|
Jump to year ->
[1950-01-01]
[1956-01-01]
[1961-04-01]
[1964-08-01]
[1964-11-01]
[1964-12-01]
[1965-01-01]
[1966-07-01]
[1968-01-01]
[1969-01-02]
[1970-03-09]
[1975-07-01]
[1976-03-01]
[1976-09-01]
[1977-01-01]
[1978-01-01]
[1978-04-01]
[1978-08-01]
[1980-01-01]
[1981-01-01]
[1981-04-01]
[1981-11-01]
[1982-01-01]
[1984-03-01]
[1984-12-01]
[1987-04-01]
[1987-06-01]
[1987-09-01]
[1987-12-01]
[1988-04-01]
[1990-01-01]
[1993-01-01]
[1994-07-01]
[1994-09-01]
[1995-08-01]
[1996-02-01]
[1996-12-05]
[1997-04-01]
[1997-06-01]
[1997-10-01]
[1998-02-01]
[1999-02-23]
[2002-01-01]
[2003-01-01]
[2003-04-20]
[2003-06-24]
[2004-01-01]
[2004-04-20]
[2004-07-17]
[2006-03-01]
[2006-04-01]
[2017-12-27]
[Discipline]: Mechanical Engineering 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: 286
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)
-
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)
-
Carver, M.B. - Selected Papers and Reports, by M.B. Carver, AECL, 1950-01-01. Doc type: Essay.
Summary: Michael B. Carver, Bachelor of Mechanical Engineering, McMaster University 1963, Athlone fellow MSc in thermodynamics, University of Birmingham (UK) 1965, Ph.D Mechanical Engineering, University of Ottawa 1987. Joined AECL, Chalk River Nuclear Laboratories in November, 1965 - chosen because of its location deep in the backwoods, on the OTTAWA river giving lots of opportunity for outdoor activities. AECL was then a great place to do 'Prestige R&D' and indulge in research in a number of fields. Mike traveled to nuclear conferences all over the Northern Hemisphere, giving presentations on his research. There was something about that atmosphere that made him publish poetry as well. And maybe it was the poet in him that came up with the computer code acronyms THIRST and ASSERT. See also https://www.researchgate.net/profile/Michael_Carver3. As a nuclear reactor relies entirely on fluid circuits for energy transfer, mathematical modeling of thermalhydraulic phenomena plays an important role in reactor design, development, safety and Dynamics (CFD) is, thus, of central importance to nuclear power plant systems. Mike spent his career improving CFD mathematical algorithms. His seminal contributions are given herein.
Keywords: [Concept] - [SI] 30000 Reactor, Steam Generators and Auxiliaries 33000 Primary Heat Transport System [Discipline] Mechanical Engineering [Topic] - [Phase] - [Audience] -
- Introduction Carver-intro.pdf (268 kb)
1956-01-01---------Jump to [Top]
-
The Pressurized Water Reactor as a Source of Heat for Steam Power Plants, by J.M. Kay and F.J. Hutchinson, IMechE, 1956-01-01. Doc type: Paper.
Summary: Published in the Proceedings of the Institution of Mechanical Engineers Volume 170 1956 pps 281 - 297
Keywords: [Concept] - [SI] 09000 Special Studies [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Conceptual Heat Transfer Thermodynamics [Phase] Concept Design Operation [Audience] Engineer Ugrad Vendor
- Published in the Proceedings of the Institution of Mechanical Engineers Volume 170 1956 pps 281 - 296 20054600.pdf (2333 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)
1964-08-01---------Jump to [Top]
-
Heat and Thermodynamics, Course 1-2.5, Nuclear Electric GS Technical Training Course, by D. Dueck, OPG, 1964-08-01. Doc type: Course.
Summary: Basic concepts of thermodynamics
Keywords: [Concept] Mechanical [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Full course, sections 1 to 8. NEGS-TT1-2-5-1964.pdf (7809 kb)
-
Heat and Thermodynamics, Course 2-2.5, Nuclear Electric GS Technical Training Course, by D. Dueck, OPG, 1964-08-01. Doc type: Course.
Summary: Basic concepts of thermodynamics
Keywords: [Concept] Mechanical [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Concept Design Design Analysis [Audience] College Ugrad
- Full course, sections 1 to 10. NEGS-TT2-2-5-1964.pdf (3387 kb)
-
Heat and Thermodynamics, Course 1-2.5, Nuclear Electric GS Technical Training Course, by D. Dueck, OPG, 1964-08-01. Doc type: Course.
Summary: Basic concepts of thermodynamics
Keywords: [Concept] Mechanical [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Full course, sections 1 to 10. NEGS-TT3-2-5-1964.pdf (4826 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)
1966-07-01---------Jump to [Top]
-
Heat and Thermodynamics, Course 1A25, Nuclear Training Course , by George Howie, OPG, 1966-07-01. Doc type: Course.
Summary: Basic concepts of thermodynamics
Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermodynamics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Full course, sections 1 to 10. OH-1A25-1966.pdf (5569 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)
1969-01-02---------Jump to [Top]
-
The Effect of Bypass Characteristics on Parallel Channel Flow Instabilities, by M.B. Carver, AECL, 1969-01-02. Doc type: Paper.
Summary: This article is definitive because nobody could figure out why all the instability codes gave stability thresholds well below the measured threshold power in the experiments done at Canadian Westinghouse. The paper determines analytically that this is because the small bypass stabilized the experimental system as it could not maintain a constant pressure drop, which all the codes assumed at step 1.
Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics Mechanical Engineering [Topic] Basic Equations Collections Conceptual Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
- Proceedings of the Institution of Mechanical Engineers, Volume 184, 1969 BYPASS PIME_CONF_1969_184_083_02.pdf (703 kb)
1970-03-09---------Jump to [Top]
-
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)
1975-07-01---------Jump to [Top]
-
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)
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)
1977-01-01---------Jump to [Top]
-
Fluid Mechanics, Nuclear Training Course 223, January 1977, OPG, 1977-01-01. Doc type: Course.
Summary: Basic fluid mechanics concepts (viscosity, friction, water hammer, pipe flow, lubrication).
Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Course Objectives 20040300.pdf (82 kb)
- Force - Momentum, 20040306.pdf (90 kb)
- Water Hammer, 20040307.pdf (226 kb)
1978-01-01---------Jump to [Top]
-
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)
1978-04-01---------Jump to [Top]
-
Fluid Mechanics, Nuclear Training Course 123, April 1978, OPG, 1978-04-01. Doc type: Course.
Summary: Basic fluid mechanics concepts (viscosity, friction, water hammer, pipe flow, lubrication).
Note: Doc# 20040201 through to 20040205 are identical to OPG 223.00-1, rev January 1977 (see Doc# 20040301 through to 20040305
Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Course Objectives 20040200.pdf (87 kb)
- Parallel Pipe Flow, 20040206.pdf (202 kb)
- Compressible Flow, 20040207.pdf (285 kb)
- Water Hammer, 20040208.pdf (265 kb)
- Hydrodynamic Film Lubrication, 20040209.pdf (562 kb)
-
Fluid Mechanics, Nuclear Training Course 223, January 1977, OPG, 1978-04-01. Doc type: Course.
Summary:
Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Viscosity 20040301.pdf (147 kb)
- Reynolds' Number, 20040302.pdf (105 kb)
- Friction in Fluid Flow, 20040303.pdf (301 kb)
- Minor Losses, 20040304.pdf (213 kb)
- Pipe Flow Problems, 20040305.pdf (132 kb)
- Appendix, 20040308.pdf (489 kb)
1978-08-01---------Jump to [Top]
-
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)
1980-01-01---------Jump to [Top]
-
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)
1981-01-01---------Jump to [Top]
-
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)
1981-04-01---------Jump to [Top]
-
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)
1981-11-01---------Jump to [Top]
-
Heat and Thermodynamics, Course 125, Nuclear Training Centre, OPG, 1981-11-01. Doc type: Course.
Summary: Basic concepts of heat and thermodynamics: steam tables, Mollier diagrams, turbine, feedheater, condenser, steam generator, reactor.
Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Full Course 20050100.pdf (6328 kb)
- Module B.7 Course Procedures, 20050101.pdf (302 kb)
- Module B.6 Basics, 20050102.pdf (339 kb)
- Module B.5 Steam Tables, 20050103.pdf (740 kb)
- Module B.4.2 Entropy, Throttling and Molier Diagram, 20050104.pdf (904 kb)
- Module B.4.1 Turbine With Reheat, 20050105.pdf (684 kb)
- Module B.3.2 Feedheater Operation, 20050106.pdf (569 kb)
- Module B.3.1 Condenser Performance, 20050107.pdf (594 kb)
- Module B.2 Steam Generator, 20050108.pdf (477 kb)
- Module B.1 Reactor, 20050109.pdf (826 kb)
- B.6 Self Evaluation, 20050110.pdf (87 kb)
- B.5 Self Evaluation, 20050111.pdf (69 kb)
- B.4.2 Self Evaluation, 20050112.pdf (118 kb)
- B.4.1 Self Evaluation, 20050113.pdf (103 kb)
- B.3.2 Self Evaluation, 20050114.pdf (121 kb)
- B.3.1 Self Evaluation, 20050115.pdf (118 kb)
- B.2 Self Evaluation, 20050116.pdf (137 kb)
- B.1 Self Evaluation, 20050117.pdf (102 kb)
- Criterion Tests, 20050118.pdf (134 kb)
1982-01-01---------Jump to [Top]
-
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)
1984-03-01---------Jump to [Top]
-
Heat and Thermodynamics, Course PI 25, Nuclear Training Centre, OPG, 1984-03-01. Doc type: Course.
Summary: Basic concepts of heat and thermodynamics: expansion and contraction, heat transfer, pressure control, Mollier diagrams, efficiency, the CANDU cycle.
Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Full Course 20050200.pdf (3028 kb)
- 25-0 Introduction and Course Procedures, 20050201.pdf (336 kb)
- 25-1 Basics, 20050202.pdf (471 kb)
- 25-2 Expansion and Contraction, 20050203.pdf (351 kb)
- 25-3 Heat Transfer Calculations, 20050204.pdf (183 kb)
- 25-4 Pressure Control, 20050205.pdf (200 kb)
- 25-5 Mechanisms of Heat Transfer, 20050206.pdf (144 kb)
- 25-6 Mollier Diagrams and The Turbine Process, 20050207.pdf (679 kb)
- 25-7 Efficiency and The CANDU Cycle, 20050208.pdf (298 kb)
- 25-8 Criterion Tests, 20050209.pdf (105 kb)
- 25-9 Self Evaluation Answer Sheet, 20050210.pdf (309 kb)
1984-12-01---------Jump to [Top]
-
Fluid Mechanics, Nuclear Training Course 223, December 1984, OPG, 1984-12-01. Doc type: Course.
Summary: These sections provide definitions and sample calculations for basic concepts such as pressure, density, flowrate, etc. and are NOT the same as the corresponding sections in the January 1977 version of 223.
Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fuel Management [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Course Objectives 20040400.pdf (29 kb)
- Fluid Mechanics, 20040401.pdf (599 kb)
- Answer Section, 20040402.pdf (407 kb)
-
Two Dimensional Modelling of the Homogenizing Effects of Flow Obstructions in Two Fluid Flow, by M.B. Carver and M. E. Salcudean, AECL, 1984-12-01. Doc type: Paper.
Summary: It is well known that obstructions in two fluid flow have the effect of homogenizing the two fluid mixture, resulting not only in a more uniform phase distribution, but also in a significant reduction of the ratio of fluid velocities. This paper describes a 2D, 2Fluid computer program written by the first author to do proof of principal studies of 2fluid redistribution around bends and past obstacles. The details necessary for modelling air/water flows in these geometries have been introduced here before extending the work to 3D. The paper shows that these phase redistribution effects can be modelled using the two fluid computer program, and compares results to those obtained in a recent experiment on flow past obstructions.
Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
- Mathematics and Computers in Simulation 26(6):pp 475–484, December 1984 two-dimensional-modelling-of-the-homogenizing-effects-of-flow-obstructions.pdf (1202 kb)
1987-04-01---------Jump to [Top]
-
Development and Application of a Three-Dimensional Two-Fluid Numerical Algorithm for Simulation of Phase Redistribution by Bends and Obstructions, by M.B. Carver, AECL, 1987-04-01. Doc type: Other.
Summary: Mike completed his Ph.D in parallel to his full time position at AECL as branch head of Applied Mathematics at CRNL. Upon completion he was appointed adjunct professor at McMaster and was co-supervisor of two degrees.
Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics#Mechanical Engineering [Topic] Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
- Ph.D Thesis, Department of Mechanical Engineering, University of Ottawa, April 1987 ThesisNL56352.pdf (4350 kb)
1987-06-01---------Jump to [Top]
-
Nuclear Journal of Canada, 1987 Vol 1 No. 2, by M.B. Carver, R.A. Judd, J.E. Kiteley, and A. Tahir, CNS-, 1987-06-01. Doc type: Paper.
Summary: The ASSERT subchannel code has been developed specifically to model flow and phase distributions within CANDU fuel bundles. ASSERT uses a drift-flux model that permits the phases to have unequal velocities, and can thus model phase separation tendencies that may occur in horizontal flow. The basic principles of ASSERT are outlined, and computed results are compared against data from various experiments for validation purposes. The paper concludes with an example of the use of the code to predict critical heat flux in CANDU geometries.
Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Fluid Mechanics [Phase] Design Analysis [Audience] Engineer Grad Ugrad
- The Drift Flux Model in the ASSERTSubchannel Code NJC-1-2-08.pdf (742 kb)
1987-09-01---------Jump to [Top]
-
Nuclear Journal of Canada, 1987 Vol 1 No. 3, by S. Banerjee, CNS-, 1987-09-01. Doc type: Paper.
Summary: The multifield model, in which separate sets of conservation equations are written for each phase, or clearly identifiable portion of a phase, is derived and explored.
Keywords: [Concept] Thermalhydraulics [SI] 03000 Engineering Science and Technology [Discipline] Mechanical Engineering [Topic] Basic Equations Modelling Thermalhydraulics [Phase] Design Analysis [Audience] Engineer Grad
- Multifield Methods for Nuclear Thermalhydraulics Problems NJC-1-3-04.pdf (1030 kb)
1987-12-01---------Jump to [Top]
-
Nuclear Journal of Canada, 1987 Vol 1 No. 4, by Matija Cenanovic and Hugo Maureira, CNS-, 1987-12-01. Doc type: Paper.
Summary: Proper spacing between the pressure tube and the surrounding calandria tube of the fuel channels in CANDU reactors is maintained by spacers (garter springs). It was established that many garter springs are no longer in their correct positions in Ontario Hydro's operating reactors. A novel AC device was developed at Ontario Hydro Research Division to reposition the garter springs without any harmful effect on the fuel channel integrity.
Keywords: [Concept] Mechanical [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] - [Phase] Operation [Audience] College Engineer Grad Manager Technician Ugrad
- The AC Device for Repositioning of Garter Springs in CANDU Reactors NJC-1-4-09.pdf (696 kb)
- Waterlancing for CANDU Steam Generators, by W.G. Schneider, NJC-1-4-10.pdf (370 kb)
1988-04-01---------Jump to [Top]
-
Heat and Thermodynamics, Course 225, Nuclear Training Centre, OPG, 1988-04-01. Doc type: Course.
Summary: Basic concepts of heat and thermodynamics: steam tables, Mollier diagrams, turbine with reheat, feedheater, condenser, steam generator, reactor.
Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Full Course 20043100.pdf (4667 kb)
- Index, 20043101.pdf (208 kb)
- Module 1 Basics, 20043102.pdf (404 kb)
- Module 2 Steam Tables, 20043103.pdf (636 kb)
- Module 3 Entropy, Throttling and Mollier Diagrams, 20043104.pdf (701 kb)
- Module 4 Turbine with Reheat, 20043105.pdf (611 kb)
- Module 5 Feedheater Operation, 20043106.pdf (511 kb)
- Module 6 Condenser Performance, 20043107.pdf (546 kb)
- Module 7 Steam Generator, 20043108.pdf (382 kb)
- Module 8 Reactor, 20043109.pdf (710 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)
-
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)
1993-01-01---------Jump to [Top]
-
Principes de Science et de Fonctionnement des Réacteurs - Chaleur et Thermodynamique, CNSC, 1993-01-01. Doc type: Course.
Summary:
Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Chaleur et Thermodynamique 20070900.pdf (850 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)
1995-08-01---------Jump to [Top]
-
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)
1996-02-01---------Jump to [Top]
-
Thermal Study of Nuclear Reactors, Course 2.2, by A. Tapucu, Chulalongkorn University, 1996-02-01. Doc type: Course.
Summary:
Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Design Design Analysis [Audience] Engineer Grad Ugrad
- Title and Table of Contents 20043801.pdf (96 kb)
- Chapter 1 - Fundamental Concepts, by A. Tapucu, 20043802.pdf (234 kb)
- Chapter 2 - Single Phase Fluid Equations, by A. Tapucu, 20043803.pdf (200 kb)
- Chapter 3 - Principles of Heat Transfer, by A. Tapucu, 20043804.pdf (1061 kb)
- Chapter 4 - Forced Convection Heat Transfer, by A. Tapucu, 20043805.pdf (1624 kb)
- Chapter 7 - Heat Removal from Nuclear Reactors, by A. Tapucu, 20043806.pdf (1557 kb)
- Appendix 1 - Tensors, by A. Tapucu, 20043807.pdf (49 kb)
- Appendix 2 - Stress in a Fluid, by A. Tapucu, 20043808.pdf (256 kb)
- Appendix 3 - A Short Summary of Orthogonal Functions Used in Chapter 4, by A. Tapucu, 20043809.pdf (178 kb)
- Workbook, Chapter 4, by A. Tapucu, 20043810.pdf (2301 kb)
- Workbook, Chapter 7, by A. Tapucu, 20043811.pdf (2043 kb)
-
Reactor Thermalhydraulics Analysis, Course 2.3, by Wm.J. Garland, Chulalongkorn University, 1996-02-01. Doc type: Course.
Summary: Fundamentals of thermalhydraulic analysis (heat transfer and fluid mechanics)of the heat transport system.
Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
- Title and Table of Contents 20043901.pdf (144 kb)
-
Welding Technology, Course 7.5, by I. Grant, Chulalongkorn University, 1996-02-01. Doc type: Course.
Summary: Appreciation of metal joining techniques: wleding, welding processes, weldment quality, symbols on drawings, nondestructive examination, and codes and standards.
Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
- Chapter 01 - Introduction 20053401.pdf (1359 kb)
- Chapter 02 - Specification – Covered Carbon Steel Electrodes, by I. Grant, 20053402.pdf (2022 kb)
- Chapter 03 - Submerged Arc Welding, by I. Grant, 20053403.pdf (1118 kb)
- Chapter 04 - Gas Metal Arc Welding, by I. Grant, 20053404.pdf (949 kb)
- Chapter 05 - Plasma Welding, by I. Grant, 20053405.pdf (119 kb)
- Chapter 06 - Electrical Power Sources, by I. Grant, 20053406.pdf (551 kb)
- Chapter 07 - Welding Stainless Steel Tubing, by I. Grant, 20053407.pdf (473 kb)
- Chapter 08 - Thermal Efficiency of Arc Welding Processes, by I. Grant, 20053408.pdf (737 kb)
- Chapter 09 - Solidification Structures & Properties of Fusion Welds, by I. Grant, 20053409.pdf (3163 kb)
- Chapter 10 - Prediction of Welding Distortion, by I. Grant, 20053410.pdf (618 kb)
- Chapter 11 - Material & Fabrication Considerations for CANDU Heat Transport Systems, by I. Grant, 20053411.pdf (1808 kb)
- Chapter 13 - Fitness for Purpose, by I. Grant, 20053413.pdf (858 kb)
- Chapter 14 - Welding Variables Procedure Specs, by I. Grant, 20053414.pdf (965 kb)
- Chapter 17 - Calculating Force/Unit Length on Welds, by I. Grant, 20053417.pdf (773 kb)
- Chapter 18 - Design for Welding, by I. Grant, 20053418.pdf (569 kb)
- Chapter 19 - Design and Construction Methods for Welded Steel Merchant Vessels, by I. Grant, 20053419.pdf (313 kb)
- Workbook 01 - Welding Technologyes), by I. Grant, 20053420.pdf (240 kb)
- Workbook 02 - Flux Shielded Welding Processes, by I. Grant, 20053421.pdf (549 kb)
- Workbook 03 - Submerged Arc Welding, by I. Grant, 20053422.pdf (636 kb)
- Workbook 04 - Gas Metal Arc Welding, by I. Grant, 20053423.pdf (497 kb)
- Workbook 05 - Plasma Arc Welding, by I. Grant, 20053424.pdf (169 kb)
- Workbook 06 - Welding Power Supplies & Controls, by I. Grant, 20053425.pdf (262 kb)
- Workbook 07 - Arc Physics and Weld Pool Behaviour, by I. Grant, 20053426.pdf (281 kb)
- Workbook 08 - Heat Flow in Welding, by I. Grant, 20053427.pdf (262 kb)
- Workbook 09 - Metallurgical Effects of the Weld Thermal Cycle, by I. Grant, 20053428.pdf (1172 kb)
- Workbook 10 - Distortion, Residual Stress & Post-Weld Heat Treatment, by I. Grant, 20053429.pdf (361 kb)
- Workbook 11 - Weldability of Structural Steels, by I. Grant, 20053430.pdf (535 kb)
- Workbook 12 - Weld Discontinuities, by I. Grant, 20053431.pdf (923 kb)
- Workbook 13 - Inspection & Testing, by I. Grant, 20053432.pdf (327 kb)
- Workbook 14 - Welding Qualification & Certification, by I. Grant, 20053433.pdf (480 kb)
- Workbook 15 - Design for Welding, by I. Grant, 20053434.pdf (605 kb)
- Workbook 16 - Weld Symbols on Drawings, by I. Grant, 20053435.pdf (531 kb)
- Workbook 17 Static Strength of Welded Joints, by I. Grant, 20053436.pdf (443 kb)
- Workbook 18 - Fatigue Failure of Welded Joints, by I. Grant, 20053437.pdf (557 kb)
- Workbook 19 - Fracture of Welded Structures, by I. Grant, 20053438.pdf (539 kb)
1996-12-05---------Jump to [Top]
-
Non-Destructive Testing, Course 7.2, by E. Hussein, Chulalongkorn University, 1996-12-05. Doc type: Course.
Summary: Nondestructive testing including ultrasonics, magnetic flux leakage, eddy current, radiography, acoustic emission, and microwaves.
Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
- Chapter 00 - Table of Contents 20053101.pdf (162 kb)
- Chapter 01 - Introduction, by E. Hussein, 20053102.pdf (220 kb)
- Chapter 02 - Ultrasonics, by E. Hussein, 20053103.pdf (670 kb)
- Chapter 03 - Magnetic Flux Leakage, by E. Hussein, 20053104.pdf (301 kb)
- Chapter 04 - Eddy Current (pdf 340 kb, 20 pages), by E. Hussein, 20053105.pdf (369 kb)
- Chapter 05 - Radiography, by E. Hussein, 20053106.pdf (409 kb)
- Chapter 06 - Acoustic Emission, by E. Hussein, 20053107.pdf (305 kb)
- Chapter 07 - Microwaves, by E. Hussein, 20053108.pdf (145 kb)
1997-04-01---------Jump to [Top]
-
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)
1997-06-01---------Jump to [Top]
-
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)
1997-10-01---------Jump to [Top]
-
Reactor Mechanical Design, Course 3.6, by R.S. Porter, Chulalongkorn University, 1997-10-01. Doc type: Course.
Summary:
Keywords: [Concept] - [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Mechanical Engineering [Topic] Conceptual Physical Description [Phase] Concept Design [Audience] Engineer Grad Ugrad
- Section 0 - Title, Table of Contents 20044601.pdf (99 kb)
- Section 1 - Overview, Reg. Req’ts, Codes & Standards, by R.S. Porter, 20044602.pdf (531 kb)
- Section 2 - Design Philosophy, Rationale, Key Operating Parameters, by R.S. Porter, 20044603.pdf (481 kb)
- Section 3 - Stress Analysis of Reactor Structures, by R.S. Porter, 20044604.pdf (253 kb)
- Section 4 - Excitation Spectra Etc., by R.S. Porter, 20044605.pdf (374 kb)
- Section 5 - Design of Fuel Channels, by R.S. Porter, 20044606.pdf (622 kb)
- Section 6 - Design of Reactivity Control Units, by R.S. Porter, 20044607.pdf (1181 kb)
- Section 7 - Design of Fuel Handling System, by R.S. Porter, 20044608.pdf (1121 kb)
- Appendix 1 - Design Loads and Load Cases for CANDU 6, by R.S. Porter, 20044609.pdf (174 kb)
- Appendix 2 - Stresses for Design Cases, by R.S. Porter, 20044610.pdf (316 kb)
- Appendix 3 - Finite Element Analysis, by R.S. Porter, 20044611.pdf (96 kb)
- Appendix 4 - Seismic Behaviour of CANDU 6, by R.S. Porter, 20044612.pdf (168 kb)
- Workbook, Chapter 1 - Figures, by R.S. Porter, 20044613.pdf (208 kb)
- Workbook, Chapter 2 - Figures, by R.S. Porter, 20044614.pdf (778 kb)
- Workbook, Chapter 3 - Figures, by R.S. Porter, 20044615.pdf (355 kb)
- Workbook, Chapter 4 - Figures, by R.S. Porter, 20044616.pdf (455 kb)
- Workbook, Chapter 5 - Figures, by R.S. Porter, 20044617.pdf (150 kb)
- Workbook, Chapter 6 - Figures, by R.S. Porter, 20044618.pdf (964 kb)
- Workbook, Chapter 7 - Figures, by R.S. Porter, 20044619.pdf (1006 kb)
1998-02-01---------Jump to [Top]
-
Reactor Thermalhydraulics Analysis, Course 2.3, by Wm.J. Garland, Chulalongkorn University, 1998-02-01. Doc type: Course.
Summary:
Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
- Glossary and Foreword 20043902.pdf (152 kb)
- Chapter 1 - Course Overview, by Wm.J. Garland, 20043903.pdf (140 kb)
- Chapter 2 - Basic Equations for Thermalhydraulic Systems Analysis, by Wm.J. Garland, 20043904.pdf (561 kb)
- Chapter 3 - Nodalization, by Wm.J. Garland, 20043905.pdf (303 kb)
- Chapter 4 - Equation of State, by Wm.J. Garland, 20043906.pdf (338 kb)
- Chapter 5 - The Rate Form of the Equation of State, by Wm.J. Garland, 20043907.pdf (512 kb)
- Chapter 6 - Thermalhydraulic Network Simulation, by Wm.J. Garland, 20043908.pdf (343 kb)
- Chapter 7 - Empirical Correlations, by Wm.J. Garland, 20043909.pdf (532 kb)
- Chapter 8 - On Design Tools, by Wm.J. Garland, 20043910.pdf (481 kb)
- Workbook, Chapter 1, by Wm.J. Garland, 20043911.pdf (151 kb)
- Workbook Chapter, 2, by Wm.J. Garland, 20043912.pdf (767 kb)
- Workbook Chapter 3, by Wm.J. Garland, 20043913.pdf (466 kb)
- Workbook Chapter 4, by Wm.J. Garland, 20043914.pdf (604 kb)
- Workbook Chapter 5, by Wm.J. Garland, 20043915.pdf (847 kb)
- Workbook Chapter 6, by Wm.J. Garland, 20043916.pdf (614 kb)
- Workbook Chapter 7, by Wm.J. Garland, 20043917.pdf (719 kb)
- Workbook Chapter 8, by Wm.J. Garland, 20043918.pdf (903 kb)
- Workbook Figures, by Wm.J. Garland, 20043919.pdf (509 kb)
-
Reactor Thermalhydraulics Analysis, Supplementary, Course 2.3a, by Wm.J. Garland, Chulalongkorn University, 1998-02-01. Doc type: Course.
Summary: Supplementary info for thermalhydraulic analysis (heat transfer and fluid mechanics)of the heat transport system.
Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
- Appendices 1 - 4 1 - Time Derivatives 2 - The Reynolds Transport Theorem 3 - Rearrangement of Independent Variables 4 - Fast Calculation of Light-Water Properties 20044001.pdf (647 kb)
- Calculation of Water Properties, by Wm.J. Garland, 20044002.pdf (947 kb)
- THSIM User Manual, by Wm.J. Garland, 20044003.pdf (733 kb)
- A Pedagogical Look at Fully- and Semi-Implicit Solutions to T-H Eq'ns, by Wm.J. Garland, 20044004.pdf (320 kb)
- Basic Equations for T-H Systems Analysis, by Wm.J. Garland, 20044005.pdf (590 kb)
- Miscellaneous Figures and Equations, by Wm.J. Garland, 20044006.pdf (315 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)
2002-01-01---------Jump to [Top]
-
Mechanical Equipment Course, CNSC, 2002-01-01. Doc type: Course.
Summary:
Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
- Cover Page 20030200.pdf (86 kb)
- , 20030201.pdf (1463 kb)
- Vibrations, 20030202.pdf (1123 kb)
- Valves, 20030203.pdf (2952 kb)
- Flowsheets, 20030204.pdf (1693 kb)
-
Heat and Thermodynamics Course, CNSC, 2002-01-01. Doc type: Course.
Summary: This module covers the following areas pertaining to thermodynamics: Introduction, Heat and Thermodynamics - The Basics, Reactor and Heat Transport System Normal Operation, Heat Transport System Component Operation
Keywords: [Concept] Heat and Thermodynamics [SI] 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries [Discipline] Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Cover Page 20030900.pdf (83 kb)
- , 20030901.pdf (647 kb)
- Presentation, 20030902.pdf (1557 kb)
2003-01-01---------Jump to [Top]
-
Principes de Science et de Fonctionnement des Réacteurs - Équipement Mécanique, CNSC, 2003-01-01. Doc type: Course.
Summary:
Keywords: [Concept] Mechanical [SI] - [Discipline] Mechanical Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
- Équipement Mécanique 20070700.pdf (954 kb)
2003-04-20---------Jump to [Top]
-
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)
2003-06-24---------Jump to [Top]
-
Fluid Mechanics, CNSC, 2003-06-24. Doc type: Course.
Summary:
Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fluid Mechanics [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
- Presentation 20040602.pdf (610 kb)
- , 20040601.pdf (353 kb)
- , 20070300.pdf (336 kb)
2004-04-20---------Jump to [Top]
-
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)
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)
2006-03-01---------Jump to [Top]
-
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)
2006-04-01---------Jump to [Top]
-
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)
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)
|
|