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[DocType]: Presentation 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: 107

    1961-09-18---------Jump to [Top]
  1. NPD, a Description of, by J.L Olsen, OPG, 1961-09-18. Doc type: Presentation.
    Summary: Nuclear Power Demonstration. An illustrated talk presented at the Seventh AECL Symposium on Atomic Energy, Chalk River, September 18, 1961.
    Keywords: [Concept] General [SI] 00000 General Project 30000 Reactor, Steam Generators and Auxiliaries 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Description [Audience] College Engineer High Technician Ugrad
    - Canada's First Nuclear Power Station CAPD10--Sept1961NPD-Description.pdf (5637 kb)
    2. 1971-05-01---------Jump to [Top]
  2. Do the Universities Prepare the Type of Engineers that our Nuclear Industry Needs, by Gordon L. Brooks, AECL, 1971-05-01. Doc type: Presentation.
    Summary: Author suggests the more emphasis on systems engineering is needed in the university training of engineers, including design oriented graduate degrees.
    Keywords: [Concept] General [SI] Not assigned [Discipline] General Engineering [Topic] Conceptual [Phase] - [Audience] Engineer Grad Technician Ugrad
    - CNA Annual Meeting Panel Presentation CNA-UnivEngineers-BrooksMay1971.pdf (149 kb)
    3. 1993-01-01---------Jump to [Top]
  3. Principes de Science et de Fonctionnement des Réacteurs, CNSC, 1993-01-01. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] - [Phase] Concept Design [Audience] College Engineer Manager Technician Ugrad
    - Réacteurs à Neutrons Intermédiaires et Auxiliaires - Systèmes Spéciaux de Sûreté 20070501.pdf (237 kb)
    - Réacteurs à Neutrons Intermédiaires et Auxiliaires - Combustible, 20070502.pdf (280 kb)
    - Réacteurs à Neutrons Intermédiaires et Auxiliaires - CC, 20070503.pdf (1500 kb)
    - Réacteurs à Neutrons Intermédiaires et Auxiliaires - Réacteurs à Neutrons Intermédiaires et Auxiliaires, 20070504.pdf (961 kb)
    - Réacteurs à Neutrons Intermédiaires et Auxiliaires - Circuits du Réacteur, 20070505.pdf (421 kb)
    4. 1995-09-11---------Jump to [Top]
  4. Synergistic Nuclear Fuel Cycles of the Future - Associated Presentation, by D.A. Meneley, A.R. Dastur, P.J. Fehrenbach and K.H. Talbot, AECL, 1995-09-11. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Fuel Management [Phase] Concept Design Operation [Audience] Engineer Manager
    - Global 1995, International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France 20054702.pdf (443 kb)
    5. 1999-03-01---------Jump to [Top]
  5. CANDU Fuel Management Course, by Ben Rouben, AECL, 1999-03-01. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
    - Basic Characteristics of the CANDU Lattice 20031111.pdf (186 kb)
    - The CANDU Reactivity Devices, by Ben Rouben, 20031112.pdf (147 kb)
    - Detector Systems, by Ben Rouben, 20031113.pdf (141 kb)
    - Computational Scheme for CANDU Neutronics, by Ben Rouben, 20031114.pdf (182 kb)
    - General Discussion on CANDU Fuel Management, by Ben Rouben, 20031115.pdf (125 kb)
    - Equilibrium-Core Design, by Ben Rouben, 20031116.pdf (217 kb)
    - Ongoing Reactor Operation with Channel Refuellings, by Ben Rouben, 20031117.pdf (252 kb)
    - Effects of 135Xe, by Ben Rouben, 20031118.pdf (151 kb)
    - Summary, by Ben Rouben, 20031119.pdf (61 kb)
    6. 1999-06-21---------Jump to [Top]
  6. 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)
    7. 2000-09-13---------Jump to [Top]
  7. 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)
    8. 2000-11-15---------Jump to [Top]
  8. The CANDU System: A Canadian Achievement, by Adam McLean, University of Toronto, 2000-11-15. Doc type: Presentation.
    Summary: A presentation on CANDU, its history and its achievements.
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] General Engineering [Topic] Intro and Overview [Phase] Operation [Audience] College
    - 20000401.pdf (31 kb)
    9. 2001-01-01---------Jump to [Top]
  9. CANDU Poster, AECL, 2001-01-01. Doc type: Presentation.
    Summary: Handy overview poster showing the major components and concepts of CANDU.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Operation [Audience] High
    - 20010501.pdf (945 kb)
    10. 2001-01-02---------Jump to [Top]
  10. CANDU - How a Reactor Works, AECL, 2001-01-02. Doc type: Presentation.
    Summary: A handy overview poster showing how a CANDU reactor works.
    Keywords: [Concept] Overview [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Operation [Audience] High
    - 20010601.pdf (578 kb)
    11. 2001-01-03---------Jump to [Top]
  11. 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)
    12. 2001-03-06---------Jump to [Top]
  12. Fuel for the Next Millennia, by D.A. Meneley, AECL, 2001-03-06. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Fuel Management [Phase] Concept Design Operation [Audience] Engineer Manager
    - 20010201.pdf (906 kb)
    13. 2002-09-25---------Jump to [Top]
  13. 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)
    14. 2003-05-01---------Jump to [Top]
  14. Chemistry Control Requirements for Generic CANDU Power Stations, by Stu Groom, NB Power, 2003-05-01. Doc type: Presentation.
    Summary: A series of presentations by Stu Groom to the Karachi Nuclear Power Plant (KANUPP) in May 2003 as a part of an IAEA 5-day training program to review the chemistry control requirements of the Karachi Nuclear Power Plant.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Construction [Audience] College Engineer Ugrad
    - Basic Chemistry Concepts 20032101.pdf (833 kb)
    - Moderator System Chemistry Control, by Stu Groom, 20032102.pdf (264 kb)
    - Annulus Gas System Chemistry Control, by Stu Groom, 20032103.pdf (362 kb)
    - Primary Heat Transport System Chemistry Control, by Stu Groom, 20032104.pdf (667 kb)
    - Feeder Thinning, by Stu Groom, 20032105.pdf (600 kb)
    - Boiler Feedwater / Condensate Chemistry Control, by Stu Groom, 20032106.pdf (605 kb)
    - Steam Generator Chemistry Control, by Stu Groom, 20032107.pdf (430 kb)
    - ECC and Dousing Systems Chemistry Control, by Stu Groom, 20032108.pdf (116 kb)
    - Spent Fuel Bay Chemistry Control, by Stu Groom, 20032109.pdf (85 kb)
    - Plant Chemistry Controm - PLGS Manual, by Stu Groom, 20032110.pdf (4826 kb)
    - PHT System Chemitry Monitoring and Control Improvements, by Stu Groom, 20032111.pdf (753 kb)
    - Chemistry Laboratory Analytical Procedure – Gadolinium Arsenazo III, by Stu Groom, 20032112.pdf (175 kb)
    - Chemistry Specifications, by Stu Groom, 20032113.pdf (119 kb)
    15. 2003-06-01---------Jump to [Top]
  15. CANTEACH Flyer, by CANTEACH, CANTEACH, 2003-06-01. Doc type: Presentation.
    Summary:
    Keywords: [Concept] General [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High K-8 Manager Technician Ugrad Vendor
    - 20031601.pdf (156 kb)
  16. Qinshan Project, by Ken Petrunik, AECL, 2003-06-01. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Construction [Audience] College Engineer Ugrad
    - CNS 2003 Conference Paper 20031801.pdf (3687 kb)
    17. 2003-06-24---------Jump to [Top]
  17. CANDU Fundamentals, CNSC, 2003-06-24. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Radioactivity - Spontaneous Nuclear Processes 20040727.pdf (539 kb)
    - Nuclear Stability And Instability, 20040728.pdf (1360 kb)
    - Activity and Half-Life, 20040729.pdf (120 kb)
    - Neutrons and Neutron Interactions, 20040730.pdf (163 kb)
    - Fission, 20040731.pdf (3750 kb)
    - Fuel, Moderator, and Reactor Management, 20040732.pdf (937 kb)
    - Nuclear Safety, 20040733.pdf (465 kb)
    - Nuclear Power Reactors, 20040734.pdf (693 kb)
    - CANDU Reactor Construction, 20040735.pdf (1259 kb)
    - Moderator System, 20040736.pdf (731 kb)
    - Heat Transport System, 20040737.pdf (1053 kb)
    - Fuel and Fuelling, 20040738.pdf (2226 kb)
    - Neutron Life Cycle, 20040739.pdf (151 kb)
    - Criticality and Neutron Multiplication, 20040740.pdf (709 kb)
    - Changes in Reactor Power with time, 20040741.pdf (2744 kb)
    - Neutron Flux Control, 20040742.pdf (157 kb)
    - Reactivity Mechanisms, 20040743.pdf (1894 kb)
    - Emergency Coolant Injection & Containment, 20040744.pdf (1024 kb)
    - The Conventional Side of the Station, 20040745.pdf (1535 kb)
    - Other Major Systems, 20040746.pdf (2581 kb)
    18. 2003-06-30---------Jump to [Top]
  18. 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)
    19. 2004-04-08---------Jump to [Top]
  19. 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)
    20. 2004-04-20---------Jump to [Top]
  20. The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators - Associated Presentation, by J.M. Dyke, Individual Contributions, 2004-04-20. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Concept Design Operation [Audience] Engineer
    - Associated Presentation 20054202.pdf (1558 kb)
    21. 2012-01-25---------Jump to [Top]
  21. 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)
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