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[SI]: 30000 Reactor, Steam Generators and Auxiliaries 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: 128

    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. 1958-09-01---------Jump to [Top]
  2. NPD-2 Design Description, OPG, 1958-09-01. Doc type: Report.
    Summary: This booklet presents a detailed design description of the NPD-2 station, a joint project of AECL, CGE and the Hydro-Electric Power Commission of Ontario.
    Keywords: [Concept] General [SI] 00000 General Project 30000 Reactor, Steam Generators and Auxiliaries 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Description [Audience] College Engineer High Technician Ugrad
    - Canada's First Nuclear Power Station CGE-NPD-DD-Sept1958.pdf (2766 kb)
    3. 1961-09-18---------Jump to [Top]
  3. NPD, a Description of, by J.L Olsen, OPG, 1961-09-18. Doc type: Presentation.
    Summary: Nuclear Power Demonstration. An illustrated talk presented at the Seventh AECL Symposium on Atomic Energy, Chalk River, September 18, 1961.
    Keywords: [Concept] General [SI] 00000 General Project 30000 Reactor, Steam Generators and Auxiliaries 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Description [Audience] College Engineer High Technician Ugrad
    - Canada's First Nuclear Power Station CAPD10--Sept1961NPD-Description.pdf (5637 kb)
    4. 1964-08-01---------Jump to [Top]
  4. 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)
  5. 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)
  6. 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)
    7. 1966-07-01---------Jump to [Top]
  7. 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)
    8. 1969-01-01---------Jump to [Top]
  8. Pickering Generating Station Design Description, OPG, 1969-01-01. Doc type: Report.
    Summary:
    Keywords: [Concept] Overview [SI] 00000 General Project 10000 Site and Improvements 20000 Buildings and Structures 30000 Reactor, Steam Generators and Auxiliaries 40000 Turbine, Generator and Auxiliaries 50000 Electric Power Systems 60000 Instrumentation and Control [Discipline] General Engineering Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Operation Safety [Audience] College Engineer Technician Ugrad
    - OH-PickeringDD1969.pdf (23589 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. 1981-11-01---------Jump to [Top]
  10. 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)
    11. 1982-06-01---------Jump to [Top]
  11. Chemistry, Course PI 24, OPG, 1982-06-01. Doc type: Course.
    Summary: Heavy water production, water composition and treatment, moderator water and cover gas chemistry, heat transport system aspects, heavy water leakage, environmental monitoring and control, chemical cleaning, chemical analysis.
    Keywords: [Concept] Chemistry and Corrosion [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Chemistry [Topic] Corrosion Heavy Water Purification Radiation [Phase] Design Operation [Audience] College Engineer Ugrad
    - 24.00-0 Course Index and Checkout 20042700.pdf (62 kb)
    - 24.11-1 Isotopic Separation - General, 20042701.pdf (58 kb)
    - 24.11-2 Isotopic Separation - Deuterium and Hydrogen, 20042702.pdf (71 kb)
    - 24.11-3 Fractional Distillation, 20042703.pdf (102 kb)
    - 24.12-0 Heavy Water Production - Enriching, 20042704.pdf (24 kb)
    - 24.13-0 Heavy Water Production - Finishing Process, 20042705.pdf (23 kb)
    - 24.21-2 Chemical Additives and Blowdown, 20042706.pdf (166 kb)
    - 24.21-3 Make-Up Water Treatment Plant, 20042707.pdf (227 kb)
    - 24.21-4 Secondary System Materials, 20042708.pdf (21 kb)
    - 24.22-1 Moderator Cover Gas System - System Materials, 20042709.pdf (22 kb)
    - 24.22-2 Moderator Water Chemistry, 20042710.pdf (52 kb)
    - 24.22-3 Moderator Water - Purification, 20042711.pdf (37 kb)
    - 24.22-4 Cover Gas - Purity, 20042712.pdf (96 kb)
    - 24.23-1 Primary Heat Transport System - Materials, 20042713.pdf (18 kb)
    - 24.23-2 Comissioning (chemical conditioning) of the Primary Heat Transport System, 20042714.pdf (96 kb)
    - 24.23-3 Primary Heat Transport System Chemical and Impurity Control, 20042715.pdf (154 kb)
    - 24.23-4 Transport of Radioactivity in Nuclear Reactors, 20042716.pdf (265 kb)
    - 24.41-1 Heavy Water Leakage - Detection, 20042717.pdf (92 kb)
    - 24.42-1Heavy Water Leakage - Recovery by Molecular Sieves, 20042718.pdf (42 kb)
    - 24.30-1 Radioactive Materials - Management, 20042719.pdf (321 kb)
    - 24.51-1 Environmental Monitoring - Radiological Emissions, 20042720.pdf (182 kb)
    - 24.51-2 Environmental Monitoring - Radiological Emission Measurement, 20042721.pdf (69 kb)
    - 24.52-1 Environmental Monitoring and Control - BHWP, 20042722.pdf (36 kb)
    - 24.52-2 Environmental Monitoring and Control - General, 20042723.pdf (40 kb)
    - 24.60-1 Chemical Cleaning of Fouled Equipment, 20042724.pdf (132 kb)
    - 24.61-1 Chemical Cleaning - NGD experience, 20042725.pdf (21 kb)
    - 24.61-1AI Decontamination of Douglas Pt. Reactor by CAN-DECON process, 20042726.pdf (313 kb)
    - 24.61-1AII H.E. Fouling and Cleaning Experience in Ontario Hydro's Nuclear Generating Divisions, 20042727.pdf (278 kb)
    - 24.61-1AIII Reference #3, 20042728.pdf (349 kb)
    - 24.70-0 Chemical Analysis - General, 20042729.pdf (190 kb)
    12. 1984-03-01---------Jump to [Top]
  12. 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)
    13. 1987-12-01---------Jump to [Top]
  13. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by A. Busigin and S. K. Sood, CNS-, 1987-12-01. Doc type: Paper.
    Summary: Ontario Hydro has constructed a Tritium Removal Facility (DTRF) at its Darlington Nuclear Generating Station to extract tritium from the heavy water moderator water of its CANDU heavy water nuclear reactors. This paper discusses the major process variables in the DTRF and how they affect system performance.
    Keywords: [Concept] - [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Chemical Engineering [Topic] Heavy Water [Phase] Operation [Audience] College Engineer Grad Technician Ugrad
    - Optimization of Darlington Tritium Removal Facility Performance: Effects of Key Process Variables NJC-1-4-12.pdf (230 kb)
    14. 1988-04-01---------Jump to [Top]
  14. 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)
    15. 1992-10-01---------Jump to [Top]
  15. Chemistry, Nuclear Training Course 224, OPG, 1992-10-01. Doc type: Course.
    Summary: Reviews the chemical technology fundamentals and addresses the chemistry-realated concerns of the condensate, feedwater and boiler system, the moderator system, the heat trnsport system, the liquid zone control system and the irradiated fuel bay.
    Keywords: [Concept] Chemistry and Corrosion [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Chemistry [Topic] Corrosion Heavy Water Purification Radiation [Phase] Design Operation [Audience] College Engineer Ugrad
    - Cover page, Table of contents, Introduction 20040800.pdf (382 kb)
    - A Review of 424, 20040801.pdf (753 kb)
    - The Condensate, Feedwater and Boiler System, 20040802.pdf (967 kb)
    - The Moderator and Auxiliary Systems, 20040803.pdf (1005 kb)
    - The Heat Transport and Auxiliary Systems, 20040804.pdf (511 kb)
    - Auxiliary Systems: Liquid Zone Control, Irradiated Fuel Bay, 20040805.pdf (447 kb)
    16. 1993-01-01---------Jump to [Top]
  16. 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)
    17. 1996-11-01---------Jump to [Top]
  17. CANDU Overiew, Course 3.2, by G. Bereznai, Chulalongkorn University, 1996-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Operation [Audience] College Engineer Ugrad
    - Chapter 0 - Title, Table of Contents, Objectives 20044201.pdf (89 kb)
    - Chapter 1 - Overall Unit, by G. Bereznai, 20044202.pdf (973 kb)
    - Chapter 2 - Reactor and Moderator, by G. Bereznai, 20044203.pdf (659 kb)
    - Chapter 3 - Reactor Control, by G. Bereznai, 20044204.pdf (881 kb)
    - Chapter 4 - Heat Transport, by G. Bereznai, 20044205.pdf (755 kb)
    - Chapter 5 - Steam, Turbine and Feedwater, by G. Bereznai, 20044206.pdf (666 kb)
    - Chapter 6 - Special Safety Systems, by G. Bereznai, 20044207.pdf (1131 kb)
    - Workbook, Chapter 0 - Table of Contents, Course Introduction, by G. Bereznai, 20044208.pdf (194 kb)
    - Workbook, Chapter 1 - Modules A to E, by G. Bereznai, 20044209.pdf (3559 kb)
    - Workbook, Chapter 2 - Modules A to C, by G. Bereznai, 20044210.pdf (688 kb)
    - Workbook, Chapter 3 - Modules A to C, by G. Bereznai, 20044211.pdf (2317 kb)
    - Workbook, Chapter 4 - Modules A to D, by G. Bereznai, 20044212.pdf (1115 kb)
    - Workbook, Chapter 5 - Modules A & B, by G. Bereznai, 20044213.pdf (1110 kb)
    - Workbook, Chapter 6 - Modules A to D, by G. Bereznai, 20044214.pdf (464 kb)
    18. 1997-04-01---------Jump to [Top]
  18. 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)
    19. 1997-10-01---------Jump to [Top]
  19. 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)
    20. 2002-01-01---------Jump to [Top]
  20. 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)
    21. 2005-05-01---------Jump to [Top]
  21. CANDU 6 Technical Summary, by AECL staff, AECL, 2005-05-01. Doc type: Report.
    Summary: This Technical Summary provides an overview of the CANDU 6 nuclear power system. All CANDU 6 power plants are fundamentally the same, although there are differences in detail: these largely result from different site conditions, and from improvements made in the newer designs. The evolution of CANDU 6 is illustrated in the inside back cover.
    Keywords: [Concept] - [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] General Engineering [Topic] Process Systems [Phase] Design [Audience] College Engineer High Manager Ugrad Vendor
    - CANDU6_TechnicalSummary-s.pdf (3750 kb)
    22. 2005-07-01---------Jump to [Top]
  22. Nuclear Power Plant Systems and Operation, by G. Bereznai, University of Ontario Institute of Technology, 2005-07-01. Doc type: Reference.
    Summary: Nuclear Power Plant Systems and Operation course covering following: science fundamentals, equipment and systems principles relevant to CANDU reactors; CANDU reactor power plant systems and their operation.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Operation [Audience] College Engineer Ugrad
    - 20071000.pdf (2511 kb)
    23. 2012-01-25---------Jump to [Top]
  23. Design and Safety of Canadian Nuclear Reactors, by V. Snell, UNENE, 2012-01-25. Doc type: Presentation.
    Summary:
    Keywords: [Concept] Safety [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety [Audience] Engineer Grad Manager Technician Ugrad
    - 20120101.pdf (11620 kb)
    24. 2015-01-01---------Jump to [Top]
  24. The Essential CANDU, by Wm.J. Garland, Editor-in-Chief, UNENE, 2015-01-01. Doc type: Book.
    Summary: The Essential CANDU is a textbook about nuclear science and engineering pertaining to CANDU reactors using CANDU as the reference design. This distinguishes it from comparable textbooks based on PWR reactors. This is not a product description of CANDU per se. The book emphasizes theory over other aspects of nuclear science. This is a textbook about CANDU nuclear reactor and power plant engineering, not just the reactor physics of the core.
    Keywords: [Concept] General [SI] 30000 Reactor, Steam Generators and Auxiliaries 35000 Fuel Transfer and Storage 36000 Steam Generator Steam and Water Systems 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Chemistry General Engineering Health Physics Nuclear Engineering [Topic] Corrosion Fluid Mechanics Fuel Management Heat Transfer Important Parameters Physical Description Process Systems Radiation Reactor Physics Safety Thermalhydraulics Thermodynamics Waste Handling [Phase] Design Design Analysis Design Description Design Evolution Safety Safety Analysis [Audience] Engineer Grad Ugrad
    - A textbook on the CANDU nuclear power plant technology. press_release-Jan2016.pdf (382 kb)
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