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[SI]: 36000 Steam Generator Steam and Water Systems 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: 13

    1970-03-09---------Jump to [Top]
  1. Nuclear Heated Steam Generators, by D. J. Stelliga and J.M. Dyke, Babcock & Wilcox Canada, 1970-03-09. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
    - Presented to the Canadian Electrical Association, Toronto, Ontario, March 9-12, 1970 20053900.pdf (928 kb)
    2. 1981-01-01---------Jump to [Top]
  2. Memories of my Life as a Professional Engineer in the Royal Navy and the Canadian Boiler Industry, by J.M. Dyke, Individual Contributions, 1981-01-01. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
    - Fran Gregory, Ed 20054000.pdf (2139 kb)
    3. 1987-03-01---------Jump to [Top]
  3. Nuclear Journal of Canada, 1987 Vol 1 No. 1, by J.G. Roberts, CNS, 1987-03-01. Doc type: Paper.
    Summary: Pre-operational storage chemistry and flushing of the secondary side is described. The approach devised for Bruce NGS 'B' Unit 6 was unique for an Ontario Hydro Nuclear Unit. The significance of the improved Construction installation and Quality Assurance procedures, combined with those of Operations is identified. Secondary side chemistry during both commissioning and later operation is reported. It will be shown that the application of ALARA (As Low As is Reasonably Achievable) concept has resulted in tighter chemical specifications being met.
    Keywords: [Concept] Chemistry and Corrosion [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Chemistry [Topic] Corrosion [Phase] Commissioning Construction Operation [Audience] College Engineer Grad Technician Ugrad
    - Chemistry Control at Bruce NGS 'B' from Construction to Commercial Operation NJC-1-1-09.pdf (382 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)
    5. 1987-12-01---------Jump to [Top]
  5. 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)
    - Waterlancing for CANDU Steam Generators NJC-1-4-10.pdf (370 kb)
    6. 1997-06-01---------Jump to [Top]
  6. Steam Generators for CANDU, Engineering Memoirs, by J.M. Dyke, Individual Contributions, 1997-06-01. Doc type: Essay.
    Summary:
    Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
    - 20054100.pdf (19 kb)
    7. 2003-04-20---------Jump to [Top]
  7. Fretting in Nuclear Steam Generators - A New Approach, by J.M. Dyke, Individual Contributions, 2003-04-20. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
    - 11th International Conference on Nuclear Engineering, Tokyo, Japan 20054500.pdf (2821 kb)
    8. 2004-04-20---------Jump to [Top]
  8. The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators, by J.M. Dyke, Individual Contributions, 2004-04-20. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
    - 12th International Conference on Nuclear Engineering, Washington, DC 20054201.pdf (1714 kb)
    - 12th International Conference on Nuclear Engineering, Washington, DC 20054202.pdf (1558 kb)
    9. 2006-03-01---------Jump to [Top]
  9. Fretting Failures in Early Canadian Nuclear Steam Generators, by J.M. Dyke and W.J. Garland, CANTEACH, 2006-03-01. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
    - 20060201.pdf (140 kb)
    10. 2006-04-01---------Jump to [Top]
  10. Evolution of CANDU Steam Generators – A Historical View, by J.M. Dyke and W.J. Garland, CANTEACH, 2006-04-01. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
    - 20060101.pdf (702 kb)
    11. 2015-01-01---------Jump to [Top]
  11. The Essential CANDU, by Wm. J. Garland, Editor-in-Chief, UNENE, 2015-01-01. Doc type: Book.
    Summary: The Essential CANDU is a textbook about nuclear science and engineering pertaining to CANDU reactors using CANDU as the reference design. This distinguishes it from comparable textbooks based on PWR reactors. This is not a product description of CANDU per se. The book emphasizes theory over other aspects of nuclear science. This is a textbook about CANDU nuclear reactor and power plant engineering, not just the reactor physics of the core.
    Keywords: [Concept] General [SI] 30000 Reactor, Steam Generators and Auxiliaries 35000 Fuel Transfer and Storage 36000 Steam Generator Steam and Water Systems 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Chemistry General Engineering Health Physics Nuclear Engineering [Topic] Corrosion Fluid Mechanics Fuel Management Heat Transfer Important Parameters Physical Description Process Systems Radiation Reactor Physics Safety Thermalhydraulics Thermodynamics Waste Handling [Phase] Design Design Analysis Design Description Design Evolution Safety Safety Analysis [Audience] Engineer Grad Ugrad
    - A textbook on the CANDU nuclear power plant technology. press_release-Jan2016.pdf (382 kb)
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