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[SI]: 03000 Engineering Science and Technology 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.

182 files

    1972---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  1. AECL Lectures on Nuclear Power Symposium, by G.A. Pon, AECL, 25/05/1972. 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 19720102.pdf (1025 kb)
    - Lecture 3 - Power Reactor Types 19720103.pdf (3378 kb)
    - Lecture 4 - Reactor Physics 19720104.pdf (1755 kb)
    - Lecture 5 - Canadian Reactor Fuel 19720105.pdf (3924 kb)
    - Lecture 8 - System Analysis 19720108.pdf (1770 kb)
    - Lecture 9 - Reactor and Station Control 19720109.pdf (2715 kb)
    - Lecture 10 - Plant Layout 19720110.pdf (3190 kb)
    - Lecture 11 - Accident Analysis 19720111.pdf (1418 kb)
    - Lecture 12 - Licensing 19720112.pdf (1755 kb)
    - Lecture 13 - Training 19720113.pdf (1432 kb)
    - Lecture 14 - Canadian Power Reactor Fuel. See AECL 5609 doc#19760101 for an updated version. 19720114.pdf (2844 kb)
    - Lecture 15 - Construction 19720115.pdf (3542 kb)
    - Lecture 16 - Costs 19720116.pdf (764 kb)
    - Lecture 17 - Development Potential 19720117.pdf (1390 kb)
    - Lectures 6 and 7 - Heat Transport and Auxiliary Systems 19720167.pdf (2431 kb)
    2. 1976---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  2. Canadian Power Reactor Fuel, by R.D. Page, AECL, 01/03/1976. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 37000 Fuel [Discipline] Materials Engineering Mechanical Engineering [Topic] Heat Transfer Thermalhydraulics [Phase] Design Description [Audience] College Engineer Technician Ugrad
    - AECL 5609, updated version of Lecture 14 of the 1974 Nuclear Power Symposium Series, doc#19720114 19760101.pdf (8580 kb)
    3. 1993---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  3. Fundamentals of Power Reactors, CNSC, 01/01/1993. Doc type: Course.
    Summary: Fundamentals of power reactors covering basic nuclear processes, basic thermodynamics, thermalhydraulics, materials, nuclear systems and radiation protection.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Operation [Audience] College Engineer Ugrad
    - Science & Engineering Fundamentals - Part 1 19930201.pdf (5929 kb)
    - Science & Engineering Fundamentals - Part 2 19930202.pdf (7656 kb)
    - Nuclear Reactor System - Part 1 19930203.pdf (6312 kb)
    - Nuclear Reactor System - Part 2 19930204.pdf (8311 kb)
    - Nuclear Reactor System - Part 3 19930205.pdf (3791 kb)
    - Nuclear Reactor System - Part 4 19930206.pdf (4327 kb)
    - Radiation Protection 19930207.pdf (5465 kb)
  4. A Short History of the CANDU Nuclear Power System, by Gordon L. Brooks, AECL, 01/02/1993. Doc type: Paper.
    Summary: This paper provides a short historical summary of the evolution of the CANDU nuclear power system with emphasis on the roles played by Ontario Hydro and private sector companies in Ontario in collaboration with Atomic Energy of Canada Limited (AECL).
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Operation [Audience] College Engineer Manager Ugrad
    - 19930101.pdf (214 kb)
    5. 1996---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  5. CANDU Overiew, Course 3.2, by G. Bereznai, Chulalongkorn University, 01/11/1996. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Operation [Audience] College Engineer Ugrad
    - Chapter 0 - Title, Table of Contents, Objectives 20044201.pdf (89 kb)
    - Chapter 1 - Overall Unit 20044202.pdf (973 kb)
    - Chapter 2 - Reactor and Moderator 20044203.pdf (659 kb)
    - Chapter 3 - Reactor Control 20044204.pdf (881 kb)
    - Chapter 4 - Heat Transport 20044205.pdf (755 kb)
    - Chapter 5 - Steam, Turbine and Feedwater 20044206.pdf (666 kb)
    - Chapter 6 - Special Safety Systems 20044207.pdf (1131 kb)
    - Workbook, Chapter 0 - Table of Contents, Course Introduction 20044208.pdf (194 kb)
    - Workbook, Chapter 1 - Modules A to E 20044209.pdf (3559 kb)
    - Workbook, Chapter 2 - Modules A to C 20044210.pdf (688 kb)
    - Workbook, Chapter 3 - Modules A to C 20044211.pdf (2317 kb)
    - Workbook, Chapter 4 - Modules A to D 20044212.pdf (1115 kb)
    - Workbook, Chapter 5 - Modules A & B 20044213.pdf (1110 kb)
    - Workbook, Chapter 6 - Modules A to D 20044214.pdf (464 kb)
    6. 1998---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  6. 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, 22/09/1998. 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 19980102.pdf (2650 kb)
    - Moderator, HTS, Heavy Water 19980103.pdf (2454 kb)
    - Main Steam & T/G Systems 19980104.pdf (2626 kb)
    - Special Safety Systems 19980105.pdf (949 kb)
    - CANDU Reactor Control 19980106.pdf (1038 kb)
    7. 1999---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  7. China Journal of Nuclear Power Engineering, 1999 Vol 20 No. 6, by Xu Jijun and K.R. Hedges, AECL, 01/10/1999. 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 20054402.pdf (3387 kb)
    - Paper 03 - Reactor Core Structure of Qinshan Phase III CANDU Nuclear Power Plant 20054403.pdf (1893 kb)
    - Paper 04 - Moderator, Heat Transport, and Steam Systems of Qinshan Phase III Nuclear Power Plant 20054404.pdf (353 kb)
    - Paper 05 - Fuel Handling System for Qinshan Phase III Nuclear Power Plant 20054405.pdf (649 kb)
    - Paper 06 - Control System of Qinshan Phase III Nuclear Power Plant, by Zhang Jianmin 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 20054407.pdf (2543 kb)
    - Paper 08 - Safety Systems and Safety Analysis of Qinshan Phase III Nuclear Power Plant 20054408.pdf (197 kb)
    - Paper 09 - Design and Performance of Fuel for Qinshan Phase III Nuclear Power Plant 20054409.pdf (168 kb)
    - Paper 10 - Computer-Aided Engineering for Qinshan CANDU Projects 20054410.pdf (366 kb)
    - Paper 11 - Fuel Management of CANDU Reactors 20054411.pdf (252 kb)
    - Paper 12 - Physics Codes and Methods for CANDU Reactors 20054412.pdf (240 kb)
    - Paper 13 - Thermalhydraulic Design Methods and Computer Codes for CANDU Reactors 20054413.pdf (577 kb)
    - Paper 14 - Operational Characteristics and Management of the Qinshan Phase III CANDU Nuclear Power Plant 20054414.pdf (201 kb)
    - Paper 15 - Advanced CANDU Fuel Cycle Vision 20054415.pdf (80 kb)
    - Paper 16 - A Brief Introduction to CANDU9 – A New Generation of Pressurized Heavy Water Reactors 20054416.pdf (189 kb)
    8. 2000---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  8. How and Why is CANDU designed the way it is, by Bill Garland, CANTEACH, 01/12/2000. Doc type: Paper.
    Summary: Why we need nuclear power; A look at the nuclear reactor in a nutshell; The engineering approach - CANDUs are engineered systems, typified by functional decomposition; A quick overview of CANDU vs PWR vs BWR and others.
    Keywords: [Concept] Overview [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Intro and Overview [Phase] Concept Design [Audience] High
    - 20000101.pdf (819 kb)
    9. 2001---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  9. CANDU Poster, AECL, 01/01/2001. 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. CANDU - How a Reactor Works, AECL, 02/01/2001. 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. CANDU Origins and Evolution, by Gordon L.Brooks and John S. Foster, AECL, 01/02/2001. Doc type: Paper.
    Summary: While the name 'CANDU' was not adopted until the 1960's, the CANDU program can be considered to have started in early 1954. At that time, a team, called the Nuclear Power Group, was established to undertake studies intended to identify a potential Canadian nuclear power system. While the team operated under the auspices of AECL and was located in Building 456 at AECL's Chalk River Laboratory, its membership was drawn from a cross-section of Canadian utility and industrial organizations supported, as required, with "nuclear" expertise provided by AECL staff.
    Keywords: [Concept] Overview [SI] 03000 Engineering Science and Technology 31000 Reactor [Discipline] General Engineering Nuclear Engineering [Topic] Conceptual Important Parameters Intro and Overview [Phase] Concept Design Design Evolution [Audience] Manager
    - Overview 20010301.pdf (132 kb)
    - Why CANDU 20010302.pdf (99 kb)
    - Figure of 8 20010303.pdf (111 kb)
    - Emergency Core Cooling System 20010304.pdf (107 kb)
    - The Origin and Evolution of the Second Shutdown System 20010305.pdf (101 kb)
    12. 2002---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  12. Heavy Water Reactors: Status and Projected Development, Technical Report Series No. 407, IAEA, Vienna, Austria, 2002., IAEA, 01/01/2002. Doc type: .
    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)
  13. ACR Presentation given to the US Nuclear Regulatory Commission on September 25-26, 2002, AECL, 25/09/2002. 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---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  14. Qinshan CANDU Project Construction Experiences and Lessons Learned to Reduce Capital Costs and Schedule Based on Qinshan CANDU Project in China, by Ken Petrunik, Kang Rixin, AECL, 01/02/2003. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Construction [Audience] College Engineer Ugrad
    - 20031701.pdf (1470 kb)
    - 20031901.pdf (513 kb)
  15. Chemistry Control Requirements for Generic CANDU Power Stations, by Stu Groom, NB Power, 01/05/2003. 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 20032102.pdf (264 kb)
    - Annulus Gas System Chemistry Control 20032103.pdf (362 kb)
    - Primary Heat Transport System Chemistry Control 20032104.pdf (667 kb)
    - Feeder Thinning 20032105.pdf (600 kb)
    - Boiler Feedwater / Condensate Chemistry Control 20032106.pdf (605 kb)
    - Steam Generator Chemistry Control 20032107.pdf (430 kb)
    - ECC and Dousing Systems Chemistry Control 20032108.pdf (116 kb)
    - Spent Fuel Bay Chemistry Control 20032109.pdf (85 kb)
    - Plant Chemistry Controm - PLGS Manual 20032110.pdf (4826 kb)
    - PHT System Chemitry Monitoring and Control Improvements 20032111.pdf (753 kb)
    - Chemistry Laboratory Analytical Procedure – Gadolinium Arsenazo III 20032112.pdf (175 kb)
    - Chemistry Specifications 20032113.pdf (119 kb)
  16. Qinshan Project, by Ken Petrunik, AECL, 01/06/2003. 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. CANDU Fundamentals, CNSC, 24/06/2003. Doc type: Course.
    Summary: Fundamentals of reactor processes of the CANDU reactor.
    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
    - Complete Course 20040700.pdf (6375 kb)
    - Objectives 20040701.pdf (422 kb)
    - Atomic Structure 20040702.pdf (257 kb)
    - Radioactivity - Spontaneous Nuclear Processes 20040703.pdf (372 kb)
    - Nuclear Stability And Instability 20040704.pdf (264 kb)
    - Activity and Half-Life 20040705.pdf (271 kb)
    - Neutrons and Neutron Interactions 20040706.pdf (296 kb)
    - Fission 20040707.pdf (488 kb)
    - Fuel, Moderator, and Reactor Management 20040708.pdf (231 kb)
    - Nuclear Safety 20040709.pdf (182 kb)
    - Nuclear Power Reactors 20040710.pdf (205 kb)
    - Candu Reactor Construction 20040711.pdf (653 kb)
    - Moderator and Moderator System 20040712.pdf (196 kb)
    - Moderator Auxiliary Systems 20040713.pdf (253 kb)
    - Heat Transport System (HTS) 20040714.pdf (410 kb)
    - Heat Transport Auxiliary Systems 20040715.pdf (372 kb)
    - Reactor Fuel 20040716.pdf (503 kb)
    - Neutron Life Cycle 20040717.pdf (221 kb)
    - Criticality and Neutron Multiplication 20040718.pdf (297 kb)
    - Changes In Reactor Power With Time 20040719.pdf (236 kb)
    - Xenon: A Fission Product Poison 20040720.pdf (287 kb)
    - Reactivity Effects of Temperature Changes 20040721.pdf (268 kb)
    - Neutron Flux Control 20040722.pdf (311 kb)
    - Reactivity Mechanisms 20040723.pdf (538 kb)
    - Emergency Coolant Injection & Containment 20040724.pdf (795 kb)
    - The Conventional Side of the Station 20040725.pdf (1049 kb)
    - Other Major Systems 20040726.pdf (665 kb)
    - 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. Principes Fondamentaux des Réacteurs CANDU - CANDU Fundamentals, CNSC, 24/06/2003. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Operation [Audience] College Engineer Ugrad
    - Texte Complet 20060300.pdf (7093 kb)
    - Table des Matières 20060301.pdf (102 kb)
    - Chapitre 1 - Objectifs 20060302.pdf (105 kb)
    - Chapitre 2 - Structure de l’Atome 20060303.pdf (156 kb)
    - Chapitre 3 - Radioactivité - Phénomènes Nucléaires Spontanés 20060304.pdf (296 kb)
    - Chapitre 4 - Stabilité et Instabilité Nucléaires 20060305.pdf (198 kb)
    - Chapitre 5 - Activité et Période 20060306.pdf (177 kb)
    - Chapitre 6 - Les Neutrons et Leurs Interactions 20060307.pdf (206 kb)
    - Chapitre 7 - La Fission 20060308.pdf (382 kb)
    - Chapitre 8 - Combustible, Modérateur et Gestion du Réacteur 20060309.pdf (156 kb)
    - Chapitre 9 - Sûreté Nucléaire 20060310.pdf (141 kb)
    - Chapitre 10 - Réacteurs de Puissance 20060311.pdf (157 kb)
    - Chapitre 11 - Structure d’un Réacteur 20060312.pdf (820 kb)
    - Chapitre 12 - Modérateur et Circuit du Modérateur 20060313.pdf (125 kb)
    - Chapitre 13 - Circuits Auxiliaires du Modérateur 20060314.pdf (250 kb)
    - Chapitre 14 - Circuit Caloporteur (CC) 20060315.pdf (356 kb)
    - Chapitre 15 - Systèmes Auxiliaires du Circuit Caloporteur 20060316.pdf (321 kb)
    - Chapitre 16 - Le Combustible CANDU 20060317.pdf (575 kb)
    - Chapitre 17 - Cycle de Vie des Neutrons 20060318.pdf (126 kb)
    - Chapitre 18 - Criticité et Multiplication de Neutrons 20060319.pdf (189 kb)
    - Chapitre 19 - Changements dans la Puissance du Réacteur au Fil du Temps 20060320.pdf (149 kb)
    - Chapitre 20 - Un Produit de Fission Agissant Comme Poison : le Xénon 20060321.pdf (211 kb)
    - Chapitre 21 - Effets des Changements de Température sur la Réactivité 20060322.pdf (197 kb)
    - Chapitre 22 - Contrôle du Flux de Neutron 20060323.pdf (267 kb)
    - Chapitre 23 - Mécanismes de Contrôle de la Réactivité 20060324.pdf (461 kb)
    - Chapitre 24 - Injection d’Urgence de Caloporteur et Confinement 20060325.pdf (969 kb)
    - Chapitre 25 - Les Parties Non Nucléaires de la Centrale 20060326.pdf (1176 kb)
    - Chapitre 26 - Autres Grands Systèmes 20060327.pdf (752 kb)
    19. 2005---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  19. Nuclear Power Plant Systems and Operation, by G. Bereznai, University of Ontario Institute of Technology, 01/07/2005. Doc type: Reference.
    Summary: Nuclear Power Plant Systems and Operation course covering following: science fundamentals, equipment and systems principles relevant to CANDU reactors; CANDU reactor power plant systems and their operation.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Operation [Audience] College Engineer Ugrad
    - 20071000.pdf (2511 kb)
    20. 2010---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  20. ACR-1000 Technical Description Summary, AECL, 01/01/2010. Doc type: Report.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - 20100100.pdf (2399 kb)
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