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[Phase]: Safety 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: 307

    1969-01-01---------Jump to [Top]
  1. 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)
    2. 1969-01-02---------Jump to [Top]
  2. 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)
    3. 1971-03-01---------Jump to [Top]
  3. 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)
    4. 1972-05-25---------Jump to [Top]
  4. AECL Lectures on Nuclear Power Symposium, by G.A. Pon, AECL, 1972-05-25. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems [Phase] Concept Design Design Analysis Safety Safety Analysis [Audience] College Engineer Ugrad
    - Lecture 1 - Introduction 19720101.pdf (1091 kb)
    - Lecture 2 - Radiation, by G. Cowper, 19720102.pdf (1025 kb)
    - Lecture 3 - Power Reactor Types, by Gordon L. Brooks, 19720103.pdf (3378 kb)
    - Lecture 4 - Reactor Physics, by E. Critoph, 19720104.pdf (1755 kb)
    - Lecture 5 - Canadian Reactor Fuel, by R.D. Page, 19720105.pdf (3924 kb)
    - Lecture 8 - System Analysis, by D.B. Primeau, 19720108.pdf (1770 kb)
    - Lecture 9 - Reactor and Station Control, by E.M. Yaremy, 19720109.pdf (2715 kb)
    - Lecture 10 - Plant Layout, by R.B.V. Simmons, 19720110.pdf (3190 kb)
    - Lecture 11 - Accident Analysis, by J.D. Sainsbury, 19720111.pdf (1418 kb)
    - Lecture 12 - Licensing, by L. Pease, 19720112.pdf (1755 kb)
    - Lecture 13 - Training, by G.R. Howey, 19720113.pdf (1432 kb)
    - Lecture 14 - Canadian Power Reactor Fuel. See AECL 5609 doc#19760101 for an updated version., by R.D. Page, 19720114.pdf (2844 kb)
    - Lecture 15 - Construction, by V.A. Harrison, 19720115.pdf (3542 kb)
    - Lecture 16 - Costs, by D.L.S. Bate, 19720116.pdf (764 kb)
    - Lecture 17 - Development Potential, by W.B. Lewis, 19720117.pdf (1390 kb)
    - Lectures 6 and 7 - Heat Transport and Auxiliary Systems, by R.H. Renshaw, 19720167.pdf (2431 kb)
  5. 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)
    6. 1975-07-01---------Jump to [Top]
  6. 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)
    7. 1978-01-01---------Jump to [Top]
  7. 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)
    8. 1978-08-01---------Jump to [Top]
  8. 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)
    9. 1980-01-01---------Jump to [Top]
  9. 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)
    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. 1982-01-01---------Jump to [Top]
  11. 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)
    12. 1984-12-01---------Jump to [Top]
  12. 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)
    13. 1986-01-01---------Jump to [Top]
  13. Safety and Licensing Philosophy and Experience at Ontario Hydro Nuclear Generating Stations, by W. Lee, OPG, 1986-01-01. Doc type: Paper.
    Summary: As published in the Canadian Nuclear Society Bulletin Vol. 7, No. 1, 1986 with the kind permission of the CNS: The safely and licensing philosophy adopted by Ontario Hydro in establishing the need for retrofit design modifications to CANDU nuclear generating stations in operation since the early 1970's is discussed. This philosophy was developed in response to regulatory requests to determine whether this need exists in view of the more extensive safely and licensing design features incorporated in recent CANDU nuclear generating stations compared to the earlier designs. These addition features generally reflect evolving safety knowledge and licensing requirements over time.
    Keywords: [Concept] Safety [SI] 03600 Nuclear Safety (Reactor) 10000 Site and Improvements [Discipline] Nuclear Engineering [Topic] Safety [Phase] Operation Safety [Audience] Engineer Grad Manager Technician Ugrad
    - 19860101.pdf (2661 kb)
    14. 1987-04-01---------Jump to [Top]
  14. 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)
    15. 1987-06-01---------Jump to [Top]
  15. Nuclear Journal of Canada, 1987 Vol 1 No. 2, by J.T. Rogers, CNS-, 1987-06-01. Doc type: Paper.
    Summary: The accident at the Chernobyl-4 RBMK reactor near Kiev in the USSR on 26 April 1986 is described. The characteristics of the RBMK reactors are compared to those of CANDU reactors. Certain insights on the assessment of severe accidents in CANDU reactors are drawn frurn the Chernobyl-4 accident. In particular. the importance of the design of the safety shutdown systems in CANDU is recognized. The most significant lesson from the Chernobyl-4 accident is that primary responsibility for the safety of a nuclear power plant must lie with the operating utility itself, and all managers and operators must be fully conscious of their responsibility for worker and public safety.
    Keywords: [Concept] Safety [SI] 03600 Nuclear Safety (Reactor) [Discipline] Nuclear Engineering [Topic] Safety [Phase] Operation Safety [Audience] College Engineer Grad Technician Ugrad
    - Insights from Chernobyl on Severe Accident Assessment of CANDU Reactors NJC-1-2-03.pdf (829 kb)
    - Simulation Methodology for Pressure Tube Integrity Analysis and Comparison with Experiments, by G.H. Archinoff, J.e. Luxat, P.O. Lowe, K.E. Locke and A.P. Muzumdar, NJC-1-2-07.pdf (575 kb)
    16. 1987-09-01---------Jump to [Top]
  16. Nuclear Journal of Canada, 1987 Vol 1 No. 3, by J.Q. Howieson and V.G. Snell, CNS-, 1987-09-01. Doc type: Paper.
    Summary: On 26 April 1986, the unit 4 reactor at the Chernobyl Nuclear Power Station in the Soviet Union suffered a severe accident which destroyed the reactor core. The reactor design, as it relates to the accident sequence, is reviewed in detail, using information presented in Soviet literature and at the International Atomic Energy Agency Post-Accident Review Meeting in August 1986.
    Keywords: [Concept] Safety [SI] 03600 Nuclear Safety (Reactor) [Discipline] Nuclear Engineering [Topic] Safety [Phase] Operation Safety [Audience] College Engineer Grad Technician Ugrad
    - Chernobyl - A Canadian Technical Perspective NJC-1-3-02.pdf (1766 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)
    - Book Review: Fallout from Chernobyl by L. Ray Silver, by A.N. Sinclair, NJC-1-3-09.pdf (104 kb)
    17. 1987-12-01---------Jump to [Top]
  17. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by L.L. Bennett, CNS-, 1987-12-01. Doc type: Paper.
    Summary: In light of the accident at the Chernobyl nuclear power station, 1986 represents a critical year for nuclear power programmes. This paper reviews the nuclear power programmes in a number of countries, and gives an overview of the current status and future prospects of nuclear power for electricity generation in the world, with particular emphasis to developing countries. The paper also presents economic comparisons of nuclear and coal-fired stations, since the competitiveness of nuclear power is an important factor in nuclear power development.
    Keywords: [Concept] Safety [SI] 03600 Nuclear Safety (Reactor) [Discipline] Nuclear Engineering [Topic] Safety [Phase] Operation Safety [Audience] College Engineer Grad Technician Ugrad
    - The Outlook for Nuclear Power after Chernobyl NJC-1-4-02.pdf (499 kb)
    - Book Reviews: (1) Planet Earth in Jeopardy: Environmental Consequences of Nuclear War by Lydia Datto; (2) Understanding Chernobyl by The Uranium Institute, by Alan Wyatt, David Mosey, NJC-1-4-14.pdf (168 kb)
    18. 1991-08-01---------Jump to [Top]
  18. 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)
    19. 1992-01-01---------Jump to [Top]
  19. Radiation Protection, Course 4.2, by J.U. Burnham, Chulalongkorn University, 1992-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Health Physics [Topic] Radiation [Phase] Safety [Audience] Engineer Manager Vendor
    - Title & Table of Contents 20051601.pdf (63 kb)
    - Chapter 03 - Biological Effects, by J.U. Burnham, 20051602.pdf (1049 kb)
    - Chapter 04 - Dose Limits and Risk, by J.U. Burnham, 20051603.pdf (694 kb)
    - Chapter 06 - Protection from External Radiation, by J.U. Burnham, 20051604.pdf (895 kb)
    - Chapter 07 - External Radiation Hazards, by J.U. Burnham, 20051605.pdf (842 kb)
    - Chapter 08 - Internal Radiation Hazards, by J.U. Burnham, 20051606.pdf (1406 kb)
    - Chapter 09 - Contamination Control, by J.U. Burnham, 20051607.pdf (3037 kb)
    - Workbook 03 - Biological Effects, by J.U. Burnham, 20051608.pdf (341 kb)
    - Workbook 04 - Dose Limits and Risk, by J.U. Burnham, 20051609.pdf (205 kb)
    - Workbook 06 - Protection from External Radiation, by J.U. Burnham, 20051610.pdf (299 kb)
    - Workbook 07 - External Radiation Hazards, by J.U. Burnham, 20051611.pdf (249 kb)
    - Workbook 08 - Internal Radiation Hazards, by J.U. Burnham, 20051612.pdf (311 kb)
    20. 1995-06-25---------Jump to [Top]
  20. Effects Contributing to Positive Coolant Void Reactivity in CANDU, by J. J. Whitlock, Wm.J. Garland, M.S. Milgram, McMaster University, 1995-06-25. Doc type: Paper.
    Summary: The lattice cell properties leading to positive coolant void reactivity in the CANDU reactor are described. The effect is subdivided into spectral, spatial, and isotopic components, and described in terms of criticality factors based on the six-factor fo
    Keywords: [Concept] Reactor Physics [SI] 03000 Engineering Science and Technology 31000 Reactor [Discipline] Nuclear Engineering [Topic] Reactor Physics3 [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Whitlock_ANS_1995.pdf (777 kb)
    21. 1995-08-01---------Jump to [Top]
  21. 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)
    22. 1996-02-01---------Jump to [Top]
  22. Nuclear Reactor Safety Design, Course 3.7, by Wm.J. Garland, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Concept Design Safety [Audience] Engineer Grad Ugrad
    - Chapter 1 - Introduction 20044701.pdf (421 kb)
    - Chapter 2 - Probability Tools & Techniques, by Wm.J. Garland, 20044702.pdf (441 kb)
    - Chapter 3 - Safety Criteria, by Wm.J. Garland, 20044703.pdf (396 kb)
    - Chapter 4 - Design Basis Accidents, by Wm.J. Garland, 20044704.pdf (131 kb)
    - Chapter 5 - Probabilistic Risk Assessment, by Wm.J. Garland, 20044705.pdf (154 kb)
    - Chapter 6 - Safety Analysis, by Wm.J. Garland, 20044706.pdf (190 kb)
    - Chapter 7 - Safety Systems, by Wm.J. Garland, 20044707.pdf (365 kb)
    - Chapter 8 - Good Design Principles & Practices, by Wm.J. Garland, 20044708.pdf (211 kb)
    - References, by Wm.J. Garland, 20044709.pdf (91 kb)
    - Appendix 1 - NRX Accident, by Wm.J. Garland, 20044710.pdf (308 kb)
    - Appendix 2 - Subcategory A.1 Events, by Wm.J. Garland, 20044711.pdf (135 kb)
    - Appendix 3 - Applicable Codes & Standards, by Wm.J. Garland, 20044712.pdf (99 kb)
    - Appendix 4 - Organization of Licensing Basis Document, by Wm.J. Garland, 20044713.pdf (64 kb)
    - Appendix 5 - Accident Analysis Matrix, by Wm.J. Garland, 20044714.pdf (97 kb)
    - Appendix 6 - Large LOCA, by Wm.J. Garland, 20044715.pdf (193 kb)
    - Appendix 7 - Failure Data, by Wm.J. Garland, 20044716.pdf (157 kb)
    - Appendix 8 - Accident Analysis Overview by R. Holmes, by Wm.J. Garland, 20044717.pdf (287 kb)
    - Workbook, Chapter 1 - Figures, by Wm.J. Garland, 20044718.pdf (638 kb)
    - Workbook, Chapter 2 - Figures, by Wm.J. Garland, 20044719.pdf (772 kb)
    - Workbook, Chapter 3 - Figures, by Wm.J. Garland, 20044720.pdf (656 kb)
    - Workbook, Chapter 4 - Figures, by Wm.J. Garland, 20044721.pdf (215 kb)
    - Workbook, Chapter 5 - Figures, by Wm.J. Garland, 20044722.pdf (266 kb)
    - Workbook, Chapter 6 - Figures, by Wm.J. Garland, 20044723.pdf (294 kb)
    - Workbook, Chapter 7 - Figures, by Wm.J. Garland, 20044724.pdf (600 kb)
    - Workbook, Chapter 8 - Figures, by Wm.J. Garland, 20044725.pdf (389 kb)
  23. Principles of Nuclear Safety, Course 4.3, by L. Haacke, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety [Audience] Engineer Manager Vendor
    - Module 01 - Introduction to the Course 20051701.pdf (70 kb)
    - Module 02 - Safety Management & Safety Culture, by L. Haacke, 20051702.pdf (367 kb)
    - Module 03 - Defence in Depth, by L. Haacke, 20051703.pdf (599 kb)
    - Module 04 - Control/Cool/Contain, by L. Haacke, 20051704.pdf (324 kb)
    - Module 05 - Guaranteed Shutdown State, by L. Haacke, 20051705.pdf (212 kb)
    - Module 06 - Reliability Concepts, by L. Haacke, 20051706.pdf (807 kb)
    - Module 07 - Licensing Principles & Safety Assumptions, by L. Haacke, 20051707.pdf (593 kb)
    - Module 08 - Operating Policies & Procedures, by L. Haacke, 20051708.pdf (150 kb)
    - Module 09 - Hierarchy of Documents, by L. Haacke, 20051709.pdf (82 kb)
    - Module 10 - Authorizations & Approvals, by L. Haacke, 20051710.pdf (302 kb)
    - Module 11 - Change Control, by L. Haacke, 20051711.pdf (193 kb)
    - Module 12 - Emergency Procedures, by L. Haacke, 20051712.pdf (177 kb)
    - Module 13 - Quality Assurance, by L. Haacke, 20051713.pdf (239 kb)
    - Module 14 - Surveillance, by L. Haacke, 20051714.pdf (177 kb)
    - Module 15 - Impairments, by L. Haacke, 20051715.pdf (195 kb)
    - Module 16 - Emissions Compliance Monitoring, by L. Haacke, 20051716.pdf (148 kb)
    - Module 17 - Maintenance, by L. Haacke, 20051717.pdf (462 kb)
    - Module 18 - Investigating & Reporting Incidents, by L. Haacke, 20051718.pdf (326 kb)
    - Appendix I - Definitions, by L. Haacke, 20051719.pdf (371 kb)
    - Appendix II - Acronyms, by L. Haacke, 20051720.pdf (55 kb)
    - Appendix III - References, by L. Haacke, 20051721.pdf (11 kb)
    - Workbook 01 - Introduction to Ontario Hydro, by L. Haacke, 20051722.pdf (95 kb)
    - Workbook 02 - Safety Management & Safety Culture, by L. Haacke, 20051723.pdf (254 kb)
    - Workbook 03 - Defence in Depth, by L. Haacke, 20051724.pdf (206 kb)
    - Workbook 04 - Control/Cool/Contain, by L. Haacke, 20051725.pdf (93 kb)
    - Workbook 05 - Guaranteed Shutdown State, by L. Haacke, 20051726.pdf (68 kb)
    - Workbook 06 - Reliability Concepts, by L. Haacke, 20051727.pdf (144 kb)
    - Workbook 07 - Licensing Principles & Safety Assumptions, by L. Haacke, 20051728.pdf (190 kb)
    - Workbook 08 - Operating Policies & Principles, by L. Haacke, 20051729.pdf (39 kb)
    - Workbook 09 - Hierarchy of Documents, by L. Haacke, 20051730.pdf (24 kb)
    - Workbook10 - Authorizations & Approvals, by L. Haacke, 20051731.pdf (58 kb)
    - Workbook11 - Change Control, by L. Haacke, 20051732.pdf (32 kb)
    - Workbook 12 - Emergency Procedures, by L. Haacke, 20051733.pdf (60 kb)
    - Workbook 13 - Quality Assurance, by L. Haacke, 20051734.pdf (48 kb)
    - Workbook 14 - Surveillance, by L. Haacke, 20051735.pdf (39 kb)
    - Workbook 15 - Impairments, by L. Haacke, 20051736.pdf (48 kb)
    - Workbook 16 - Emissions Compliance Monitoring, by L. Haacke, 20051737.pdf (66 kb)
    - Workbook 17 - Maintenance, by L. Haacke, 20051738.pdf (124 kb)
    - Workbook 18 - Investigating & Reporting Incidents, by L. Haacke, 20051739.pdf (113 kb)
  24. Natural Analogs for Nuclear Fuel Disposal, Course 5.2, by J. Cramer, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Workbook 00 - Introduction to Natural Analogs 20052101.pdf (102 kb)
    - Workbook 01 - Copper Corrosion, by J. Cramer, 20052102.pdf (396 kb)
    - Workbook 02 - Clay Sealing, by J. Cramer, 20052103.pdf (249 kb)
    - Workbook 03 - Clay Sealing 2, by J. Cramer, 20052104.pdf (268 kb)
    - Workbook 04 - Clay Sealing - Avonlea Bentonite, by J. Cramer, 20052105.pdf (230 kb)
    - Workbook 05 - Concrete Stability, by J. Cramer, 20052106.pdf (99 kb)
    - Workbook 06 - Concrete & Ground Water, by J. Cramer, 20052107.pdf (48 kb)
    - Workbook 07 - Radionuclide Migration in Soils, by J. Cramer, 20052108.pdf (228 kb)
    - Workbook 08 - Natural Nuclear Reactor, by J. Cramer, 20052109.pdf (479 kb)
    - Workbook 09 - Disposal System Analog, by J. Cramer, 20052110.pdf (1381 kb)
    - Workbook 10 - Summary, by J. Cramer, 20052111.pdf (50 kb)
  25. Hydrogeology of Nuclear Fuel Disposal, Course 5.4, by D. Stevenson, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Workbook 01 - Hydrogeology 20052301.pdf (1408 kb)
    - Workbook 02 - Structural Geology & Borehole Studies, by D. Stevenson, 20052302.pdf (1036 kb)
    - Workbook 03 - Groundwater Sampling, by D. Stevenson, 20052303.pdf (1231 kb)
    - Workbook 04 - Candidate Site Characterization, by D. Stevenson, 20052304.pdf (734 kb)
  26. Environmental Issues in Nuclear Fuel Disposal, Course 5.5, by S. Sheppard, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Workbook 01 - Environmental Issues in Waste Management 20052401.pdf (2604 kb)
    - Workbook 02 - Lakes and Rivers, by S. Sheppard, 20052402.pdf (1445 kb)
    - Workbook 03 - Atmosphere, by S. Sheppard, 20052403.pdf (815 kb)
    - Workbook 04 - Natural Realm, by S. Sheppard, 20052404.pdf (906 kb)
    - Workbook 05 - Sensitivity Analysis, by S. Sheppard, 20052405.pdf (1734 kb)
    - Workbook 06 - Monte Carlo Models, by S. Sheppard, 20052406.pdf (1234 kb)
  27. Nuclear Fuel Disposal Performance Assessment, Course 5.6, by J. Cramer, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Workbook 00 - Performance Assessment Modeling 20052501.pdf (65 kb)
    - Workbook 01 - Introduction & System Variability Analysis, by J. Cramer, 20052502.pdf (2055 kb)
    - Workbook 02 - I/O and Systems Model Interfaces, by J. Cramer, 20052503.pdf (1567 kb)
    - Workbook 03 - Complex & Large System Models, by J. Cramer, 20052504.pdf (412 kb)
    - Workbook 04 - Sensitivity Analysis & SYVAC3 Applications, by J. Cramer, 20052505.pdf (592 kb)
    - Workbook 05 - Canadian System Model & SYVAC3-CC3, by J. Cramer, 20052506.pdf (880 kb)
  28. Radiation Processing, Course 6.1, by A. Sigh and H. Singh, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Workbook 01 - Basics, Current & Emerging Applications 20052701.pdf (360 kb)
    - Workbook 02 - Potential Concerns Associated with Irradiated Foods, by A. Sigh and H. Singh, 20052702.pdf (598 kb)
    - Workbook 03 - Irradiated Foods (cont'd), by A. Sigh and H. Singh, 20052703.pdf (392 kb)
    - Workbook 04 - Sterilization of Medical Products, by A. Sigh and H. Singh, 20052704.pdf (494 kb)
    - Workbook 05 - Dosimetry, by A. Sigh and H. Singh, 20052705.pdf (223 kb)
    - Workbook 06 - Radiation Polymerization - Coatins & Links, by A. Sigh and H. Singh, 20052706.pdf (111 kb)
    - Workbook 07 - Radiation Polymerization - Grafting, by A. Sigh and H. Singh, 20052707.pdf (110 kb)
    - Workbook 08 - Radiation Polymerization - Bioengineering, by A. Sigh and H. Singh, 20052708.pdf (188 kb)
    - Workbook 09 - Polymerization - Material Composites, by A. Sigh and H. Singh, 20052709.pdf (93 kb)
    - Workbook 10 - Radiation Protection, by A. Sigh and H. Singh, 20052710.pdf (100 kb)
    - Workbook 11 - Dose Rate Effect in Food Irradiation, by A. Sigh and H. Singh, 20052711.pdf (1661 kb)
    - Workbook 12 - Radiation Processing - Basic Aspects, by A. Sigh and H. Singh, 20052712.pdf (691 kb)
    - Workbook 13 - Industrial Irradiators, by A. Sigh and H. Singh, 20052713.pdf (628 kb)
    - Workbook 14 - The Environment, by A. Sigh and H. Singh, 20052714.pdf (66 kb)
    - Workbook 15 - Chemical Wastes - PCBs, by A. Sigh and H. Singh, 20052715.pdf (62 kb)
    - Workbook 16 - Radiation Processing of Sewage, by A. Sigh and H. Singh, 20052716.pdf (194 kb)
    - Workbook 17 - Radiation Processing of Flue Gases, by A. Sigh and H. Singh, 20052717.pdf (91 kb)
    - Workbook 18 - Electron Processing in the Pulping Industry, by A. Sigh and H. Singh, 20052718.pdf (360 kb)
    - Workbook 19 - Chemical Effects, by A. Sigh and H. Singh, 20052719.pdf (274 kb)
    - Workbook 20 - Manufacturing of Chemicals, by A. Sigh and H. Singh, 20052720.pdf (50 kb)
    - Workbook 21 - Food Irradiation - Dose Rate Effect, by A. Sigh and H. Singh, 20052721.pdf (301 kb)
    - Workbook 22 - Electron Processing - Composites, by A. Sigh and H. Singh, 20052722.pdf (887 kb)
    - Workbook 23 - Dosimetry Procedures in Electron Processing, by A. Sigh and H. Singh, 20052723.pdf (248 kb)
    - Workbook 24 - Safety in Industrial Accelerator Facility, by A. Sigh and H. Singh, 20052724.pdf (467 kb)
    - Workbook 25 - Effects on Polymeric Systems - Polymerization, by A. Sigh and H. Singh, 20052725.pdf (68 kb)
    - Workbook 26 - Effects on Polymeric Systems - Crosslinking and Scission, by A. Sigh and H. Singh, 20052726.pdf (232 kb)
    - Workbook 27 - Effects on Polymeric Systems - Polyethylene Crosslinking, by A. Sigh and H. Singh, 20052727.pdf (91 kb)
    - Workbook 28 - Effects on Polymeric Systems - Elastomers, by A. Sigh and H. Singh, 20052728.pdf (138 kb)
    - Workbook 29 - Spices, Herbs, Other Vegetable Seasonings, by A. Sigh and H. Singh, 20052729.pdf (236 kb)
    - Workbook 30 - Successful Applications in Food Irradiation, by A. Sigh and H. Singh, 20052730.pdf (316 kb)
    - Workbook 31 - Irradiation of Fresh Fruits, by A. Sigh and H. Singh, 20052731.pdf (273 kb)
    - Workbook 32 - Radiation Processing of Advanced Composites, by A. Sigh and H. Singh, 20052732.pdf (670 kb)
    - Workbook 33 - Micronutrients, by A. Sigh and H. Singh, 20052733.pdf (210 kb)
    - Workbook 34 - Irradiation of Red Meats, by A. Sigh and H. Singh, 20052734.pdf (157 kb)
    29. 1997-01-01---------Jump to [Top]
  29. Radioactive Waste Management, Course 5.1, by L. Zikovsky, Chulalongkorn University, 1997-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Chapter 00 - Table of Contents 20052001.pdf (312 kb)
    - Chapter 01 - Introduction, by L. Zikovsky, 20052002.pdf (1537 kb)
    - Chapter 02 - Gaseous Waste, by L. Zikovsky, 20052003.pdf (1137 kb)
    - Chapter 03 - Liquid and Wet Waste, by L. Zikovsky, 20052004.pdf (2459 kb)
    - Chapter 04 - Solid Medium & Low Level, by L. Zikovsky, 20052005.pdf (2018 kb)
    - Chapter 05 - Transport, by L. Zikovsky, 20052006.pdf (542 kb)
    - Chapter 06 - Solid High Level Waste, by L. Zikovsky, 20052007.pdf (846 kb)
    - Chapter 07 - Disposal of High Level Waste, by L. Zikovsky, 20052008.pdf (3282 kb)
    - Chapter 08 - Management of Radioactive Waste in Canada, by L. Zikovsky, 20052009.pdf (2503 kb)
    - Workbook 01 - Radioactive Waste Management, by L. Zikovsky, 20052010.pdf (374 kb)
    - Workbook 02 - Gaseous Radwaste, by L. Zikovsky, 20052011.pdf (378 kb)
    - Workbook 03 - Liquid Radwaste, by L. Zikovsky, 20052012.pdf (642 kb)
    - Workbook 04 - Solid LLW, by L. Zikovsky, 20052013.pdf (720 kb)
    - Workbook 05 - Transport, by L. Zikovsky, 20052014.pdf (193 kb)
    - Workbook 06 - Solid HLW, by L. Zikovsky, 20052015.pdf (350 kb)
    - Workbook 07 - Disposal Principles, by L. Zikovsky, 20052016.pdf (1066 kb)
    - Workbook 08 - Canada's Radwaste, by L. Zikovsky, 20052017.pdf (1015 kb)
    30. 1997-03-18---------Jump to [Top]
  30. Engineered Barriers for Fuel Disposal, Course 5.3, by L.H. Johnson, Chulalongkorn University, 1997-03-18. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Nuclear Engineering [Topic] Waste Handling [Phase] Concept Design Operation Safety [Audience] Engineer Manager
    - Workbook 01 - Introduction 20052201.pdf (1579 kb)
    - Workbook 02 - Detailed Chemistry Considerations, by L.H. Johnson, 20052202.pdf (700 kb)
    - Workbook 03 - Container Failure Predictions, by L.H. Johnson, 20052203.pdf (924 kb)
    - Workbook 04 - Container Design Considerations, by L.H. Johnson, 20052204.pdf (829 kb)
    - Workbook 05 - Seal Materials, Design, & Performance, by L.H. Johnson, 20052205.pdf (757 kb)
    - Workbook 06 - Large Scale In Situ Testing, by L.H. Johnson, 20052206.pdf (1582 kb)
    - Workbook 07 - Vault Model, by L.H. Johnson, 20052207.pdf (322 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. 1998-09-22---------Jump to [Top]
  32. Introduction to CANDU 6 - Overheads for a course presented at Xi'an Jiaotong University, 1998-09-22 to 25, by D.A. Meneley and Y.Q. Ruan, AECL, 1998-09-22. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems [Phase] Concept Design Safety [Audience] College Engineer Ugrad
    - Comparison of PHWR and PWR 19980101.pdf (1874 kb)
    - Reactor and Fuel Handling, by D.A. Meneley and Y.Q. Ruan, 19980102.pdf (2650 kb)
    - Moderator, HTS, Heavy Water, by D.A. Meneley and Y.Q. Ruan, 19980103.pdf (2454 kb)
    - Main Steam & T/G Systems, by D.A. Meneley and Y.Q. Ruan, 19980104.pdf (2626 kb)
    - Special Safety Systems, by D.A. Meneley and Y.Q. Ruan, 19980105.pdf (949 kb)
    - CANDU Reactor Control, by D.A. Meneley and Y.Q. Ruan, 19980106.pdf (1038 kb)
    33. 1999-02-23---------Jump to [Top]
  33. Decay Heat Estimates for MNR, by Wm.J. Garland, McMaster University, 1999-02-23. Doc type: Other.
    Summary: Decay heat removal is essential in preventing fuel overheating and possible fission product release.  This
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Basic Equations Modelling Reactor Physics [Phase] Concept Design Safety Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - decayhe1.xls (521 kb)
    34. 1999-06-21---------Jump to [Top]
  34. CANDU Safety - presentations in Shanghai, 1999, by V. Snell, AECL, 1999-06-21. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual [Phase] Design Safety [Audience] Engineer Manager
    - CANDU Nuclear Power Plant Design 19990101.pdf (1646 kb)
    - Risk from Nuclear Power Plants, by V. Snell, 19990102.pdf (84 kb)
    - Nuclear Safety Characteristics, by V. Snell, 19990103.pdf (286 kb)
    - Thermalhydraulic Safety Characteristics of CANDU Reactors, by F.J. Doria, 19990104.pdf (1183 kb)
    - Safety Functions - Shutdown Systems, by V. Snell, 19990105.pdf (517 kb)
    - Heat Removal, by V. Snell, 19990106.pdf (767 kb)
    - Emergency Core Cooling, by V. Snell, 19990107.pdf (1182 kb)
    - Containment, by V. Snell, 19990108.pdf (699 kb)
    - Grouping and Separation, by V. Snell, 19990109.pdf (65 kb)
    - Design and Analysis Process, by F.J. Doria, 19990110.pdf (524 kb)
    - Reactivity Control, by V. Snell, 19990111.pdf (412 kb)
    - Large Loss of Coolant Accident, by F.J. Doria, 19990112.pdf (578 kb)
    - Small Loss of Coolant Accident, by F.J. Doria, 19990113.pdf (651 kb)
    - Loss of Heat Sink, by V. Snell, 19990114.pdf (199 kb)
    - Loss of Forced Circulation, by V. Snell, 19990115.pdf (1517 kb)
    - Large Loss of Coolant Accident with Coincident Loss of Emergency Core Cooling, by F.J. Doria, 19990116.pdf (554 kb)
    - Severe Core Damage Accidents, by V. Snell, 19990117.pdf (478 kb)
    - Safety Research and Development, by V. Snell, 19990118.pdf (1851 kb)
    - Safety Research and Development Programs, by F.J. Doria, 19990119.pdf (903 kb)
    - Safety Analysis Tools, by F.J. Doria, 19990120.pdf (608 kb)
    - Probabilistic Safety Analysis, by V.G. Snell and R. Jaitly, 19990121.pdf (81 kb)
    - Regulation of CANDU, by V. Snell, 19990122.pdf (1223 kb)
    - Regulatory Requirements for Design, by V. Snell, 19990123.pdf (162 kb)
    - Regulatory Requirements for Accident Analysis, by V. Snell, 19990124.pdf (60 kb)
    - CANDU 9 Design Overview, by V. Snell, 19990125.pdf (630 kb)
    - CANDU 9 Safety and Licensability, by V. Snell, 19990126.pdf (580 kb)
    35. 1999-10-01---------Jump to [Top]
  35. China Journal of Nuclear Power Engineering, 1999 Vol 20 No. 6, by Xu Jijun and K.R. Hedges, AECL, 1999-10-01. Doc type: Paper.
    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
    - Paper 01 - The Development of CANDU 20054401.pdf (2187 kb)
    - Paper 02 - Introduction to the Qinshan Phase III CANDU Nuclear Power Plant, by Zhang Yanfa and B.A. Shalaby, 20054402.pdf (3387 kb)
    - Paper 03 - Reactor Core Structure of Qinshan Phase III CANDU Nuclear Power Plant, by Qiu Suizheng and Norman C. Johnston, 20054403.pdf (1893 kb)
    - Paper 04 - Moderator, Heat Transport, and Steam Systems of Qinshan Phase III Nuclear Power Plant, by Gong Hongqi and R.S. Hart, 20054404.pdf (353 kb)
    - Paper 05 - Fuel Handling System for Qinshan Phase III Nuclear Power Plant, by Lin Chuanqing and D.C. Hancock, 20054405.pdf (649 kb)
    - Paper 06 - Control System of Qinshan Phase III Nuclear Power Plant, by Zhang Jianmin and R.A. Olmstead, by Jianmin Zhang and R.A. Olmstead, 20054406.pdf (427 kb)
    - Paper 07 - Main Electric Power and Balance of Plant Systems and Equipment for Qinshan Phase III Nuclear Power Plant, by Ji Yan, Jin Wanggui, He Ping and Surya Varanasi, 20054407.pdf (2543 kb)
    - Paper 08 - Safety Systems and Safety Analysis of Qinshan Phase III Nuclear Power Plant, by Cai Jianping, Shen Sen and Nick Barkman, 20054408.pdf (197 kb)
    - Paper 09 - Design and Performance of Fuel for Qinshan Phase III Nuclear Power Plant, by Song Wenhui and A.M. Manzer, 20054409.pdf (168 kb)
    - Paper 10 - Computer-Aided Engineering for Qinshan CANDU Projects, by Huang Zhizhang and David Goland, 20054410.pdf (366 kb)
    - Paper 11 - Fuel Management of CANDU Reactors, by Shao-hong Zhang and and B. Rouben, 20054411.pdf (252 kb)
    - Paper 12 - Physics Codes and Methods for CANDU Reactors, by Zhu XingGuan, Cai Jianping and H.C. Chow, 20054412.pdf (240 kb)
    - Paper 13 - Thermalhydraulic Design Methods and Computer Codes for CANDU Reactors, by Xu Jijun, V.S. Krishnan, P.J. Ingham, B.N. Hanna and J.R. Buell, 20054413.pdf (577 kb)
    - Paper 14 - Operational Characteristics and Management of the Qinshan Phase III CANDU Nuclear Power Plant, by Zhu Jizhou, Shan Jianqiang and Dennis McQuade, 20054414.pdf (201 kb)
    - Paper 15 - Advanced CANDU Fuel Cycle Vision, by Xie Zhonsheng and P.G. Boczar, 20054415.pdf (80 kb)
    - Paper 16 - A Brief Introduction to CANDU9 – A New Generation of Pressurized Heavy Water Reactors, by Zhang Zhenhua and K.R. Hedges, 20054416.pdf (189 kb)
    36. 2000-09-13---------Jump to [Top]
  36. Safety Analysis Technology: Evolution, Revolution and the Drive to Re-Establish Margins, by John C Luxat, OPG, 2000-09-13. Doc type: Presentation.
    Summary: A historical perspective of the evolution of safety analysis technology at OPG is presented below. The key elements of the new safety analysis methodology are then described together with its relationship to other components of Canadian nuclear safety technology. This development is placed in context with similar work being conducted in the international Light Water Reactor (LWR) community.
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Performance [Phase] Commissioning Design Operation Safety [Audience] Engineer Technician
    - 20000301.pdf (256 kb)
    37. 2000-11-01---------Jump to [Top]
  37. A Reactor Cannot Explode Like a Nuclear Bomb, by Dan Meneley, Individual Contributions, 2000-11-01. Doc type: Lecture.
    Summary:
    Keywords: [Concept] - [SI] 03600 Nuclear Safety (Reactor) [Discipline] Nuclear Engineering [Topic] Conceptual Performance [Phase] Concept Design Operation Safety [Audience] College Engineer Manager Technician Vendor
    - 20000201.pdf (237 kb)
    38. 2001-01-03---------Jump to [Top]
  38. Why a Chernobyl-type accident cannot happen in CANDU reactors, AECL, 2001-01-03. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Concept Design Operation Safety [Audience] Engineer Manager Vendor
    - 20010701.pdf (1026 kb)
    39. 2002-01-01---------Jump to [Top]
  39. 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)
    40. 2002-09-25---------Jump to [Top]
  40. ACR Presentation given to the US Nuclear Regulatory Commission on September 25-26, 2002, AECL, 2002-09-25. Doc type: Presentation.
    Summary: Presentation given by AECL to the US Nuclear Regulatory Commission on September 25-26, 2002
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - Introduction. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031201.pdf (1939 kb)
    - An Overview of the ACR Design. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031202.pdf (7935 kb)
    - ACR Technology Base. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031203.pdf (19271 kb)
    - ACR Reactor and Fuel Handling. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031204.pdf (12607 kb)
    - Core Design & Reactor Physics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031205.pdf (957 kb)
    - Reactor Coolant System, Moderator and Major Auxiliary Systems. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031206.pdf (17255 kb)
    - ACR Safety Support Systems Safety Assessment. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031207.pdf (583 kb)
    - ACR Technology Base: Reactor Physics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031208.pdf (1490 kb)
    - ACR Technology Base: Fuel. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031209.pdf (2924 kb)
    - ACR Technology Base: RCS Thermalhydraulics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031210.pdf (3081 kb)
    - ACR Technology Base: Fuel Channels. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031211.pdf (1817 kb)
    - ACR Technology Base: Fuel Channel Thermalhydraulics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031212.pdf (1444 kb)
    - ACR Moderator Circulation. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031213.pdf (2038 kb)
    - ACR Technology Base: Containment. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031214.pdf (792 kb)
    - Qualification Process for Safety Analysis Computer Codes. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031215.pdf (493 kb)
    41. 2003-06-30---------Jump to [Top]
  41. Safer Nuclear Energy for the Future, by D.A. Meneley, AECL, 2003-06-30. Doc type: Presentation.
    Summary: Series of lectures by Dan Meneley presented at the 28th International Summer College on Physics and Contemporary Needs, June 30 - July 12, 2003, Nathiagali, Pakistan
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Conceptual Performance Safety [Phase] Concept Design Safety [Audience] Engineer Manager
    - Introduction 20041000.pdf (77 kb)
    - Lecture 1 - Safety Perspectives, by D.A. Meneley, 20041001.pdf (115 kb)
    - Lecture 2 - Past Design Evolution, by D.A. Meneley, 20041002.pdf (103 kb)
    - Lecture 3 - Future Design Directions, by D.A. Meneley, 20041003.pdf (136 kb)
    - Lecture 4 - The Long Term, by D.A. Meneley, 20041004.pdf (205 kb)
    42. 2003-10-01---------Jump to [Top]
  42. Nuclear Safety & Reliability Course, by D.A. Meneley, University of New Brunswick, 2003-10-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Safety [Phase] Design Safety [Audience] Grad Ugrad
    - Cover Page 20032200.pdf (89 kb)
    - Week 1, by D.A. Meneley, 20032201.pdf (293 kb)
    - Week 2, by D.A. Meneley, 20032202.pdf (461 kb)
    - Week 3, by D.A. Meneley, 20032203.pdf (378 kb)
    - Week 4, by D.A. Meneley, 20032204.pdf (335 kb)
    - Week 5, by D.A. Meneley, 20032205.pdf (666 kb)
    - Week 6, by D.A. Meneley, 20032206.pdf (636 kb)
    - Week 7, by D.A. Meneley, 20032207.pdf (930 kb)
    - Week 8, by D.A. Meneley, 20032208.pdf (1943 kb)
    - Week 9, by D.A. Meneley, 20032209.pdf (2120 kb)
    - Week 10, by D.A. Meneley, 20032210.pdf (433 kb)
    - Week 11, by D.A. Meneley, 20032211.pdf (476 kb)
    - Week 12, by D.A. Meneley, 20032212.pdf (353 kb)
    43. 2004-04-08---------Jump to [Top]
  43. Communicating About Nuclear Issues: Nuclear Power Plants, by Jon Jennekens, CNSC, 2004-04-08. Doc type: Presentation.
    Summary: Presented on April 8, 2004 at the CNA Communications Workshop at Darlington site
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] General Engineering [Topic] Intro and Overview [Phase] Safety [Audience] Manager
    - 20041501.pdf (829 kb)
    44. 2009-05-30---------Jump to [Top]
  44. Large LOCA Margins in CANDU Reactors - An Overview of the COG Report, by A.P. Muzumdar and D.A. Meneley, COG, 2009-05-30. Doc type: Paper.
    Summary: This paper discusses the background and conclusions of the 2007 COG report on Large LOCA Safety Margins in CANDU Reactors, and the various initiatives that have resulted from this study since its release. The COG study challenged the notion that positive void reactivity itself is a design weakness, raised as an issue at the Convention on Nuclear Safety, to demonstrate the safety of operating CANDUs worldwide when compared to other certified LWR designs. The paper will briefly describe a new perspective on how the seemingly complex analytical results on reactor safety parameters can be compared on a level playing field, in such a manner that the non-specialist is able to understand. The paper is presented together with a companion paper that focuses on the comparison of reactivity initiated events in CANDU with some other internationally accepted LWR reactor designs.
    Keywords: [Concept] - [SI] 31000 Reactor 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety Safety Analysis [Audience] College Engineer Grad Manager Technician Ugrad Vendor
    - 20090101.pdf (89 kb)
  45. Power Reactor Safety Comparison - A Limited Review, by D.A. Meneley and A.P. Muzumdar, COG, 2009-05-30. Doc type: Paper.
    Summary: A large amount of attention has been paid to avoiding positive coolant void reactivity in LWR reactors. This can be justified due to specific accident events that could lead to severe consequences. Somewhat less attention has been paid to other accident sequences that can lead to positive reactivity addition. Other designs, for example the CANDU-PHWR, exhibit positive coolant void reactivity but include both inherent and engineered systems that compensate for this undesirable characteristic. This paper represents the beginning of a long-term process intended to enable a balanced and fair comparison of the real safety of all reactor types.
    Keywords: [Concept] - [SI] 31000 Reactor 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety Safety Analysis [Audience] College Engineer Grad Manager Technician Ugrad Vendor
    - 20090201.pdf (170 kb)
    46. 2010-01-01---------Jump to [Top]
  46. 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)
    47. 2012-01-25---------Jump to [Top]
  47. 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)
    48. 2015-01-01---------Jump to [Top]
  48. 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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