Jump to year -> [1986-01-01] [1987-06-01] [1987-09-01] [1987-12-01] [1991-08-01] [1996-02-01] [2001-01-03] [2003-06-30] [2003-10-01] [2009-05-30] [2012-01-25] [2015-01-01]
[Topic]: 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: 109

    1986-01-01---------Jump to [Top]
  1. 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)
    2. 1987-06-01---------Jump to [Top]
  2. 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)
    3. 1987-09-01---------Jump to [Top]
  3. 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)
    4. 1987-12-01---------Jump to [Top]
  4. 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)
    5. 1991-08-01---------Jump to [Top]
  5. 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)
    6. 1996-02-01---------Jump to [Top]
  6. 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)
  7. Reactor Licensing & Siting, Course 4.1, by F.C. Boyd, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Safety [Phase] Licensing [Audience] Engineer Manager Vendor
    - Section 01 - Schedules Made Persuant to the Nuclear Liability Act 20051501.pdf (299 kb)
    - Section 02 - Atomic Energy Control Regulations, by F.C. Boyd, 20051502.pdf (1000 kb)
    - Section 03 - Liability Act, by F.C. Boyd, 20051503.pdf (1128 kb)
    - Section 04 - Bill C-125 Physical Security, by F.C. Boyd, 20051504.pdf (1341 kb)
    - Section 05 - Transport Packaging, U and Th Mining, by F.C. Boyd, 20051505.pdf (2067 kb)
    - Section 06 - R-7 Containment, R-8 Shutdown, R-9 Emergency Cooling, by F.C. Boyd, 20051506.pdf (1114 kb)
    - Section 07 - R-10, R-58, R-75, by F.C. Boyd, 20051507.pdf (656 kb)
    - Section 08 - R-76, R-85, R-90, by F.C. Boyd, 20051508.pdf (653 kb)
    - Section 09 - R-99, R-104, by F.C. Boyd, 20051509.pdf (1128 kb)
    - Section 10 - AECB 1139 The Licensing Process, by F.C. Boyd, 20051510.pdf (937 kb)
    - Section 11 - Licensing Systems & Inspection, by F.C. Boyd, 20051511.pdf (1703 kb)
    - Workbook 01 - Licensing of Nuclear Facilities, by F.C. Boyd, 20051512.pdf (982 kb)
    - Workbook 02 - Siting of NPP, by F.C. Boyd, 20051513.pdf (624 kb)
    - Workbook 03 - Containment & Siting Requirements from IAEA Conference, 1967, by F.C. Boyd, 20051514.pdf (2248 kb)
  8. 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)
    9. 2001-01-03---------Jump to [Top]
  9. 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)
    10. 2003-06-30---------Jump to [Top]
  10. 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)
    11. 2003-10-01---------Jump to [Top]
  11. 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)
    12. 2009-05-30---------Jump to [Top]
  12. 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)
  13. 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)
    14. 2012-01-25---------Jump to [Top]
  14. 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)
    15. 2015-01-01---------Jump to [Top]
  15. 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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