Jump to year -> [1958-09-01] [1962-09-24] [1968-05-01] [1969-01-01] [1971-03-01] [1971-09-06] [1975-07-01] [1976-03-01] [1980-01-01] [1981-04-01] [1991-08-01] [1995-08-01] [1997-04-01] [1997-08-01] [2002-01-01] [2005-05-01] [2010-01-01]
[DocType]: Report 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: 27

    1958-09-01---------Jump to [Top]
  1. 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)
    2. 1962-09-24---------Jump to [Top]
  2. Douglas Point Project, by D.L.S. Bate, OPG, 1962-09-24. Doc type: Report.
    Summary: Description of the progress in designing and constructing the Douglas Point Project, a 200 MW nuclear power plant.
    Keywords: [Concept] General [SI] 00000 General Project [Discipline] General Engineering [Topic] Intro and Overview [Phase] Construction Design [Audience] Engineer Manager Technician
    - Status Report DP-Status-Sept1962.pdf (2380 kb)
    3. 1968-05-01---------Jump to [Top]
  3. The Performance of Zirconium Alloy Clad UO2 Fuel for Canadian Pressurized and Boiling Water Power Reactors, by R.D. Page and A.D. Lane, AECL, 1968-05-01. Doc type: Report.
    Summary: This paper presents the most recent information (as of 1968) on the performance of CANDU fuel, and goes on to summarize the results of an extensive irradiation program to develop fuels for boiling water cooled reactors.
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Materials Engineering [Topic] Function Performance [Phase] Design Development Operation [Audience] Engineer
    - 19680101.pdf (2338 kb)
    4. 1969-01-01---------Jump to [Top]
  4. 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)
    5. 1971-03-01---------Jump to [Top]
  5. Fast Reactor Kinetics - The QXI Code, by D.A. Meneley, K.O. Ott and E.S. Wiener, Individual Contributions, 1971-03-01. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Modelling [Phase] Design Analysis Safety Analysis [Audience] Grad Ugrad
    - 20070100.pdf (7793 kb)
    6. 1971-09-06---------Jump to [Top]
  6. Commissioning and Operating Experience with Canadian Nuclear Electric Stations, by L. W. Woodhead, D. C. Milley, K. E. Elston, E.P. Horton, A. Dahlinger and R.C. Johnston, AECL, 1971-09-06. Doc type: Report.
    Summary:  
    Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Performance [Phase] Commissioning Operation [Audience] Engineer Manager Technician
    - Paper No. A/Conf. 49/A/148 presented at the Fourth U.N. International Conference on the Peaceful Uses of Atomic Energy, Geneva, 6-16 September, 1971 19710101.pdf (965 kb)
    7. 1975-07-01---------Jump to [Top]
  7. 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)
    8. 1976-03-01---------Jump to [Top]
  8. 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)
    9. 1980-01-01---------Jump to [Top]
  9. Fundamentals of CANDU Reactor Nuclear Design (TDAI-244), by A.A. Pasanen, AECL, 1980-01-01. Doc type: Report.
    Summary: A Lecture Series given at Trieste 22 January - 28 March 1980, TDAI-244 1980 August
    Keywords: [Concept] - [SI] 31000 Reactor 37000 Fuel [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Manager Ugrad
    - Title and Table of Contents 20042000.pdf (176 kb)
    - Chapter 1 - Introduction, by A.A. Pasanen, 20042001.pdf (35 kb)
    - Chapter 2 - Physical Description of the CANDU-600, by A.A. Pasanen, 20042002.pdf (672 kb)
    - Chapter 3 - Methodology for Reactor Physics Analysis In Core Design, by A.A. Pasanen, 20042003.pdf (1922 kb)
    - Chapter 4 - Initial Fuel Loading Determination, by A.A. Pasanen, 20042004.pdf (379 kb)
    - Chapter 5 - Physics Analysis and Tests Related to Commissioning, by A.A. Pasanen, 20042005.pdf (764 kb)
    - Bibliography, by A.A. Pasanen, 20042006.pdf (111 kb)
    10. 1981-04-01---------Jump to [Top]
  10. 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)
    11. 1991-08-01---------Jump to [Top]
  11. Chernobyl – A Canadian Perspective, by V.G. Snell and J.Q. Howieson, AECL, 1991-08-01. Doc type: Report.
    Summary: This brochure looks at the Canadian CANDU (CANada Deuterium Uranium) reactor to see how it stacks up in its ability to tolerate the sorts of mistakes that were made at Chernobyl.
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Concept Design Operation Safety [Audience] Engineer Manager Vendor
    - 19910101.pdf (398 kb)
    12. 1995-08-01---------Jump to [Top]
  12. 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)
    13. 1997-04-01---------Jump to [Top]
  13. 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)
    14. 1997-08-01---------Jump to [Top]
  14. Nuclear Weapons and Nuclear Reactors, by Dan Meneley, OPG, 1997-08-01. Doc type: Report.
    Summary: This report addresses the tenuous link between nuclear power reactor development and the proliferation of nuclear weapons, particularly with respect to possible terrorist exploitation. Arguments are presented which contradict the popular image of nuclear weaponry as a "basement project".
    Keywords: [Concept] - [SI] 03600 Nuclear Safety (Reactor) [Discipline] Nuclear Engineering [Topic] Conceptual Waste Handling [Phase] Operation [Audience] Engineer Manager Vendor
    - Nuclear Studies & Safety Department, Ontario Hydro, Report No. 77157 20032001.pdf (101 kb)
    15. 2002-01-01---------Jump to [Top]
  15. Heavy Water Reactors: Status and Projected Development, Technical Report Series No. 407, IAEA, Vienna, Austria, 2002., IAEA, 2002-01-01. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - Table of Contents. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp. D407_cont.pdf (54 kb)
    - Part 1. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp., D407_scr1.pdf (4200 kb)
    - Part 2. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp., D407_scr2.pdf (3619 kb)
    - Part 3. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp., D407_scr3.pdf (1384 kb)
    - Cover Page. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp., D407_start.pdf (53 kb)
    16. 2005-05-01---------Jump to [Top]
  16. 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)
    17. 2010-01-01---------Jump to [Top]
  17. ACR-1000 Technical Description Summary, AECL, 2010-01-01. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - 20100100.pdf (2399 kb)
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