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[Topic]: Thermalhydraulics 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: 226

    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. 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)
    3. 1962-09-01---------Jump to [Top]
  3. Reactor Loops at Chalk River, by Ronald Needham, AECL, 1962-09-01. Doc type: Paper.
    Summary: Description of the Chalk River NRX and NRU in-reactor test loops for materials testing under simulated reactor power conditions.
    Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Materials Engineering Nuclear Engineering [Topic] Radiation Reactor Physics Thermalhydraulics [Phase] Concept [Audience] Engineer Technician Ugrad
    - CRL-Loops1962.pdf (1547 kb)
    4. 1966-11-01---------Jump to [Top]
  4. Reactor, Boiler and Auxiliaries, Course 133, Nuclear Training Center, OPG, 1966-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Full Course 20050900.pdf (10930 kb)
    - 133.00-00 Index, 20050901.pdf (252 kb)
    - 133.10-01 The Function of a Reactor, 20050902.pdf (262 kb)
    - 133.10-02 Reactor Classification - Fast and Thermal Reactors, 20050903.pdf (306 kb)
    - 133.10-03 Reactor Classification - Types of Thermal Reactors, 20050904.pdf (791 kb)
    - 133.10-04 Reactor Construction, 20050905.pdf (622 kb)
    - 133.20-01 Moderator Requirements, 20050906.pdf (227 kb)
    - 133.20-02 Moderator Materials Properties and Comparison, 20050907.pdf (459 kb)
    - 133.20-03 Moderator System and Equipment Considerations, 20050908.pdf (930 kb)
    - 133.30-01 Heat Transport Fluid Requirements, 20050909.pdf (401 kb)
    - 133.30-02 Heat Transport Fluid Comparisons, 20050910.pdf (600 kb)
    - 133.30-03 Main Circuit Considerations, 20050911.pdf (845 kb)
    - 133.30-04 Auxiliary Circuits, 20050912.pdf (708 kb)
    - 133.40-01 Reflector Systems, 20050913.pdf (367 kb)
    - 133.40-02 Shield Cooling Systems, 20050914.pdf (318 kb)
    - 133.50-01 Functions of Reactivity Mechanisms, 20050915.pdf (191 kb)
    - 133.50-02 Comparisons of Reactivity Mechanisms, 20050916.pdf (711 kb)
    - 133.62-01 Upgrading Requirements and Processes, 20050917.pdf (170 kb)
    - 133.62-02 Principles of Isotope Separation, 20050918.pdf (126 kb)
    - 133.62-03 The Distillation Upgrading Process, 20050919.pdf (258 kb)
    - 133.62-04 The Electrolytic Process, 20050920.pdf (149 kb)
    - 133.62-05 Common Problems, 20050921.pdf (183 kb)
    - 133.71-01 General Fuel Considerations, 20050922.pdf (190 kb)
    - 133.71-02 Fuel Preparation and Manufacture, 20050923.pdf (233 kb)
    - 133.71-03 Canadian Designs and Their Performance, 20050924.pdf (294 kb)
    - 133.91-01 Safety Standards and Safety Measures, 20050925.pdf (198 kb)
    - 133.91-02 Emergency Injection and Containment Systems, 20050926.pdf (160 kb)
    - 133.91-03 Safety System Performance, 20050927.pdf (199 kb)
    - 133.92-01Chemistry of Water Circuits, 20050928.pdf (940 kb)
    5. 1968-11-01---------Jump to [Top]
  5. Reactor Boiler and Auxiliaries, Course 433, Nuclear Training Centre, OPG, 1968-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Full Course 20051200.pdf (1786 kb)
    - 433.00-00 Index, 20051201.pdf (241 kb)
    - 433.10-01 Nuclear Power, 20051202.pdf (121 kb)
    - 433.10-02 Power Reactor Construction, 20051203.pdf (179 kb)
    - 433.20-01 Moderator Systems, 20051204.pdf (141 kb)
    - 433.30-01 Heat Transport Systems, 20051205.pdf (239 kb)
    - 433.40-01 Auxiliary Circuits, 20051206.pdf (205 kb)
    - 433.50-01 Fuel, 20051207.pdf (247 kb)
    - 433.50-02 Fuel Handling and Storage, 20051208.pdf (172 kb)
    - 433.60-01 Boiler Steam and Water Systems, 20051209.pdf (291 kb)
    6. 1969-01-02---------Jump to [Top]
  6. 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)
    7. 1970-03-09---------Jump to [Top]
  7. 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)
    8. 1972-05-25---------Jump to [Top]
  8. An Introduction to the CANDU Nuclear Energy Conversion System, by Archie Harms, McMaster University, 1972-05-25. Doc type: Book.
    Summary:
    Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Nuclear Engineering [Topic] Basic Equations Conceptual Intro and Overview Reactor Physics Thermalhydraulics [Phase] Concept Design Safety [Audience] College Engineer Technician Ugrad
    - Table of Contents and Chapter 1: Introduction 19750101.pdf (622 kb)
    - Chapter 2: Nuclear Processes, by Archie Harms, 19750102.pdf (493 kb)
    - Chapter 3: Neutron Physics, by Archie Harms, 19750103.pdf (567 kb)
    - Chapter 4: Reactor Statics, by Archie Harms, 19750104.pdf (650 kb)
    - Chapter 5: Reactor Dynamics, by Archie Harms, 19750105.pdf (428 kb)
    - Chapter 6: Control and Operations, by Archie Harms, 19750106.pdf (499 kb)
    - Chapter 7: Thermal-hydraulic Analysis, by Archie Harms, 19750107.pdf (439 kb)
    - Chapter 8: Nuclear Reactor Materials, by Archie Harms, 19750108.pdf (781 kb)
    - Chapter 9: Safety Analysis, by Archie Harms, 19750109.pdf (152 kb)
    - Chapter 10: CANDU Reactors part 1, by Archie Harms, 19750110.pdf (764 kb)
    - Chapter 10: CANDU Reactors part 2, by Archie Harms, 19750111.pdf (686 kb)
    9. 1975-07-01---------Jump to [Top]
  9. 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)
    10. 1976-03-01---------Jump to [Top]
  10. 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)
    11. 1977-04-01---------Jump to [Top]
  11. Reactor, Boilers and Auxiliaries, Nuclear Training Course 133, OPG, 1977-04-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Cover Page, Table of Contents, Basic Moderator Requirements 20041301.pdf (194 kb)
    - Moderator System & Equipment, 20041302.pdf (911 kb)
    - Basic Heat Transport Fluid Requirements, 20041303.pdf (274 kb)
    - Main Heat Transport Circuit Considerations, 20041304.pdf (1476 kb)
    - Auxiliary PHT System Features, 20041305.pdf (477 kb)
    - Shield Systems, 20041306.pdf (446 kb)
    - Annulus Gas System, 20041307.pdf (97 kb)
    - Containment Systems, 20041308.pdf (522 kb)
    - Reactivity Mechanisms, 20041309.pdf (233 kb)
    - Practical Reactivity Mechanisms, 20041310.pdf (161 kb)
    - Choice of Reactivity Mechanisms, 20041311.pdf (855 kb)
    - Fuel - Design and Manufacturing Features, 20041312.pdf (447 kb)
    - Fuel Performance and Operating Experience, 20041313.pdf (213 kb)
    12. 1978-01-01---------Jump to [Top]
  12. 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)
    13. 1978-08-01---------Jump to [Top]
  13. 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)
    14. 1980-01-01---------Jump to [Top]
  14. 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)
    15. 1981-01-01---------Jump to [Top]
  15. 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)
    16. 1981-04-01---------Jump to [Top]
  16. 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)
    17. 1981-11-01---------Jump to [Top]
  17. 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)
    18. 1982-01-01---------Jump to [Top]
  18. 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)
    19. 1984-03-01---------Jump to [Top]
  19. 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)
    20. 1984-12-01---------Jump to [Top]
  20. 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)
    21. 1987-04-01---------Jump to [Top]
  21. 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)
    22. 1987-09-01---------Jump to [Top]
  22. 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)
    - CATHENA Simulation of Thermosiphoning in a Pressurized-Water Test Facility, by J.P. Mallory and P.J. Ingham, NJC-1-3-05.pdf (615 kb)
    23. 1988-04-01---------Jump to [Top]
  23. 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)
    24. 1992-06-01---------Jump to [Top]
  24. Reactor Boiler and Auxiliaries, Course 233, Nuclear Training, OPG, 1992-06-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Full Course 20053800.pdf (13185 kb)
    - Abstract and Table of Contents, 20053801.pdf (162 kb)
    - Module 0 - Introduction, 20053802.pdf (269 kb)
    - Module 1 - Moderator Heavy Water, 20053803.pdf (359 kb)
    - Module 2 - Moderator Circulation System, 20053804.pdf (418 kb)
    - Module 3 - Moderator Cover Gas System, 20053805.pdf (387 kb)
    - Module 4 - The Moderator Liquid Poison System, 20053806.pdf (578 kb)
    - Module 5 - The Moderator Purification System, 20053807.pdf (486 kb)
    - Module 6 - HTS Heat Sources and Heat Transfer Paths, 20053808.pdf (362 kb)
    - Module 7 - HTS Pressure and Inventory Control, 20053809.pdf (1482 kb)
    - Module 8 - Heat Transport System Shutdown Operation, 20053810.pdf (609 kb)
    - Module 9 - HTS Heavy Water, 20053811.pdf (602 kb)
    - Module 10 - Heat Transport System Auxiliaries, 20053812.pdf (755 kb)
    - Module 11 - Shutdown Systems, 20053813.pdf (704 kb)
    - Module 12 - Emergency Coolant Injection, 20053814.pdf (663 kb)
    - Module 13 - Containment, 20053815.pdf (1004 kb)
    - Module 14 - Annulus Gas System, 20053816.pdf (407 kb)
    - Module 15 - Shield Cooling Systems, 20053817.pdf (528 kb)
    - Module 16 - Fuel Performance, 20053818.pdf (751 kb)
    - Module 17 - Fuel Handling, 20053819.pdf (616 kb)
    - Module 18 - Unit Upsets, 20053820.pdf (1950 kb)
    25. 1993-01-01---------Jump to [Top]
  25. 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)
    26. 1993-02-01---------Jump to [Top]
  26. Reactor, Boiler and Accessories, Course 233, OPG, 1993-02-01. Doc type: Course.
    Summary: Table of contents and Objectives for Course 233, Reactor, Boiler, and Auxiliaries.
    Keywords: [Concept] - [SI] 33000 Primary Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Reactor Physics Thermalhydraulics [Phase] Design [Audience] Engineer Technician
    - Table of Contents and Objectives 20042200.pdf (640 kb)
    - 233.20-1 Moderator and Main Moderator System, 20042201.pdf (485 kb)
    - 233.20-2 Moderator Purification, 20042202.pdf (241 kb)
    - 233.20-3 Moderator Cover Gas System, 20042203.pdf (202 kb)
    - 233.20-4 Moderator D2O Collection, 20042204.pdf (117 kb)
    - 233.20-5 Moderator Liquid Poison System, 20042205.pdf (343 kb)
    - 233.30-1 Heat Transport D2O and Heat Transport Main System, 20042206.pdf (284 kb)
    - 233.30-2 Heat Transport Pressurizing System, 20042207.pdf (277 kb)
    - 233.30-3 Heat Transport Purification, 20042208.pdf (235 kb)
    - 233.30-4 Heat Transport Gland Seal Circuit, 20042209.pdf (165 kb)
    - 233.30-5 Heat Transport Shutdown Cooling, 20042210.pdf (144 kb)
    - 233.30-6 Heat Transport Maintenance Cooling System, 20042211.pdf (56 kb)
    - 233.30-7 Heat Transport H2 Addition, 20042212.pdf (132 kb)
    - 233.30-8 Heat Transport Pressure Relief, 20042213.pdf (204 kb)
    - 233.30-9 Heat Transport D2O Collection, 20042214.pdf (100 kb)
    - 233.30-10 Heat Transport D2O Recovery, 20042215.pdf (113 kb)
    - 233.30-11 Emergency Coolant Injection System, 20042216.pdf (197 kb)
    - 233.30-12 Heat Sources and Transfer Paths, 20042217.pdf (271 kb)
    - 233.40-1 Shield Cooling Systems, 20042218.pdf (250 kb)
    - 233.40-2 Containment System, 20042219.pdf (462 kb)
    - 233.40-3 Annulus Gas System, 20042220.pdf (95 kb)
    - 233.60-1 Steam Supply System, 20042221.pdf (383 kb)
    - 233.70-1 Fuel Design and Manufacturing Features, 20042222.pdf (377 kb)
    - 233.70-2 Fuel Performance and Operating Features, 20042223.pdf (521 kb)
    27. 1995-08-01---------Jump to [Top]
  27. 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)
    28. 1996-02-01---------Jump to [Top]
  28. Reactor Thermalhydraulics Design, Course 2.1, by Wm.J. Garland, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: This course is concerned with the thennalhydraulic design of the process systems that are required to transport heat energy away from the nuclear reactor source and transform this heat energy into useful work (generally electrical energy).
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Basic Equations Important Parameters Process Systems Thermalhydraulics [Phase] Concept Design Design Analysis Design Evolution Design Process [Audience] Engineer Ugrad
    - Title and Table of Contents 20043701.pdf (170 kb)
    - Foreword and Glossary, by Wm.J. Garland, 20043702.pdf (74 kb)
    - Chapter 1 - Introduction, by Wm.J. Garland, 20043703.pdf (130 kb)
    - Chapter 2 - Design Requirements and Engineering Considerations, by Wm.J. Garland, 20043704.pdf (1189 kb)
    - Chapter 3 - Heat Transport System Thermalhydrauilics, by Wm.J. Garland, 20043705.pdf (447 kb)
    - Chapter 4 - Thermodynamics, by Wm.J. Garland, 20043706.pdf (309 kb)
    - Chapter 5 - Fuel Coolant Heat Transfer, by Wm.J. Garland, 20043707.pdf (245 kb)
    - Chapter 6 - Control, by Wm.J. Garland, 20043708.pdf (313 kb)
    - Chapter 7 - The Design Process, by Wm.J. Garland, 20043709.pdf (419 kb)
    - Chapter 8 - Process Design and Optimization, by Wm.J. Garland, 20043710.pdf (441 kb)
    - Appendix 1 - Comparison of Bruce A, B, & Darlington, by Wm.J. Garland, 20043711.pdf (223 kb)
  29. 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)
  30. 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)
    31. 1997-04-01---------Jump to [Top]
  31. 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)
    32. 1997-06-01---------Jump to [Top]
  32. 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)
    33. 1998-02-01---------Jump to [Top]
  33. 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)
  34. 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)
    35. 2002-01-01---------Jump to [Top]
  35. 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)
    36. 2003-04-20---------Jump to [Top]
  36. 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)
    37. 2004-04-20---------Jump to [Top]
  37. 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)
    38. 2006-03-01---------Jump to [Top]
  38. 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)
    39. 2006-04-01---------Jump to [Top]
  39. 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)
    40. 2015-01-01---------Jump to [Top]
  40. 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)
    41. 2017-12-27---------Jump to [Top]
  41. 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)
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