)
1965-01-01---------Jump to [Top]
-
Turbine, Generator and Auxiliaries, Course 1-3.4, Nuclear Electric GS Technical Training Course, by Dick Dueck, OPG, 1965-01-01. Doc type: Course.
Summary:
Keywords: [Concept] Mechanical [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Full course, sections 1 to 7 NEGS-TT1-3-4-1965.pdf (4837 kb)
-
NDP Systems - Reactor Boiler Control, Course T.T.0-5.637.1, by S.G. Horton, OPG, 1965-01-01. Doc type: Course.
Summary:
Keywords: [Concept] Electrical, Instrumentation & Control [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Basic Equations Physical Description Process Systems [Phase] Concept Design Operation [Audience] College Engineer Technician Ugrad
- Reactor Boiler Regulating System NPD-TT-0-5-637-1-1965.pdf (1542 kb)
1966-11-01---------Jump to [Top]
-
Reactor, Boiler and Auxiliaries, Course 133, Nuclear Training Center, OPG, 1966-11-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
- Full Course 20050900.pdf (10930 kb)
- 133.00-00 Index, 20050901.pdf (252 kb)
- 133.10-01 The Function of a Reactor, 20050902.pdf (262 kb)
- 133.10-02 Reactor Classification - Fast and Thermal Reactors, 20050903.pdf (306 kb)
- 133.10-03 Reactor Classification - Types of Thermal Reactors, 20050904.pdf (791 kb)
- 133.10-04 Reactor Construction, 20050905.pdf (622 kb)
- 133.20-01 Moderator Requirements, 20050906.pdf (227 kb)
- 133.20-02 Moderator Materials Properties and Comparison, 20050907.pdf (459 kb)
- 133.20-03 Moderator System and Equipment Considerations, 20050908.pdf (930 kb)
- 133.30-01 Heat Transport Fluid Requirements, 20050909.pdf (401 kb)
- 133.30-02 Heat Transport Fluid Comparisons, 20050910.pdf (600 kb)
- 133.30-03 Main Circuit Considerations, 20050911.pdf (845 kb)
- 133.30-04 Auxiliary Circuits, 20050912.pdf (708 kb)
- 133.40-01 Reflector Systems, 20050913.pdf (367 kb)
- 133.40-02 Shield Cooling Systems, 20050914.pdf (318 kb)
- 133.50-01 Functions of Reactivity Mechanisms, 20050915.pdf (191 kb)
- 133.50-02 Comparisons of Reactivity Mechanisms, 20050916.pdf (711 kb)
- 133.62-01 Upgrading Requirements and Processes, 20050917.pdf (170 kb)
- 133.62-02 Principles of Isotope Separation, 20050918.pdf (126 kb)
- 133.62-03 The Distillation Upgrading Process, 20050919.pdf (258 kb)
- 133.62-04 The Electrolytic Process, 20050920.pdf (149 kb)
- 133.62-05 Common Problems, 20050921.pdf (183 kb)
- 133.71-01 General Fuel Considerations, 20050922.pdf (190 kb)
- 133.71-02 Fuel Preparation and Manufacture, 20050923.pdf (233 kb)
- 133.71-03 Canadian Designs and Their Performance, 20050924.pdf (294 kb)
- 133.91-01 Safety Standards and Safety Measures, 20050925.pdf (198 kb)
- 133.91-02 Emergency Injection and Containment Systems, 20050926.pdf (160 kb)
- 133.91-03 Safety System Performance, 20050927.pdf (199 kb)
- 133.92-01Chemistry of Water Circuits, 20050928.pdf (940 kb)
1968-01-01---------Jump to [Top]
-
NPD Systems - Fuel Handling System, Course 053, by Staff, OPG, 1968-01-01. Doc type: Course.
Summary: This manual is issued as an indoctrination course on the N.P.D. Fuel Handling System. The successful completion of the course and examinations will, however, be required as partial N04, NC4 or NM4 qualifications.
Keywords: [Concept] Mechanical [SI] 35000 Fuel Transfer and Storage [Discipline] Mechanical Engineering [Topic] Fuel Management Physical Description Process Systems [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Reactor Boiler and Auxiliaries Fuel Handling System NPD053-352.pdf (11616 kb)
1968-09-01---------Jump to [Top]
-
Basic Course for Radiation Surveyors and Contamination Monitors of the Radiation and Industrial Safety Branch, by J.H. Fenn and W.R. Bush, AECL, 1968-09-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Design Operation [Audience] Engineer Grad Technician Ugrad
- 20100200.pdf (6970 kb)
1968-11-01---------Jump to [Top]
-
Reactor Boiler and Auxiliaries, Course 433, Nuclear Training Centre, OPG, 1968-11-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
- Full Course 20051200.pdf (1786 kb)
- 433.00-00 Index, 20051201.pdf (241 kb)
- 433.10-01 Nuclear Power, 20051202.pdf (121 kb)
- 433.10-02 Power Reactor Construction, 20051203.pdf (179 kb)
- 433.20-01 Moderator Systems, 20051204.pdf (141 kb)
- 433.30-01 Heat Transport Systems, 20051205.pdf (239 kb)
- 433.40-01 Auxiliary Circuits, 20051206.pdf (205 kb)
- 433.50-01 Fuel, 20051207.pdf (247 kb)
- 433.50-02 Fuel Handling and Storage, 20051208.pdf (172 kb)
- 433.60-01 Boiler Steam and Water Systems, 20051209.pdf (291 kb)
1969-01-01---------Jump to [Top]
-
Pickering Generating Station Design Description, OPG, 1969-01-01. Doc type: Report.
Summary:
Keywords: [Concept] Overview [SI] 00000 General Project 10000 Site and Improvements 20000 Buildings and Structures 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries 50000 Electric Power Systems 60000 Instrumentation and Control [Discipline] General Engineering Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Operation Safety [Audience] College Engineer Technician Ugrad
- OH-PickeringDD1969.pdf (23589 kb)
1971-05-01---------Jump to [Top]
-
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)
1971-09-06---------Jump to [Top]
-
Commissioning and Operating Experience with Canadian Nuclear Electric Stations, by L. W. Woodhead, D. C. Milley, K. E. Elston, E.P. Horton, A. Dahlinger and R.C. Johnston, AECL, 1971-09-06. Doc type: Report.
Summary:
Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Performance [Phase] Commissioning Operation [Audience] Engineer Manager Technician
- Paper No. A/Conf. 49/A/148 presented at the Fourth U.N. International Conference on the Peaceful Uses of Atomic Energy, Geneva, 6-16 September, 1971 19710101.pdf (965 kb)
1972-05-25---------Jump to [Top]
-
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)
1976-03-01---------Jump to [Top]
-
Canadian Power Reactor Fuel, by R.D. Page, AECL, 1976-03-01. Doc type: Report.
Summary:
Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 37000 Fuel [Discipline] Materials Engineering Mechanical Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Design Description [Audience] College Engineer Technician Ugrad
- AECL 5609, updated version of Lecture 14 of the 1974 Nuclear Power Symposium Series, doc#19720114 19760101.pdf (8580 kb)
1976-09-01---------Jump to [Top]
-
Turbine, Generator and Auxiliaries, Course 134, Nuclear Training Centre, OPG, 1976-09-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Full Course 20051100.pdf (3779 kb)
- 134.00-00 Index and Objectives, 20051101.pdf (355 kb)
- 134.00-01 Turbine Theory, 20051102.pdf (793 kb)
- 134.00-02 Turbine Operational Performance, 20051103.pdf (534 kb)
- 134.00-03 Turbine Operational Problems, 20051104.pdf (554 kb)
- 134.00-04 Turbine Start-Up, 20051105.pdf (365 kb)
- 134.00-05 Factors Limiting Startup and Rates of Loading, 20051106.pdf (561 kb)
- 134.00-06 Reliability and Testing Requirements, 20051107.pdf (253 kb)
- 134.00-07 Maintenance, 20051108.pdf (404 kb)
1977-04-01---------Jump to [Top]
-
Reactor, Boilers and Auxiliaries, Nuclear Training Course 133, OPG, 1977-04-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
- Cover Page, Table of Contents, Basic Moderator Requirements 20041301.pdf (194 kb)
- Moderator System & Equipment, 20041302.pdf (911 kb)
- Basic Heat Transport Fluid Requirements, 20041303.pdf (274 kb)
- Main Heat Transport Circuit Considerations, 20041304.pdf (1476 kb)
- Auxiliary PHT System Features, 20041305.pdf (477 kb)
- Shield Systems, 20041306.pdf (446 kb)
- Annulus Gas System, 20041307.pdf (97 kb)
- Containment Systems, 20041308.pdf (522 kb)
- Reactivity Mechanisms, 20041309.pdf (233 kb)
- Practical Reactivity Mechanisms, 20041310.pdf (161 kb)
- Choice of Reactivity Mechanisms, 20041311.pdf (855 kb)
- Fuel - Design and Manufacturing Features, 20041312.pdf (447 kb)
- Fuel Performance and Operating Experience, 20041313.pdf (213 kb)
1980-11-01---------Jump to [Top]
-
Electrical Systems, Course 135, Nuclear Training Centre, OPG, 1980-11-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Full Course 20051300.pdf (1710 kb)
- 135.00-00 Index and Objectives, 20051301.pdf (279 kb)
- 135.01-01 Introduction to Symmetrical Components and Unbalanced Current, 20051302.pdf (185 kb)
- 135.02-01 Unbalanced Currents: Their Effects, 20051303.pdf (252 kb)
- 135.03-01 Further Examples of Electrical Protective Relays, 20051304.pdf (418 kb)
- 135.04-01 Composite Electrical Protective Schemes: Part 1, 20051305.pdf (344 kb)
- 135.05-01 Composite Electrical Protective Schemes: Part 2, 20051306.pdf (257 kb)
1982-01-01---------Jump to [Top]
-
Electrical Equipment, Course 230.2, Nuclear Training Center, OPG, 1982-01-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Module 230.00 Introduction and Table of Contents 20050801.pdf (250 kb)
- Module 230.21-1 Station Batteries and Battery Charges, 20050802.pdf (348 kb)
- Module 230.22-1 Switchgear - Busbars and Cables, 20050803.pdf (188 kb)
- Module 230.22-2 Switchgear - Motor Control Centres, 20050804.pdf (217 kb)
- Module 230.22-3 Switchgear - Air Circuit Breakers, 20050805.pdf (203 kb)
- Module 230.22-4 Switchgear - Vacuum Contactors, 20050806.pdf (80 kb)
- Module 230.22-5 Switchgear - Disconnect Switches, Ground Switches and G.T.D's, 20050807.pdf (257 kb)
- Module 230.22-6 Switchgear - Oil and Air Blast Breakers, 20050808.pdf (266 kb)
- Module 230.22-7 Switchgear - Circuit Breaker Control, 20050809.pdf (241 kb)
- Module 230.23-1 Transformers - Ratings, 20050810.pdf (206 kb)
- Module 230.23-2 Transformers - Operating Procedures, 20050811.pdf (246 kb)
- Module 230.24-1 Electrical Metering - Voltage and Circtuit Transformers, 20050812.pdf (200 kb)
- Module 230.24-2 Electrical Metering - Voltage Couplers and Meters, 20050813.pdf (121 kb)
- Module 230.25-1 Generators - Electrical and Magnetic Effects, 20050814.pdf (139 kb)
- Module 230.25-2 Generators - Equivalent Circuits, 20050815.pdf (214 kb)
- Module 230.25-3 Generators - Excitation Systems, 20050816.pdf (204 kb)
- Module 230.25-4 Generators - Paralleling and Synchronizing, 20050817.pdf (176 kb)
- Module 230.25-5 Generators - Infinite Bus Operation, 20050818.pdf (129 kb)
- Module 230.25-6 Generators - Non-Infinite Bus Operation, 20050819.pdf (151 kb)
- Module 230.25-7 Generators - Overfluxing, 20050820.pdf (120 kb)
- Module 230.25-8 Generators - Loading, 20050821.pdf (272 kb)
- Module 230.25-9 Generators - Operating Limitations, 20050822.pdf (168 kb)
- Module 230.25-10 Generators - Laboratory AC Generator Project, 20050823.pdf (181 kb)
1982-02-01---------Jump to [Top]
-
Instrumentation and Control, Course 136, OPG, 1982-02-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Course Index and Objectives 20042300.pdf (64 kb)
- 136.00-12 Control Equipment Review, 20042301.pdf (229 kb)
- 136.00-2 Control Theory Review, 20042302.pdf (491 kb)
- 136.00-3 Control Mode Settings, 20042303.pdf (224 kb)
- 136.00-4 Introduction to Frequency Response, 20042304.pdf (628 kb)
- 136.00-5 Direct Digital Control of Processes, 20042305.pdf (249 kb)
1985-04-24---------Jump to [Top]
-
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)
1986-01-01---------Jump to [Top]
-
Safety and Licensing Philosophy and Experience at Ontario Hydro Nuclear Generating Stations, by W. Lee, OPG, 1986-01-01. Doc type: Paper.
Summary: As published in the Canadian Nuclear Society Bulletin Vol. 7, No. 1, 1986 with the kind permission of the CNS: The safely and licensing philosophy adopted by Ontario Hydro in establishing the need for retrofit design modifications to CANDU nuclear generating stations in operation since the early 1970's is discussed. This philosophy was developed in response to regulatory requests to determine whether this need exists in view of the more extensive safely and licensing design features incorporated in recent CANDU nuclear generating stations compared to the earlier designs. These addition features generally
reflect evolving safety knowledge and licensing requirements over time.
Keywords: [Concept] Safety [SI] 03600 Nuclear Safety (Reactor) 10000 Site and Improvements [Discipline] Nuclear Engineering [Topic] Safety [Phase] Operation Safety [Audience] Engineer Grad Manager Technician Ugrad
- 19860101.pdf (2661 kb)
1987-03-01---------Jump to [Top]
-
Nuclear Journal of Canada, 1987 Vol 1 No. 1, CNS-, 1987-03-01. Doc type: Paper.
Summary: The Nuclear Journal of Canada was launched in 1987. Four issues were published in that year but sadly publication then ceased.
Keywords: [Concept] - [SI] 00000 General Project [Discipline] - [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad Manager Technician Ugrad
- Cover, Table of Contents and Editorial NJC-1-1-01.pdf (1539 kb)
- The Formative Years of the Canadian Nuclear Society 1976-1984, by G.R. Howey, P.A. Ross-Ross and I.S. Hewitt, NJC-1-1-02.pdf (1224 kb)
- A Review of the Health Effects of Energy Development [See also Vol. 1 No. 4 for a followup discussion], by O.K. Myers and M.M. Werner, NJC-1-1-03.pdf (729 kb)
- Food Irradiation: Commercial and Scientific Review, by B. K. Wilson, NJC-1-1-04.pdf (520 kb)
- Technetium-iron Oxide Reactions Under Anaerobic Conditions: A Fourier Transform Infrared, FTIR Study, by R.I. Haines, D.G. Owen and T. T. Vandergraaf, NJC-1-1-05.pdf (357 kb)
- Progress of the Swedish Radioactive Waste Management Program, by Hans G. Forsstrom, NJC-1-1-06.pdf (1534 kb)
- A Non-Intrusive Neutron Method for Poison Concentration Monitoring in CANDU Reactors, by E.M.A. Hussein, D.R. OConnor and M.E. Mosher, NJC-1-1-07.pdf (427 kb)
- Chemistry Control at Bruce NGS 'B' from Construction to Commercial Operation, by J.G. Roberts, NJC-1-1-09.pdf (382 kb)
- Gestion du cycle de combustible a la Centrale Nucleaire Gentilly-2, by G. Hotte, G. Parent, L. Cloutier, A. Aubin and N. Macici, NJC-1-1-10.pdf (762 kb)
- Summaries of CNS Conferences, Seminars and Workshops., NJC-1-1-11.pdf (625 kb)
1987-06-01---------Jump to [Top]
-
Nuclear Journal of Canada, 1987 Vol 1 No. 2, CNS-, 1987-06-01. Doc type: Paper.
Summary: The Nuclear Journal of Canada was launched in 1987. Four issues were published in that year but sadly publication then ceased.
Keywords: [Concept] - [SI] 00000 General Project [Discipline] - [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad Manager Technician Ugrad
- Cover, Table of Contents and Editorial NJC-1-2-01.pdf (1782 kb)
- Early Decisions in the Development of the CANDU Program, by J.L. Gray, NJC-1-2-02.pdf (719 kb)
- Insights from Chernobyl on Severe Accident Assessment of CANDU Reactors, by J.T. Rogers, NJC-1-2-03.pdf (829 kb)
- Concentration Processes under Tubesheet Sludge Piles in Nuclear Steam Generators, by F. Gonzalez and P. Spekkens, NJC-1-2-06.pdf (937 kb)
- A Review of Low-Level Radioactive Waste Management Technology in the Canadian Nuclear Industry, by T.J. Carter and P.K.M. Rao, NJC-1-2-09.pdf (514 kb)
- Characterization of Radioactive Wastes Incorporated in a Cement Matrix, by E.R. Merz, D. Dyckerhoff and R. Odoj, NJC-1-2-10.pdf (501 kb)
- Spent Fuel Storage and Transportation Experience for the Idaho National Engineering Laboratory, by C.P. Gertz, D.H. Schoonen and B.H. Wakeman, NJC-1-2-11.pdf (702 kb)
- Summaries of CNS Conferences, Seminars and Workshops., NJC-1-2-12.pdf (474 kb)
1987-09-01---------Jump to [Top]
-
Nuclear Journal of Canada, 1987 Vol 1 No. 3, CNS-, 1987-09-01. Doc type: Paper.
Summary: The Nuclear Journal of Canada was launched in 1987. Four issues were published in that year but sadly publication then ceased.
Keywords: [Concept] - [SI] 00000 General Project [Discipline] - [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad Manager Technician Ugrad
- Cover, Table of Contents and Editorial NJC-1-3-01.pdf (1268 kb)
- Chernobyl - A Canadian Technical Perspective, by J.Q. Howieson and V.G. Snell, NJC-1-3-02.pdf (1766 kb)
- CATHENA Simulation of Thermosiphoning in a Pressurized-Water Test Facility, by J.P. Mallory and P.J. Ingham, NJC-1-3-05.pdf (615 kb)
- Use of Quantitative Indicators of Nuclear Safety in Ontario Hydro, by R.T. Popple and S.B. Harvey, NJC-1-3-06.pdf (416 kb)
- Safe, Permanent Disposal of Nuclear Fuel Waste, by W.T. Hancox, NJC-1-3-07.pdf (942 kb)
- The Projected Environmental Impacts of Transportation of Radioactive Material to the First United States Repository Site - An Overview, by J.W. Cashwell, K.S. Neuhauser, P.C. Reardon and G.W. McNair, NJC-1-3-08.pdf (491 kb)
- Book Review: Fallout from Chernobyl by L. Ray Silver, by A.N. Sinclair, NJC-1-3-09.pdf (104 kb)
- CNS Conferences, Seminars, NJC-1-3-10.pdf (185 kb)
1987-12-01---------Jump to [Top]
-
Nuclear Journal of Canada, 1987 Vol 1 No. 4, CNS-, 1987-12-01. Doc type: Paper.
Summary: The Nuclear Journal of Canada was launched in 1987. Four issues were published in that year but sadly publication then ceased.
Keywords: [Concept] - [SI] 00000 General Project [Discipline] - [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad Manager Technician Ugrad
- Cover, Table of Contents and Editorial NJC-1-4-01.pdf (1312 kb)
- The Outlook for Nuclear Power after Chernobyl, by L.L. Bennett, NJC-1-4-02.pdf (499 kb)
- Sea Dumping of Radioactive Wastes, by J.M. Bewers, NJC-1-4-03.pdf (1065 kb)
- The Effect of Steam Generator Tube Temperature on the Stress Corrosion Cracking of Alloy 600, by F.P. Vaccaro, G.J. Theus and B.P. Miglin, NJC-1-4-04.pdf (663 kb)
- The AC Device for Repositioning of Garter Springs in CANDU Reactors, by Matija Cenanovic and Hugo Maureira, NJC-1-4-09.pdf (696 kb)
- Waterlancing for CANDU Steam Generators, by W.G. Schneider, NJC-1-4-10.pdf (370 kb)
- Locating Gas Pipelines with Radioactive Sources, by Lubomir Zikovsky and Mostafa Yagoubi, NJC-1-4-11.pdf (145 kb)
- Optimization of Darlington Tritium Removal Facility Performance: Effects of Key Process Variables, by A. Busigin and S. K. Sood, NJC-1-4-12.pdf (230 kb)
- Discussion: A Review of the Health Effects of Energy Development (Volume I, No. I, March 1987, pp. 14-24.), by E. Siddall, NJC-1-4-13.pdf (168 kb)
- Book Reviews: (1) Planet Earth in Jeopardy: Environmental Consequences of Nuclear War by Lydia Datto; (2) Understanding Chernobyl by The Uranium Institute, by Alan Wyatt, David Mosey, NJC-1-4-14.pdf (168 kb)
- CNS Conferences, Seminars, NJC-1-4-15.pdf (269 kb)
1990-01-01---------Jump to [Top]
-
Mechanical Equipment, Course PI 30.1, Nuclear Training Centre, OPG, 1990-01-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03200 Mechanical Engineering [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Operation [Audience] College Engineer Technician Ugrad
- Full Course 20043200.pdf (5736 kb)
- PI 30.10-0 Introduction and Objectives, 20043201.pdf (392 kb)
- 430.10-0 Identification and Coding of Mechanical Equipment, 20043202.pdf (251 kb)
- 430.10-1 Centrifugal Pumps, 20043203.pdf (379 kb)
- 330.10-1 Centrifugal Pumps, 20043204.pdf (795 kb)
- 430.10-2 Positive Displacement Pumps, 20043205.pdf (168 kb)
- 430.10-3 Compressonrs - Dynamic and Positive Displacement, 20043206.pdf (270 kb)
- 430.10-4 Air System, 20043207.pdf (82 kb)
- 430.10-5 Fans, 20043208.pdf (57 kb)
- 430.10-6 Vacuum Pumps, 20043209.pdf (185 kb)
- 230.11-1 Compressors, 20043210.pdf (226 kb)
- 330.11-1 Heat Exchangers, 20043211.pdf (218 kb)
- 430.12-1 Piping and Tubes, 20043212.pdf (271 kb)
- 430.13-1 Valves, 20043213.pdf (513 kb)
- 430.14-1 Lubrification, 20043214.pdf (143 kb)
- 430.14-2 Unit 1 Bearings, 20043215.pdf (68 kb)
- 430.14-2 Unit 2 Lubrification Methods, 20043216.pdf (62 kb)
- 430.14-2 Unit 3 Bearing Design and Installation, 20043217.pdf (81 kb)
- 230.12-1 Lubrification, 20043218.pdf (250 kb)
- 430.15-1 Sealing Devices, 20043219.pdf (181 kb)
- 330.14-1 Axial Mechanical Seals, 20043220.pdf (190 kb)
- 230.13-1 Shaft Couplings, 20043221.pdf (204 kb)
- 230.13-2 Belt Drives, 20043222.pdf (247 kb)
- 230.13-3 Chain Drives, 20043223.pdf (115 kb)
- 230.13-4 Gears and Gearing, 20043224.pdf (250 kb)
- 230.16-1 Gas Turbines, 20043225.pdf (289 kb)
-
Electrical Equipment, Course PI 30.2, Nuclear Training Center, OPG, 1990-01-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Full Course 20050700.pdf (4615 kb)
- Table of Contents, 20050701.pdf (234 kb)
- PI 26.34-1 Impedance, 20050702.pdf (159 kb)
- PI 26.35-1 Three Phase Systems, 20050703.pdf (282 kb)
- PI 26.35-2 Power and Power Factor, 20050704.pdf (190 kb)
- PI 30.20-1 The CANDU Generating Station, 20050705.pdf (150 kb)
- PI 30.21-1 Conductors, 20050706.pdf (379 kb)
- PI 30.21-2 Insulation, 20050707.pdf (221 kb)
- PI 30.21-3 Fuses, 20050708.pdf (323 kb)
- PI 30.21-4 Disconnect Switches and Circuit Breakers, 20050709.pdf (506 kb)
- PI 30.22-1 Transformers, 20050710.pdf (360 kb)
- PI 30.23-1 AC Generators, 20050711.pdf (357 kb)
- PI 30.23-2 Generator Auxiliary Systems, 20050712.pdf (404 kb)
- PI 30.24-1 Motors, 20050713.pdf (327 kb)
- PI 30.24 Appendix A, 20050714.pdf (77 kb)
- PI 30.25-1 Motor Control, 20050715.pdf (361 kb)
- PI 30.26-1 Batteries, 20050716.pdf (361 kb)
-
Turbine and Auxiliaries, Course PI 34 / TIMS Ref. PI 3004, Nuclear Training Centre, OPG, 1990-01-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Full Course 20051000.pdf (11938 kb)
- PI 34.00-00 Index and Objectives, 20051001.pdf (619 kb)
- 334.00-01 The Steam Turbine, 20051002.pdf (676 kb)
- 234.00-01 Turbine Construction, 20051003.pdf (1037 kb)
- 334.00-03 The Steam System, 20051004.pdf (517 kb)
- 234.00-02 Steam Control to the Turbine, 20051005.pdf (514 kb)
- 334.00-07 The Condenser, 20051006.pdf (476 kb)
- PI 25-06 The Mollier Diagram and the Turbine Processes, 20051007.pdf (1214 kb)
- 334.00-08 Feedwater Heating System -1, 20051008.pdf (212 kb)
- 334.00-09 Feedwater Heating System -2, 20051009.pdf (307 kb)
- 234.00-07 Feedwater Control and Operation, 20051010.pdf (586 kb)
- PI 24.21-01 Secondary Heat Transport System - Impurities, 20051011.pdf (230 kb)
- PI 24.21-02 Chemical Additives and Blowdown, 20051012.pdf (274 kb)
- PI 25-07 Efficiency of the CANDU Turbine Cycle, 20051013.pdf (513 kb)
- 234.00-03 Steam Valve Hydraulic Control, 20051014.pdf (255 kb)
- 234.00-04 Governor Operation, 20051015.pdf (516 kb)
- 234.00-05 Turbine Governors, 20051016.pdf (677 kb)
- 334.00-10 The Lubricating Oil System, 20051017.pdf (275 kb)
- 334.00-11 The Turning Gear, 20051018.pdf (113 kb)
- 234.00-06 Turbine Operational Problems, 20051019.pdf (568 kb)
- 234.00-08 Factors Limiting Startup and Rates of Loading, 20051020.pdf (887 kb)
- 334.00-13 appendix 1 Ontario Hydro Nuclear Turbine Types, 20051021.pdf (245 kb)
1992-02-01---------Jump to [Top]
-
Intro to Ontario Hydro and the Nuclear Operations Branch, Course 410, OPG, 1992-02-01. Doc type: Course.
Summary: An overview of the histroy of Ontario Hydro, its corporate direction and structure with a focus on teh Nuclear Operations Branch.
Keywords: [Concept] - [SI] 00000 General Project [Discipline] General Engineering [Topic] Intro and Overview [Phase] Operation [Audience] Technician
- Module 1 - Introduction to Ontario Hydro's Organization, Objectives and Performance 20042501.pdf (237 kb)
- Module 2 - Employee Safety in Nuclear Operations Branch, 20042502.pdf (84 kb)
- Module 3 - Radiation and the Public, 20042503.pdf (173 kb)
1992-06-01---------Jump to [Top]
-
Reactor Boiler and Auxiliaries, Course 233, Nuclear Training, OPG, 1992-06-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
- Full Course 20053800.pdf (13185 kb)
- Abstract and Table of Contents, 20053801.pdf (162 kb)
- Module 0 - Introduction, 20053802.pdf (269 kb)
- Module 1 - Moderator Heavy Water, 20053803.pdf (359 kb)
- Module 2 - Moderator Circulation System, 20053804.pdf (418 kb)
- Module 3 - Moderator Cover Gas System, 20053805.pdf (387 kb)
- Module 4 - The Moderator Liquid Poison System, 20053806.pdf (578 kb)
- Module 5 - The Moderator Purification System, 20053807.pdf (486 kb)
- Module 6 - HTS Heat Sources and Heat Transfer Paths, 20053808.pdf (362 kb)
- Module 7 - HTS Pressure and Inventory Control, 20053809.pdf (1482 kb)
- Module 8 - Heat Transport System Shutdown Operation, 20053810.pdf (609 kb)
- Module 9 - HTS Heavy Water, 20053811.pdf (602 kb)
- Module 10 - Heat Transport System Auxiliaries, 20053812.pdf (755 kb)
- Module 11 - Shutdown Systems, 20053813.pdf (704 kb)
- Module 12 - Emergency Coolant Injection, 20053814.pdf (663 kb)
- Module 13 - Containment, 20053815.pdf (1004 kb)
- Module 14 - Annulus Gas System, 20053816.pdf (407 kb)
- Module 15 - Shield Cooling Systems, 20053817.pdf (528 kb)
- Module 16 - Fuel Performance, 20053818.pdf (751 kb)
- Module 17 - Fuel Handling, 20053819.pdf (616 kb)
- Module 18 - Unit Upsets, 20053820.pdf (1950 kb)
1992-07-01---------Jump to [Top]
-
Electrical Systems, Course 235, OPG, 1992-07-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 50000 Electric Power Systems [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Module 235.00 Introduction 20042900.pdf (114 kb)
- Module 235.01 Unit Service Power, 20042901.pdf (305 kb)
- Module 235.02 Ring Bus Configuration, 20042902.pdf (103 kb)
- Module 235.03 Electrical Protection Schemes, 20042903.pdf (87 kb)
- Module 235.04 Application of Electrical Protection Schemes in the Power Station, 20042904.pdf (189 kb)
- Module 235.05 Electric Motor Protection, 20042905.pdf (420 kb)
- Module 235.06 Power Transformer Protection, 20042906.pdf (253 kb)
- Module 235.07 Generator Protection, 20042907.pdf (374 kb)
- Module 235.08 Generator and Transmission Line Stability, 20042908.pdf (682 kb)
- Appendix A Power Transfer Equation, 20042909.pdf (48 kb)
1993-01-01---------Jump to [Top]
-
Principes de Science et de Fonctionnement des Réacteurs - 20070500, CNSC, 1993-01-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] - [Phase] Concept Design [Audience] College Engineer Manager Technician Ugrad
- Réacteurs à Neutrons Intermédiaires et Auxiliaires 20070500.pdf (2850 kb)
- Réacteurs à Neutrons Intermédiaires et Auxiliaires - Systèmes Spéciaux de Sûreté, 20070501.pdf (237 kb)
- Réacteurs à Neutrons Intermédiaires et Auxiliaires - Combustible, 20070502.pdf (280 kb)
- Réacteurs à Neutrons Intermédiaires et Auxiliaires - CC, 20070503.pdf (1500 kb)
- Réacteurs à Neutrons Intermédiaires et Auxiliaires - Réacteurs à Neutrons Intermédiaires et Auxiliaires, 20070504.pdf (961 kb)
- Réacteurs à Neutrons Intermédiaires et Auxiliaires - Circuits du Réacteur, 20070505.pdf (421 kb)
1993-02-01---------Jump to [Top]
-
Reactor, Boiler and Accessories, Course 233, OPG, 1993-02-01. Doc type: Course.
Summary: Table of contents and Objectives for Course 233, Reactor, Boiler, and Auxiliaries.
Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
- Table of Contents and Objectives 20042200.pdf (640 kb)
- 233.20-1 Moderator and Main Moderator System, 20042201.pdf (485 kb)
- 233.20-2 Moderator Purification, 20042202.pdf (241 kb)
- 233.20-3 Moderator Cover Gas System, 20042203.pdf (202 kb)
- 233.20-4 Moderator D2O Collection, 20042204.pdf (117 kb)
- 233.20-5 Moderator Liquid Poison System, 20042205.pdf (343 kb)
- 233.30-1 Heat Transport D2O and Heat Transport Main System, 20042206.pdf (284 kb)
- 233.30-2 Heat Transport Pressurizing System, 20042207.pdf (277 kb)
- 233.30-3 Heat Transport Purification, 20042208.pdf (235 kb)
- 233.30-4 Heat Transport Gland Seal Circuit, 20042209.pdf (165 kb)
- 233.30-5 Heat Transport Shutdown Cooling, 20042210.pdf (144 kb)
- 233.30-6 Heat Transport Maintenance Cooling System, 20042211.pdf (56 kb)
- 233.30-7 Heat Transport H2 Addition, 20042212.pdf (132 kb)
- 233.30-8 Heat Transport Pressure Relief, 20042213.pdf (204 kb)
- 233.30-9 Heat Transport D2O Collection, 20042214.pdf (100 kb)
- 233.30-10 Heat Transport D2O Recovery, 20042215.pdf (113 kb)
- 233.30-11 Emergency Coolant Injection System, 20042216.pdf (197 kb)
- 233.30-12 Heat Sources and Transfer Paths, 20042217.pdf (271 kb)
- 233.40-1 Shield Cooling Systems, 20042218.pdf (250 kb)
- 233.40-2 Containment System, 20042219.pdf (462 kb)
- 233.40-3 Annulus Gas System, 20042220.pdf (95 kb)
- 233.60-1 Steam Supply System, 20042221.pdf (383 kb)
- 233.70-1 Fuel Design and Manufacturing Features, 20042222.pdf (377 kb)
- 233.70-2 Fuel Performance and Operating Features, 20042223.pdf (521 kb)
1993-04-01---------Jump to [Top]
-
Introduction to CANDU Processes, Course 41001, OPG, 1993-04-01. Doc type: Course.
Summary: Brief history of CANDU, operating philosophy, nuclear systems, energy balance and overall unit control, support systems, waste management, heavy water production and management.
Keywords: [Concept] - [SI] 01000 General Engineering (Methods, Policy, Procedures) [Discipline] General Engineering [Topic] Intro and Overview [Phase] Operation [Audience] Technician
- Module 0 - Index, Introduction and Course Information 20042600.pdf (253 kb)
- Module 1 Operating Philosophy - Introduction, 20042601.pdf (33 kb)
- Module 1 A. Employee and Public Safety, 20042602.pdf (171 kb)
- Module 1 B. Reactor Safety, 20042603.pdf (271 kb)
- Module 1 C. Environmental Limits, 20042604.pdf (64 kb)
- Module 1 D. Economics of CANDU, 20042605.pdf (94 kb)
- Module 1 E. How We Conduct Our Business, 20042606.pdf (266 kb)
- Module 2 Reactor Side of the Station - Introduction, 20042607.pdf (16 kb)
- Module 2 A. Principle of Reactor Operation, 20042608.pdf (217 kb)
- Module 2 B. Major Components of CANDU Reactors, 20042609.pdf (360 kb)
- Module 2 C. Heat Production and Reactor Regulation, 20042610.pdf (160 kb)
- Module 2 D. Reactor, Personnel and Public Protection, 20042611.pdf (276 kb)
- Module 3 The Conventional Side of the Power Station- Introduction, 20042612.pdf (28 kb)
- Module 3 A. Steam and Feedwater Cycle, 20042613.pdf (403 kb)
- Module 3 B. The Generator, 20042614.pdf (73 kb)
- Module 3 C. Conventional and Radiological Hazards, 20042615.pdf (54 kb)
- Module 4 Energy Balance and Unit Control - Introduction, 20042616.pdf (14 kb)
- Module 4 A. Efficiency and Energy Conversion, 20042617.pdf (76 kb)
- Module 4 B. Energy Balance, 20042618.pdf (166 kb)
- Module 4 C. Unit Operational Control, 20042619.pdf (71 kb)
- Module 5 Support Systems - Introduction, 20042620.pdf (18 kb)
- Module 5 A. Electrical Systems, 20042621.pdf (124 kb)
- Module 5 B. Water and Air Systems, 20042622.pdf (113 kb)
- Module 5 C. Identification System, 20042623.pdf (64 kb)
- Module 5 D. Site Support Systems, 20042624.pdf (61 kb)
- Module 5 E. Waste Management, 20042625.pdf (77 kb)
- Module 5 F. Heavy Water Production and Management, 20042626.pdf (184 kb)
1994-07-01---------Jump to [Top]
-
Turbine and Auxiliaries, Nuclear Training Course 234, OPG, 1994-07-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Module 234-00 Introduction to the Course 20042400.pdf (182 kb)
- Module 234-01 The Steam Turbine, 20042401.pdf (760 kb)
- Module 234-02 The Boiler, 20042402.pdf (851 kb)
- Module 234-03 The Main Steam System, 20042403.pdf (1399 kb)
- Module 234-04 Auxiliary Steam Systems, 20042404.pdf (684 kb)
- Module 234-05 The Condenser and its Auxiliary Systems, 20042405.pdf (1091 kb)
- Module 234-06 The Condensate, the Boiler Feed and Their Auxiliary Systems, 20042406.pdf (1736 kb)
- Module 234-07 The Turbine Governing System, 20042407.pdf (724 kb)
- Module 234-08 The Turbine Supervisory System, 20042408.pdf (273 kb)
- Module 234-09 The Turning Gear, 20042409.pdf (305 kb)
- Module 234-10 The Turbine Lubricating System, 20042410.pdf (503 kb)
- Module 234-11 Startup and Loading, 20042411.pdf (1220 kb)
- Module 234-12 Unloading and Shutdown, 20042412.pdf (333 kb)
- Module 234-13 Special Modes of Operation and Accidents, 20042413.pdf (895 kb)
- Module 234-14 Turbine Operational Problems, 20042414.pdf (850 kb)
1994-09-01---------Jump to [Top]
-
Mechanical Equipment, Course 23001, OPG, 1994-09-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03200 Mechanical Engineering [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Operation [Audience] College Engineer Technician Ugrad
- Full Course 20042800.pdf (1261 kb)
- Intro and Table of Contents, 20042801.pdf (44 kb)
- Module 1 Centrifugal Pumps and Systems, 20042802.pdf (1034 kb)
- Module 2 Positive Displacement Compressor Operation, 20042803.pdf (194 kb)
1995-07-01---------Jump to [Top]
-
Canada's Nuclear Achievement: Technical and Economic Perspectives, by T.E. Rummery and J.A. MacPherson, AECL, 1995-07-01. Doc type: Paper.
Summary: 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.
Keywords: [Concept] General [SI] 00000 General Project [Discipline] History [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High Manager Technician Ugrad Vendor
- 19950101.pdf (873 kb)
1996-02-01---------Jump to [Top]
-
Introduction to Nuclear Reactor Engineering, Course 3.1, by J. Koclas, Chulalongkorn University, 1996-02-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Nuclear Engineering [Topic] Basic Equations [Phase] Concept Design [Audience] College Manager Technician Ugrad
- Introduction to Nuclear Engineering 20044101.pdf (1855 kb)
- A Guidebook to Nuclear Reactors by Anthony V. Nero, by J. Koclas, 20044102.pdf (1874 kb)
- Miscellaneous CANDU-Related Viewgraphs, by J. Koclas, 20044103.pdf (1045 kb)
-
Nuclear Power Plant Control & Simulaion, Course 3.4, by G. Bereznai, Chulalongkorn University, 1996-02-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Workbook, Chapter 1 - Modules A & B 20044401.pdf (644 kb)
- Workbook, Chapter 2 - Modules A to F, by G. Bereznai, 20044402.pdf (3512 kb)
- Workbook, Chapter 3 - Modules A to I, by G. Bereznai, 20044403.pdf (4141 kb)
- Workbook, Chapter 4 - Modules A to D, by G. Bereznai, 20044404.pdf (2750 kb)
- Workbook, Chapter 5 - Modules A to C, by G. Bereznai, 20044405.pdf (1554 kb)
-
Operation & Maintenance of a Nuclear Power Plant, Course 4.4, by D. McQuade, Chulalongkorn University, 1996-02-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Maintainability [Phase] Operation [Audience] Engineer Manager Technician
- Title, Objectives, Text Index 20051801.pdf (374 kb)
- Workbook 01 - Management of a Nuclear Power Plant, by D. McQuade, 20051802.pdf (591 kb)
- Workbook 02 - Principles of Operation & Maintenance, by D. McQuade, 20051803.pdf (1187 kb)
- Workbook 03 - Configuration Management, by D. McQuade, 20051804.pdf (620 kb)
- Workbook 04 - Maintenance of an NPP, by D. McQuade, 20051805.pdf (1093 kb)
- Workbook 05 - Outage Management, by D. McQuade, 20051806.pdf (1108 kb)
- Workbook 06 - Specialist Requirements in Maintenance, by D. McQuade, 20051807.pdf (348 kb)
- Workbook 07 - Operator and Maintenance Standards, by D. McQuade, 20051808.pdf (1048 kb)
- Workbook 08 - System Surveillance, by D. McQuade, 20051809.pdf (795 kb)
- Workbook 09 - Building the Total Team, by D. McQuade, 20051810.pdf (771 kb)
-
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)
-
Intermediate Reactors, Boilers and Auxiliaries, CNSC, 1996-02-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] - [Phase] Concept Design [Audience] College Engineer Manager Technician Ugrad
- 20052900.pdf (14193 kb)
-
Digital Instrumentation & Control, Course 7.4, by M. MacBeth, Chulalongkorn University, 1996-02-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Chapter 01 - CANDU DCC Features 20053301.pdf (237 kb)
- Chapter 02 - Digital Control Concepts, by M. MacBeth, 20053302.pdf (317 kb)
- Chapter 03 - Computer I/O Subsystems, by M. MacBeth, 20053303.pdf (423 kb)
- Chapter 04 - Digital Ctrl Program Concepts, by M. MacBeth, 20053304.pdf (492 kb)
- Chapter 05 - PHT P&IC Control Program, by M. MacBeth, 20053305.pdf (906 kb)
- Chapter 06 - Steam Generator Level Control, by M. MacBeth, 20053306.pdf (727 kb)
- Chapter 07 - Computerized Shutdown System, by M. MacBeth, 20053307.pdf (250 kb)
- Chapter 08 - S/W Categorization Methods, by M. MacBeth, 20053308.pdf (233 kb)
- Chapter 09 - General Display Requirements, by M. MacBeth, 20053309.pdf (349 kb)
- Chapter 10 - Human Interface Design (HFE), by M. MacBeth, 20053310.pdf (1014 kb)
- Chapter 11 - HFE Methods, by M. MacBeth, 20053311.pdf (365 kb)
- Chapter 12 - Work Assignment, by M. MacBeth, 20053312.pdf (173 kb)
- Chapter 13 - Typical Design Guide Features, by M. MacBeth, 20053313.pdf (376 kb)
- Chapter 14 - Typical HFE Eng. Program, by M. MacBeth, 20053314.pdf (421 kb)
- Workbook 01 Module 01 - Introduction to Instrumentation, by M. MacBeth, 20053315.pdf (182 kb)
- Workbook 01 Module 02 - ISA Symbols, by M. MacBeth, 20053316.pdf (94 kb)
- Workbook 01 Module 03 - Pressure Instrumentation, by M. MacBeth, 20053317.pdf (122 kb)
- Workbook 01 Module 04 - Level Instrumentation, by M. MacBeth, 20053318.pdf (249 kb)
- Workbook 01 Module 05 - Flow Instrumentation, by M. MacBeth, 20053319.pdf (267 kb)
- Workbook 01 Module 06 - Temperature Instrumentation, by M. MacBeth, 20053320.pdf (235 kb)
- Workbook 01 Module 07 - Digital Computer Control, by M. MacBeth, 20053321.pdf (237 kb)
- Workbook 01 Module 08 - Control Valves, Accessories, by M. MacBeth, 20053322.pdf (931 kb)
- Workbook 02 Module 01 - Control Concepts, by M. MacBeth, 20053323.pdf (588 kb)
- Workbook 02 Module 02 - Control Equipment, by M. MacBeth, 20053324.pdf (414 kb)
- Workbook 02 Module 03 - Control and Process Considerations, by M. MacBeth, 20053325.pdf (371 kb)
- Workbook 03 Module 01 - Level Control, by M. MacBeth, 20053326.pdf (566 kb)
- Workbook 03 Module 02 - Pressure Control, by M. MacBeth, 20053327.pdf (203 kb)
- Workbook 04 Module 01 - Log and Linear Ranges, by M. MacBeth, 20053328.pdf (96 kb)
- Workbook 04 Module 02 - Log range detectors, by M. MacBeth, 20053329.pdf (126 kb)
- Workbook 04 Module 03 - Linear Range Detectors, by M. MacBeth, 20053330.pdf (119 kb)
- Workbook 05 Module 01 - Zone Level Control, by M. MacBeth, 20053331.pdf (216 kb)
- Workbook 05 Module 02 - Reactor Regulating System, by M. MacBeth, 20053332.pdf (228 kb)
- Workbook 05 Module 03 - Reactor Shutdown Systems, by M. MacBeth, 20053333.pdf (625 kb)
- Workbook 05 Module 04 - Recovery from a Poison Outage, by M. MacBeth, 20053334.pdf (79 kb)
- Workbook 06 Module 01 - Feed and Bleed Pressure Control, by M. MacBeth, 20053335.pdf (206 kb)
- Workbook 06 Module 02 - Pressure Control by Pressurizer, by M. MacBeth, 20053336.pdf (111 kb)
- Workbook 06 Module 03 - Heat Transport Bleed Control, by M. MacBeth, 20053337.pdf (245 kb)
- Workbook 07 Module 01 - Unit Control Concepts, by M. MacBeth, 20053338.pdf (173 kb)
- Workbook 07 Module 02 - Boiler Pressure Control, by M. MacBeth, 20053339.pdf (255 kb)
- Workbook 07 Module 03 - Unit Startup, by M. MacBeth, 20053340.pdf (380 kb)
- Workbook 08 Module 01 - Controller Tuning, by M. MacBeth, 20053341.pdf (189 kb)
- Workbook 09 Module 01 - CANDU 9 Plant Control, by M. MacBeth, 20053342.pdf (182 kb)
1996-08-01---------Jump to [Top]
-
Reactor Control & Simulation, Course 3.3, by J. Koclas, Chulalongkorn University, 1996-08-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Chapter 0 - Title and Table of Contents 20044301.pdf (67 kb)
- Chapter 1 - Point Kinetics, by J. Koclas, 20044302.pdf (490 kb)
- Chapter 2 - General Concepts, by J. Koclas, 20044303.pdf (262 kb)
- Chapter 3 - Power Measurement & Calibration, by J. Koclas, 20044304.pdf (211 kb)
- Chapter 4 - Power Error, by J. Koclas, 20044305.pdf (193 kb)
- Chapter 5 - Liquid Zone Control, by J. Koclas, 20044306.pdf (134 kb)
- Chapter 6 - Adjuster Rod Control, by J. Koclas, 20044307.pdf (109 kb)
- Chapter 7 - MCA Control, by J. Koclas, 20044308.pdf (90 kb)
- Chapter 8 - Shutoff Rods Extraction, by J. Koclas, 20044309.pdf (35 kb)
- Chapter 9 - Modal Flux Synthesis, by J. Koclas, 20044310.pdf (83 kb)
- Chapter 10 - Reactor Setback Program, by J. Koclas, 20044311.pdf (66 kb)
- Chapter 11 - Reactor Stepback, by J. Koclas, 20044312.pdf (62 kb)
- Chapter 12 - Shutdown Systems: SDS1 and SDS2, by J. Koclas, 20044313.pdf (173 kb)
- Chapter XX - Supplementary Materials, by J. Koclas, 20044314.pdf (531 kb)
- Workbook, Chapter 2 - General Concepts, by J. Koclas, 20044315.pdf (331 kb)
- Workbook, Chapter 3 - Power Measurement & Calibration, by J. Koclas, 20044316.pdf (263 kb)
- Workbook, Chapter 4 - Power Error, by J. Koclas, 20044317.pdf (254 kb)
- Workbook, Chapter 5 - Liquid Zone Control, by J. Koclas, 20044318.pdf (159 kb)
- Workbook, Chapter 6 - Adjuster Rod Control, by J. Koclas, 20044319.pdf (125 kb)
- Workbook, Chapter 7 - Mechanical Control Absorbers, by J. Koclas, 20044320.pdf (94 kb)
- Workbook, Chapter 8 - Shutoff Rods Extraction, by J. Koclas, 20044321.pdf (46 kb)
- Workbook, Chapter 9 - Modal Flux Synthesis, by J. Koclas, 20044322.pdf (103 kb)
- Workbook, Chapter 10 - Reactor Setback Program, by J. Koclas, 20044323.pdf (85 kb)
- Workbook, Chapter 11 - Reactor Stepback, by J. Koclas, 20044324.pdf (80 kb)
- Workbook, Chapter 12 - Shutdown Systems: SDS1 and SDS2, by J. Koclas, 20044325.pdf (209 kb)
1997-11-01---------Jump to [Top]
-
Peer Evaluation Techniques, Course 4.5, by R.B. Taylor, Chulalongkorn University, 1997-11-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Performance [Phase] Operation [Audience] Engineer Manager Technician
- Section 01 - Self-Assessment 20051901.pdf (410 kb)
- Section 02 - Operational Safety Review, by R.B. Taylor, 20051902.pdf (394 kb)
- Section 03 - Control of Plant Operations, by R.B. Taylor, 20051903.pdf (432 kb)
- Section 04 - Operations, by R.B. Taylor, 20051904.pdf (474 kb)
- Section 05 - Maintenance, by R.B. Taylor, 20051905.pdf (631 kb)
- Section 06 - Housekeeping, Material Conditions, Industrial Safety, by R.B. Taylor, 20051906.pdf (246 kb)
- Section 07 - Configuration Management, by R.B. Taylor, 20051907.pdf (218 kb)
- Workbook 01 - Self-Assessment, by R.B. Taylor, 20051908.pdf (286 kb)
- Workbook 02 - IAEA-OSART, by R.B. Taylor, 20051909.pdf (468 kb)
- Workbook 03 - Control of Plant Activities, by R.B. Taylor, 20051910.pdf (228 kb)
- Workbook 04 - Operations, by R.B. Taylor, 20051911.pdf (459 kb)
- Workbook 05 - Maintenance, by R.B. Taylor, 20051912.pdf (515 kb)
- Workbook 06 - Housekeeping, Material Conditions, Industrial Safety, by R.B. Taylor, 20051913.pdf (324 kb)
- Workbook 07 - Configuration Management, by R.B. Taylor, 20051914.pdf (309 kb)
1998-09-18---------Jump to [Top]
-
IAEA CANDU Instrumentation & Control Course, by Mike MacBeth, IAEA, 1998-09-18. Doc type: Course.
Summary: IAEA CANDU Instrumentation & Control Course, by Dr. Mike MacBeth (AECL), September 13 - 18, 1998, SNERDI, Shanghai
Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- Instrumentation Equipment 20041601.pdf (2847 kb)
- Electronic Control, by Mike MacBeth, 20041602.pdf (1680 kb)
- Controller Tuning, by Mike MacBeth, 20041603.pdf (510 kb)
- Computer Input/Output Subsystems, by Mike MacBeth, 20041604.pdf (484 kb)
- Control Programs, by Mike MacBeth, 20041605.pdf (810 kb)
- Nuclear Instrumentation, by Mike MacBeth, 20041606.pdf (518 kb)
- Reactor Control and Protection, by Mike MacBeth, 20041607.pdf (627 kb)
- Heat Transport Control Systems, by Mike MacBeth, 20041608.pdf (1415 kb)
- Reactor Protection, by Mike MacBeth, 20041609.pdf (712 kb)
- Overall Unit Control, by Mike MacBeth, 20041610.pdf (693 kb)
1999-02-23---------Jump to [Top]
-
Single Phase Friction Factors for MNR Thermalhydraulic Modelling, by Wm.J. Garland, McMaster University, 1999-02-23. Doc type: Other.
Summary: 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.
Keywords: [Concept] - [SI] 03200 Mechanical Engineering; #33000 Primary Heat Transport System [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Modelling [Phase] Concept; #Design [Audience] College; #Engineer; #Grad; #Technician; #Ugrad
- 1phase1.xls (552 kb)
-
Decay Heat Estimates for MNR, by Wm.J. Garland, McMaster University, 1999-02-23. Doc type: Other.
Summary: Decay heat removal is essential in preventing fuel overheating and possible fission product release. This
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Basic Equations Modelling Reactor Physics [Phase] Concept Design Safety Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
- decayhe1.xls (521 kb)
2000-06-01---------Jump to [Top]
-
Radiation Monitoring Notebook, by James T. Voss, Individual Contributions, 2000-06-01. Doc type: Reference.
Summary: LA-UR-00-2584 James T. (Tom) Voss, NRRPT, CHP June 2000 (Feb. 2001 Update)
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Design Operation [Audience] Engineer Grad Technician Ugrad
- 20041901.pdf (191 kb)
2000-09-13---------Jump to [Top]
-
Safety Analysis Technology: Evolution, Revolution and the Drive to Re-Establish Margins, by John C Luxat, OPG, 2000-09-13. Doc type: Presentation.
Summary: A historical perspective of the evolution of safety analysis technology at OPG is presented below. The key elements of the new safety analysis methodology are then described together with its relationship to other components of Canadian nuclear safety technology. This development is placed in context with similar work being conducted in the international Light Water Reactor (LWR) community.
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Performance [Phase] Commissioning Design Operation Safety [Audience] Engineer Technician
- 20000301.pdf (256 kb)
2000-11-01---------Jump to [Top]
-
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)
2001-06-01---------Jump to [Top]
-
Radiation Protection ("Green Book"), by Jan Burnham, NB Power, 2001-06-01. Doc type: Book.
Summary:
Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Design Operation [Audience] Engineer Grad Technician Ugrad
- Cover Page 20031300.pdf (98 kb)
- Chapter 1 - Atomic Structure, by Jan Burnham, 20031301.pdf (898 kb)
- Chapter 2 - Radiation Theory, by Jan Burnham, 20031302.pdf (1729 kb)
- Chapter 3 - Radiation Dose, by Jan Burnham, 20031303.pdf (2016 kb)
- Chapter 4 - Biological Effects Of Radiation, by Jan Burnham, 20031304.pdf (1341 kb)
- Chapter 5 - Dose Limits And Risk, by Jan Burnham, 20031305.pdf (1929 kb)
- Chapter 6 - Instruments, by Jan Burnham, 20031306.pdf (8721 kb)
- Chapter 7 - Protection From External Exposures, by Jan Burnham, 20031307.pdf (3122 kb)
- Chapter 8 - Internal Dose, by Jan Burnham, 20031308.pdf (1414 kb)
- Chapter 9 - Contamination Control, by Jan Burnham, 20031309.pdf (9704 kb)
- Chapter 10 - Dose Records, by Jan Burnham, 20031310.pdf (1925 kb)
- Chapter 11 - Waste Management, by Jan Burnham, 20031311.pdf (4460 kb)
- Chapter 12 - Work Planning, by Jan Burnham, 20031312.pdf (2171 kb)
- Chapter 13 - Emergency Planning, by Jan Burnham, 20031313.pdf (2632 kb)
- Answers to Problems, by Jan Burnham, 20031314.pdf (1093 kb)
- Index, by Jan Burnham, 20031315.pdf (1210 kb)
2001-07-20---------Jump to [Top]
-
Starting Up a CANDU Reactor, by D.A. Meneley, AECL, 2001-07-20. Doc type: Paper.
Summary: CANDU power reactor designers and operators are fully aware of the need for caution in starting up power reactors. However, the open literature describing these established methods is quite sparse, especially with regard to the unique advantages in operability and safety that arise from the computer-driven Reactor Regulating System (RRS). The following text provides a general outline of one procedure appropriate for start-up of a CANDU 6 reactor.
Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Reactor Physics [Phase] Operation [Audience] College Engineer Manager Technician Ugrad
- Abbreviated Step-by Step Procedure 20010401.pdf (94 kb)
2002-05-01---------Jump to [Top]
-
Testing the Dynamics of Shutdown Systems, by Oszvald Glockler, OPG, 2002-05-01. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Electrical Engineering [Topic] Performance [Phase] Commissioning Operation [Audience] Engineer Technician
- Instrumentation in Reactor Trip Measurements 20030501.pdf (153 kb)
-
Reactor Noise Measurements in the Safety and Regulating Systems of CANDU Stations, by Oszvald Glockler, OPG, 2002-05-01. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Electrical Engineering [Topic] Performance [Phase] Commissioning Operation [Audience] Engineer Technician
- 20030601.pdf (242 kb)
2003-02-01---------Jump to [Top]
-
What is RTD, RdF Corporation, 2003-02-01. Doc type: Paper.
Summary:
Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
- 20030701.pdf (198 kb)
2003-05-10---------Jump to [Top]
-
Preserving CANDU Technical Knowledge – The CANTEACH Project, by Wm.J. Garland, Yulia Kosarenko, Malcolm Lightfoot, D.A. Meneley, CANTEACH, 2003-05-10. Doc type: Paper.
Summary:
Keywords: [Concept] General [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High K-8 Manager Technician Ugrad Vendor
- 20031401.pdf (245 kb)
-
Preservation and Dissemination of CANDU® Technical Knowledge (The CANTEACH Project), by Wm.J. Garland, Yulia Kosarenko, Malcolm Lightfoot, D.A. Meneley, CANTEACH, 2003-05-10. Doc type: Paper.
Summary:
Keywords: [Concept] General [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High K-8 Manager Technician Ugrad Vendor
- 20031501.pdf (299 kb)
2003-06-01---------Jump to [Top]
-
CANTEACH Flyer, by CANTEACH, CANTEACH, 2003-06-01. Doc type: Presentation.
Summary:
Keywords: [Concept] General [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High K-8 Manager Technician Ugrad Vendor
- 20031601.pdf (156 kb)
2004-07-17---------Jump to [Top]
-
CANDU Primary Heat Transfer System Heat Duty Diagram - analytic solution, by Wm.J. Garland, McMaster University, 2004-07-17. Doc type: Other.
Summary: CANDU Primary Heat Transfer System Heat Duty Diagram - simplified analytical calculation.
Keywords: [Concept] - [SI] 33100 Main Heat Transport Syste 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering [Topic] Basic Equations Heat Transfer Modelling Process Systems [Phase] Concept Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
- linear1.xls (333 kb)
-
CANDU Primary Heat Transfer System Heat Duty Diagram - numeric solution, by Wm.J. Garland, McMaster University, 2004-07-17. Doc type: Other.
Summary: CANDU Primary Heat Transfer System Heat Duty Diagram simplified numerical calculation .
Keywords: [Concept] - [SI] 33100 Main Heat Transport Syste 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering [Topic] Basic Equations Heat Transfer Modelling Process Systems [Phase] Concept Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
- numeric1.xls (377 kb)
-
CANDU fuel channel 1-D temperature calculation, by Wm.J. Garland, McMaster University, 2004-07-17. Doc type: Other.
Summary: CANDU fuel channel 1-D temperature calculation spreadsheet.
Keywords: [Concept] - [SI] 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Modelling [Phase] Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
- channel1 (511 kb)
-
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)
2009-05-30---------Jump to [Top]
-
Large LOCA Margins in CANDU Reactors - An Overview of the COG Report, by A.P. Muzumdar and D.A. Meneley, COG, 2009-05-30. Doc type: Paper.
Summary: This paper discusses the background and conclusions of the 2007 COG report on Large LOCA Safety Margins in CANDU Reactors, and the various initiatives that have resulted from this study since its release. The COG study challenged the notion that positive void reactivity itself is a design weakness, raised as an issue at the Convention on Nuclear Safety, to demonstrate the safety of operating CANDUs worldwide when compared to other certified LWR designs. The paper will briefly describe a new perspective on how the seemingly complex analytical results on reactor safety parameters can be compared on a level playing field, in such a manner that the non-specialist is able to understand. The paper is presented together with a companion paper that focuses on the comparison of reactivity initiated events in CANDU with some other internationally accepted LWR reactor designs.
Keywords: [Concept] - [SI] 31000 Reactor 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety Safety Analysis [Audience] College Engineer Grad Manager Technician Ugrad Vendor
- 20090101.pdf (89 kb)
-
Power Reactor Safety Comparison - A Limited Review, by D.A. Meneley and A.P. Muzumdar, COG, 2009-05-30. Doc type: Paper.
Summary: A large amount of attention has been paid to avoiding positive coolant void reactivity in LWR reactors. This can be justified due to specific accident events that could lead to severe consequences. Somewhat less attention has been paid to other accident sequences that can lead to positive reactivity addition. Other designs, for example the CANDU-PHWR, exhibit positive coolant void reactivity but include both inherent and engineered systems that compensate for this undesirable characteristic. This paper represents the beginning of a long-term process intended to enable a balanced and fair comparison of the real safety of all reactor types.
Keywords: [Concept] - [SI] 31000 Reactor 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety Safety Analysis [Audience] College Engineer Grad Manager Technician Ugrad Vendor
- 20090201.pdf (170 kb)
2011-01-01---------Jump to [Top]
-
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)
2012-01-25---------Jump to [Top]
-
Design and Safety of Canadian Nuclear Reactors, by V. Snell, UNENE, 2012-01-25. Doc type: Presentation.
Summary:
Keywords: [Concept] Safety [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety [Audience] Engineer Grad Manager Technician Ugrad
- 20120101.pdf (11620 kb)
2017-02-13---------Jump to [Top]
-
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)
2017-12-27---------Jump to [Top]
-
Canada's Power Reactor Fuel Bundle Design and Development, by R.D. Page and A.J. Langdon, AECL, 2017-12-27. Doc type: Other.
Summary: This pictorial record of Canada's power reactor fuel bundles was prepared to historically record the evolution of the power reactor fuel over the years. No one report issued over the years has been able to describe in detail the various changes that these pictures portray. It should be noted that the record does not include WR-1 type fuel or special irradiation of assemblies. "A picture speaks a thousand words". Full resolution versions of the images contained in this document can be found in the Image Library of CANTEACH web site http://canteach.candu.org listed under the System Index (SI) 37000 - Fuel.
Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Materials Engineering Mechanical Engineering [Topic] Chemistry Fluid Mechanics Heat Transfer Physical Description Thermalhydraulics [Phase] Concept Design Design Evolution [Audience] College Engineer Grad High Manager Technician Ugrad
- Historical and Pictorial Record FuelStory.pdf (355 kb)
|
|