Jump to year -> [1962-09-01] [1968-05-01] [1971-09-06] [1987-06-01] [1987-09-01] [1987-12-01] [1997-11-01] [2000-09-13] [2000-11-01] [2002-05-01] [2003-06-30]
[Topic]: Performance 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: 31

    1962-09-01---------Jump to [Top]
  1. 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)
    2. 1968-05-01---------Jump to [Top]
  2. The Performance of Zirconium Alloy Clad UO2 Fuel for Canadian Pressurized and Boiling Water Power Reactors, by R. D. Page and A. D. Lane, AECL, 1968-05-01. Doc type: Report.
    Summary: 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.
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Materials Engineering [Topic] Function Performance [Phase] Design Development Operation [Audience] Engineer
    - 19680101.pdf (2338 kb)
    3. 1971-09-06---------Jump to [Top]
  3. 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)
    4. 1987-06-01---------Jump to [Top]
  4. Nuclear Journal of Canada, 1987 Vol 1 No. 2, by F. Gonzalez and P. Spekkens, CNS, 1987-06-01. Doc type: Paper.
    Summary: The process by which bulk water solutes are concentrated under tubesheet sluuge piles in nuclear steam generators was investigated in the laboratory under simulated CANDU operating conditions. Concentration rates were found to depend on the tube heat flux and pile depth, although beyond a critical depth the concentration efficiency decreased.
    Keywords: [Concept] Chemistry and Corrosion [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Chemical Engineering [Topic] Performance [Phase] Operation [Audience] College Engineer Grad Technician Ugrad
    - Concentration Processes under Tubesheet Sludge Piles in Nuclear Steam Generators NJC-1-2-06.pdf (937 kb)
    - Simulation Methodology for Pressure Tube Integrity Analysis and Comparison with Experiments NJC-1-2-07.pdf (575 kb)
    5. 1987-09-01---------Jump to [Top]
  5. Nuclear Journal of Canada, 1987 Vol 1 No. 3, by R.T. Popple and S.B. Harvey, CNS, 1987-09-01. Doc type: Paper.
    Summary: The measurement of reactor safety performance from a public risk standpoint is rapidly becoming an area of wide interest, both in the public mind and within the industry. This paper outlines the quantified operational risk assessment methodology that has been in use in the Ontario Hydro nuclear-electric program since the early 1960's.
    Keywords: [Concept] General [SI] 01000 General Engineering (Methods, Policy, Procedures) [Discipline] General Engineering [Topic] Performance [Phase] Operation [Audience] College Engineer Grad Manager Technician Ugrad
    - Use of Quantitative Indicators of Nuclear Safety in Ontario Hydro NJC-1-3-06.pdf (416 kb)
    6. 1987-12-01---------Jump to [Top]
  6. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by F.P. Vaccaro, G.}. Theus, and B.P. Miglin, CNS, 1987-12-01. Doc type: Paper.
    Summary: This review of the stress corrosion cracking (scc) of Alloy 600 tubing assesses the relative importance of steam generator operating temperature in contrast to other factors.
    Keywords: [Concept] Chemistry and Corrosion [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Chemical Engineering Materials Engineering [Topic] Corrosion Performance [Phase] Operation [Audience] College Engineer Grad Technician Ugrad
    - The Effect of Steam Generator Tube Temperature on the Stress Corrosion Cracking of Alloy 600 NJC-1-4-04.pdf (663 kb)
    - Fuel for Thought NJC-1-4-07.pdf (876 kb)
    7. 1997-11-01---------Jump to [Top]
  7. 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 20051902.pdf (394 kb)
    - Section 03 - Control of Plant Operations 20051903.pdf (432 kb)
    - Section 04 - Operations 20051904.pdf (474 kb)
    - Section 05 - Maintenance 20051905.pdf (631 kb)
    - Section 06 - Housekeeping, Material Conditions, Industrial Safety 20051906.pdf (246 kb)
    - Section 07 - Configuration Management 20051907.pdf (218 kb)
    - Workbook 01 - Self-Assessment 20051908.pdf (286 kb)
    - Workbook 02 - IAEA-OSART 20051909.pdf (468 kb)
    - Workbook 03 - Control of Plant Activities 20051910.pdf (228 kb)
    - Workbook 04 - Operations 20051911.pdf (459 kb)
    - Workbook 05 - Maintenance 20051912.pdf (515 kb)
    - Workbook 06 - Housekeeping, Material Conditions, Industrial Safety 20051913.pdf (324 kb)
    - Workbook 07 - Configuration Management 20051914.pdf (309 kb)
    8. 2000-09-13---------Jump to [Top]
  8. 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)
    9. 2000-11-01---------Jump to [Top]
  9. 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)
    10. 2002-05-01---------Jump to [Top]
  10. 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)
  11. 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)
    12. 2003-06-30---------Jump to [Top]
  12. Safer Nuclear Energy for the Future, by Dan Meneley, AECL, 2003-06-30. Doc type: Presentation.
    Summary: Series of lectures by Dan Meneley presented at the 28th International Summer College on Physics and Contemporary Needs, June 30 - July 12, 2003, Nathiagali, Pakistan
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual Performance Safety [Phase] Concept Design Safety [Audience] Engineer Manager
    - Introduction 20041000.pdf (77 kb)
    - Lecture 1 - Safety Perspectives 20041001.pdf (115 kb)
    - Lecture 2 - Past Design Evolution 20041002.pdf (103 kb)
    - Lecture 3 - Future Design Directions 20041003.pdf (136 kb)
    - Lecture 4 - The Long Term 20041004.pdf (205 kb)
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