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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: 24

    1950-01-01---------Jump to [Top]
  1. 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)
    2. 1970-03-09---------Jump to [Top]
  2. 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)
    3. 1975-07-01---------Jump to [Top]
  3. FORSIM a FORTRAN Oriented Simulation Package for the Automated Solution of Partial and Ordinary partial Differential Equation SYSTEMS, by M.B. Carver, AECL, 1975-07-01. Doc type: Report.
    Summary: FORSIM was Mike's vehicle for all the work he did in PDEs/ODEs including stiff equation solvers, reactor kinetics and mass action chemical kinetics, sparse matrix approximation to the Jacobian, integration over discontinuities, and parameter identification. In about a dozen PPV papers. FORSIM started as just an ODE simulator to replace MIMIC for the AECL Sheridan Park engineers.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries 32000 Moderator System 33000 Primary Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics Mechanical Engineering [Topic] Basic Equations Collections Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - AECL 4608, November 1973 FORSIM_AECL4608.pdf (538 kb)
    4. 1978-01-01---------Jump to [Top]
  4. Efficient Integration over Discontinuities in Ordinary Differential Equation Simulation, by M.B. Carver, AECL, 1978-01-01. Doc type: Paper.
    Summary: Efficient integration algorithms for ordinary differential equations take integration steps that are as large as the error control criteria permit. Events or discontinuities in equation definition are often implicitly defined to occur when a variable reaches a critical value, for example a fuel rod surface reaching saturation temperature, and this requires the integrator to basically restart the calculation precisely at the point of change. Instead integrators will "hunt" for the discontinuity wasting a lot of computer time, and will eventually "step over" the discontinuity using integration points either side of the event. This paper shows that if the discontinuity is defined and monitored as an additional part of the equation set, such a restart can be optimized, thus ensuring that the event will be defined as an integration restart point.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Mathematics and Computers in Simulation, XX, 1978 efficient-integration-over-discontinuities-in-ordinary-differential-equation.pdf (467 kb)
    5. 1978-08-01---------Jump to [Top]
  5. The method of lines and the advective equation, by M.B. Carver and H.W. Hinds, AECL, 1978-08-01. Doc type: Paper.
    Summary: This article showed that the common approach of first order differencing, used in almost all thermalhydraulic computer programs, would not properly solve the simplest hyperbolic PDE on the market. Despite the errata, it is Carver's most cited publication and laid the foundations for many higher order analyses by others, and Carver's pseudo-characteristic method of lines (PCMOL) solution of the thermalhydraulic conservation equations.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Basic Equations Modelling Process Systems Thermalhydraulics [Phase] Concept Design Analysis Safety Analysis [Audience] Engineer Grad
    - Simulation, August,1978. Also published as AECL 6155 AdvectiveEqn.pdf (804 kb)
    6. 1980-01-01---------Jump to [Top]
  6. Pseudo-characteristic method of lines solution of first-order hyperbolic equation systems, by M.B. Carver, AECL, 1980-01-01. Doc type: Paper.
    Summary: This paper introduced a new concept, pseudo-characteristics, which allows the directionality dictated by the method of characteristics to be applied on a fixed grid basis. This is the method that N.P. Kolev Nuclear Institute of Bulgaria and M. B. Carver used to apply to the EVUT form of the thermalhydraulic conservation equations at the OECD/CSNI conference on two phase flow, Pasedena, 1981. In this MACS paper, discretization of the PDEs is discussed, using higher order upwind biased derivatives of each of the Lagrange polynomials and the Hermite polynomials. Results are shown for incompressible flow in a hydraulic jump and for compressible flow in the EVET thermalhydraulic conservation equations.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Mathematics and Computers in Simulation, 22, 1980 pseudo-characteristic-method-of-lines-solution-of-first-order-hyperbolic-equation.pdf (455 kb)
    7. 1981-01-01---------Jump to [Top]
  7. 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)
    8. 1981-04-01---------Jump to [Top]
  8. Thermal-Hydraulics in Recirculating Steam Generators: Thirst Code User's Manual, by M.B. Carver, AECL, 1981-04-01. Doc type: Report.
    Summary: THIRST is for modeling ThermalHydraulics In Recirculating Steam generators. This manual gives complete details of the mathematical derivation and numerical solution of the 3D, 2Phase thermalhydraulic equilibrium conservation equations inside a reactor boiler and also explains the many constitutive correlations required. Finally the manual fully defines the immense amount of input detail required to model the primary side heat transfer and the secondary side water boiling and recirculating in the complex tube-in-shell geometry of a prototypical CANDU steam generator.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - AECL 7254, April 1981 THIRSTusersR43667.pdf (2290 kb)
    9. 1982-01-01---------Jump to [Top]
  9. A Method of Limiting Intermediate Volume Fraction in Iterative Two-Fluid Computations, by M.B. Carver, AECL, 1982-01-01. Doc type: Paper.
    Summary: This is seminal and the core contribution in Carver's thesis. The ICE guys, Harlow & Amsden and the IPSA guys, Spalding & Patankar had not got it quite right for air/water conditions where the water totally dominates the pressure field calculation when it is based on mass flux balance, as this is dominated by the water component and neglects continuity of the air. Herein, a volumetric balance fixes that and the calculation also converges better with the constraint mentioned in the title.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Journal of Mechanical Engineering Science, Vol. 24, No. 2, 1982 limiting_volume_fraction_JMES_JOUR_1982.pdf (374 kb)
    10. 1987-03-01---------Jump to [Top]
  10. 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)
    11. 1987-06-01---------Jump to [Top]
  11. 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)
    12. 1987-12-01---------Jump to [Top]
  12. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by F.P. Vaccaro, G.J. 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, by W.G. Schneider, NJC-1-4-10.pdf (370 kb)
    13. 1995-08-01---------Jump to [Top]
  13. Numerical Solution of the Thermalhydraulic Conservation Equations from Fundamental Concepts to Multidimensional Analysis, by M.B. Carver, , 1995-08-01. Doc type: Report.
    Summary: This material was presented as part of a short course in Two-Phase Flow and Heat Transfer at McMaster University and is documented in report form for further reference. The discussion briefly establishes some requisite concepts of differential equation theory, and applies these to describe methods for numerical solution of the thennalhydraulic conservation equations in their various forms. The intent is to cover the general methodology without obscuring the principles with details. As a short overview of computational thermalhydraulics, the material provides an introductory foundation, so that those working on the application of thennalhydraulic codes can begin to understand the many intricacies involved without having to locate and read the references given. Those intending to work in code development will need to read and understand all the references.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Basic Equations Collections Conceptual Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Grad
    - AECL-11387, ARD-TD-550, Revision 1 (2017) to the original (1995) Carver AECL-11387[3628]-WithAddendum.pdf (6457 kb)
    14. 1997-04-01---------Jump to [Top]
  14. Software Quality Assurance: Practical Procedures to Meet CSA Standards, by M.B. Carver, CNSC, 1997-04-01. Doc type: Report.
    Summary: In the Canadian nuclear industry at the time, only the ASSERT code team and the NUCIRC team used definitive SQA (Software Quality Assurance), which identifies exactly what version of the computer code is being used for a given application, and every component used to build that version. A drive to apply such standards to all computer programs started in the 1990s, and Mike co-authored the 1995 AECL Reactor Development SQA manual. Upon his retirement, representatives of the then AECB (now CNSC) asked him to write a SQA guide for the industry that would bring all computer codes teams in line with CSA standards ( N286.7 & Q936).This report is CNSC-info-0669, 1997. To date the ASSERT-PV development team has followed these standards, the CATHENA team has not. Source attribution: Archived in the public domain at http://www.nuclearsafety.gc.ca/eng/about/past/timeline-dev/resources/documents/infohistorical/info-0669.pdf .
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Atomic Energy Control Board, Report INFO-0699, April 1997, http://www.nuclearsafety.gc.ca info-0669.pdf (3262 kb)
    15. 1997-06-01---------Jump to [Top]
  15. 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)
    16. 2003-04-20---------Jump to [Top]
  16. 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)
    17. 2004-04-20---------Jump to [Top]
  17. 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)
    - Associated Presentation, by J.M. Dyke, 20054202.pdf (1558 kb)
    18. 2004-07-17---------Jump to [Top]
  18. 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)
  19. 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)
    20. 2006-03-01---------Jump to [Top]
  20. Fretting Failures in Early Canadian Nuclear Steam Generators, by J.M. Dyke and Wm.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)
    21. 2006-04-01---------Jump to [Top]
  21. Evolution of CANDU Steam Generators – A Historical View, by J.M. Dyke and Wm.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)
    22. 2015-01-01---------Jump to [Top]
  22. 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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