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[SI]: 33000 Primary Heat Transport System 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: 100

    1950-01-01---------Jump to [Top]
  1. 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)
    2. 1966-11-01---------Jump to [Top]
  2. 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)
    3. 1968-11-01---------Jump to [Top]
  3. 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)
    4. 1975-07-01---------Jump to [Top]
  4. 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)
    5. 1977-04-01---------Jump to [Top]
  5. 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)
    6. 1992-06-01---------Jump to [Top]
  6. 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)
    7. 1993-02-01---------Jump to [Top]
  7. 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)
    8. 1999-02-23---------Jump to [Top]
  8. 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)
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