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[Organization]: AECL 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.

148 files

    1968---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  1. The Performance of Zirconium Alloy Clad UO2 Fuel for Canadian Pressurized and Boiling Water Power Reactors, by R. D. Page and A. D. Lane, AECL, 01/05/1968. Doc type: Report.
    Summary: This paper presents the most recent information (as of 1968) on the performance of CANDU fuel, and goes on to summarize the results of an extensive irradiation program to develop fuels for boiling water cooled reactors.
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Materials Engineering [Topic] Function Performance [Phase] Design Development Operation [Audience] Engineer
    - 19680101.pdf (2338 kb)
  2. Basic Course for Radiation Surveyors and Contamination Monitors of the Radiation and Industrial Safety Branch, by J.H. Fenn and W.R. Bush, AECL, 01/09/1968. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Design Operation [Audience] Engineer Grad Technician Ugrad
    - 20100200.pdf (6970 kb)
    3. 1971---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  3. Commissioning and Operating Experience with Canadian Nuclear Electric Stations, by L. W. Woodhead, D. C. Milley, K. E. Elston, E.P. Horton, A. Dahlinger and R.C. Johnston, AECL, 06/09/1971. Doc type: Report.
    Summary:  
    Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Performance [Phase] Commissioning Operation [Audience] Engineer Manager Technician
    - Paper No. A/Conf. 49/A/148 presented at the Fourth U.N. International Conference on the Peaceful Uses of Atomic Energy, Geneva, 6-16 September, 1971 19710101.pdf (965 kb)
    4. 1972---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  4. 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)
    5. 1976---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  5. 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)
    6. 1980---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  6. Fundamentals of CANDU Reactor Nuclear Design (TDAI-244), by A.A. Pasanen, AECL, 01/01/1980. Doc type: Report.
    Summary: A Lecture Series given at Trieste 22 January - 28 March 1980, TDAI-244 1980 August
    Keywords: [Concept] - [SI] 31000 Reactor 37000 Fuel [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Manager Ugrad
    - Title and Table of Contents 20042000.pdf (176 kb)
    - Chapter 1 - Introduction 20042001.pdf (35 kb)
    - Chapter 2 - Physical Description of the CANDU-600 20042002.pdf (672 kb)
    - Chapter 3 - Methodology for Reactor Physics Analysis In Core Design 20042003.pdf (1922 kb)
    - Chapter 4 - Initial Fuel Loading Determination 20042004.pdf (379 kb)
    - Chapter 5 - Physics Analysis and Tests Related to Commissioning 20042005.pdf (764 kb)
    - Bibliography 20042006.pdf (111 kb)
    7. 1989---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  7. CANDU Advanced Plutonium Burner - The Canadian Response to the ALWR, by A.R. Dastur and A.C. Mao , AECL, 01/05/1989. Doc type: Paper.
    Summary: As published in the Canadian Nuclear Society Bulletin Vol. 10, No. 3, 1989 with the kind permission of the CNS: It is demonstrated that the prescnt CANDU design concept has potential for increased conversion and resource utilization compared with other reactor concepts. Discussed here is a CANDU based concept thau utilizes energy produced by subcritical multiplication in a fertile region designed for accelerated plutonium production is presented. Its feasibility is based on incorporating the channels with fertile material into the primary heal transport circuit. Calculations with multigroup transport codes predict very high fuel utilization due to the production and burnup of fissile plutonium in the fertile region.
    Keywords: [Concept] Reactor Physics [SI] 03300 Nuclear Engineering 31000 Reactor 37000 Fuel [Discipline] Nuclear Engineering [Topic] Conceptual Reactor Physics [Phase] Concept [Audience] Engineer Grad Manager Ugrad Vendor
    - 19890101.pdf (299 kb)
    8. 1991---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  8. Chernobyl – A Canadian Perspective, by V.G. Snell and J.Q. Howieson, AECL, 01/08/1991. 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)
    9. 1993---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  9. 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)
    10. 1995---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  10. Canada's Nuclear Achievement: Technical and Economic Perspectives, by T.E. Rummery and J.A. MacPherson, AECL, 01/07/1995. Doc type: Paper.
    Summary: As published in the Canadian Nuclear Society Bulletin Vol. 16, No. 2, 1995 with the kind permission of the CNS: Canada's leading role and eminent accomplishments in nuclear development now span more than half a century. They encompass aspects as diverse as the design and sale of nuclear power reactors and research reactor technology, to the establishment of a corps of scientists, engineers and technologists with the expertise to address a wide scope of important nuclear science issues. To address the many facets of Canada's nuclear activities over the past 50 years would obviously require space far beyond that available in this paper. We have therefore limited this review to highlights we judge to be the most pertinent and interesting from an historical, technical and economic perspective. We also indicate briefly our view of the future of nuclear power in the overall context of energy needs in a world that is becoming more industrial and increasingly environmentally conscious.
    Keywords: [Concept] General [SI] 00000 General Project [Discipline] History [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad High Manager Technician Ugrad Vendor
    - 19950101.pdf (873 kb)
  11. Synergistic Nuclear Fuel Cycles of the Future, by D.A. Meneley, A.R. Dastur, P.J. Fehrenbach and K.H. Talbot, AECL, 11/09/1995. Doc type: Paper.
    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 20054701.pdf (504 kb)
    - Global 1995, International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France 20054702.pdf (443 kb)
    12. 1998---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  12. 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)
    13. 1999---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  13. CANDU Fuel Management Course, by Ben Rouben, AECL, 01/03/1999. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
    - Cover Page 20031100.pdf (91 kb)
    - Complete Course 20031101.pdf (286 kb)
    - Basic Characteristics of the CANDU Lattice 20031111.pdf (186 kb)
    - The CANDU Reactivity Devices 20031112.pdf (147 kb)
    - Detector Systems 20031113.pdf (141 kb)
    - Computational Scheme for CANDU Neutronics 20031114.pdf (182 kb)
    - General Discussion on CANDU Fuel Management 20031115.pdf (125 kb)
    - Equilibrium-Core Design 20031116.pdf (217 kb)
    - Ongoing Reactor Operation with Channel Refuellings 20031117.pdf (252 kb)
    - Effects of 135Xe 20031118.pdf (151 kb)
    - Summary 20031119.pdf (61 kb)
    - Basic Characteristics of the CANDU Lattice - Figures 20031121.pdf (324 kb)
    - The CANDU Reactivity Devices - Figures 20031122.pdf (404 kb)
    - Detector Systems - Figures 20031123.pdf (418 kb)
    - Computational Scheme for CANDU Neutronics - Figures 20031124.pdf (83 kb)
    - General Discussion on CANDU Fuel Management - Figures 20031125.pdf (78 kb)
    - Equilibrium-Core Design - Figures 20031126.pdf (309 kb)
    - Ongoing Reactor Operation with Channel Refuellings - Figures 20031127.pdf (323 kb)
    - Effects of 135Xe - Figures 20031128.pdf (99 kb)
  14. CANDU Safety - presentations in Shanghai, 1999, by V. Snell, AECL, 21/06/1999. 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 19990102.pdf (84 kb)
    - Nuclear Safety Characteristics 19990103.pdf (286 kb)
    - Thermalhydraulic Safety Characteristics of CANDU Reactors 19990104.pdf (1183 kb)
    - Safety Functions - Shutdown Systems 19990105.pdf (517 kb)
    - Heat Removal 19990106.pdf (767 kb)
    - Emergency Core Cooling 19990107.pdf (1182 kb)
    - Containment 19990108.pdf (699 kb)
    - Grouping and Separation 19990109.pdf (65 kb)
    - Design and Analysis Process 19990110.pdf (524 kb)
    - Reactivity Control 19990111.pdf (412 kb)
    - Large Loss of Coolant Accident 19990112.pdf (578 kb)
    - Small Loss of Coolant Accident 19990113.pdf (651 kb)
    - Loss of Heat Sink 19990114.pdf (199 kb)
    - Loss of Forced Circulation 19990115.pdf (1517 kb)
    - Large Loss of Coolant Accident with Coincident Loss of Emergency Core Cooling 19990116.pdf (554 kb)
    - Severe Core Damage Accidents 19990117.pdf (478 kb)
    - Safety Research and Development 19990118.pdf (1851 kb)
    - Safety Research and Development Programs 19990119.pdf (903 kb)
    - Safety Analysis Tools 19990120.pdf (608 kb)
    - Probabilistic Safety Analysis 19990121.pdf (81 kb)
    - Regulation of CANDU 19990122.pdf (1223 kb)
    - Regulatory Requirements for Design 19990123.pdf (162 kb)
    - Regulatory Requirements for Accident Analysis 19990124.pdf (60 kb)
    - CANDU 9 Design Overview 19990125.pdf (630 kb)
    - CANDU 9 Safety and Licensability 19990126.pdf (580 kb)
  15. 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)
    16. 2000---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  16. RFSP Training Course, by Benoit Arsenault, AECL, 29/03/2000. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
    - Chapter 01 - Course Agenda 20054301.pdf (106 kb)
    - Chapter 02 - General Intro to Methods of Physics Analysis & Physics Computer Codes 20054302.pdf (381 kb)
    - Chapter 03 - The RFSP Direct-Access File 20054303.pdf (274 kb)
    - Chapter 04 - RFSP Model 20054304.pdf (400 kb)
    - Chapter 05 - Time-Average Model 20054305.pdf (322 kb)
    - Chapter 06 - Spatial Kinetics 20054306.pdf (272 kb)
    - Chapter 07 - Powderpufs-V 20054307.pdf (348 kb)
    - Chapter 08 - *Simulate and *Intrep 20054308.pdf (494 kb)
    - Chapter 09 - Flux and Power Mapping in RFSP 20054309.pdf (375 kb)
    - Chapter 10 - RRS Modelling in RFSP 20054310.pdf (275 kb)
    - Chapter 11 - *INSTANTAN 20054311.pdf (127 kb)
    - Chapter 12 - RFSP Code Development 20054312.pdf (336 kb)
    17. 2001---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  17. 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)
  18. 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)
  19. Why a Chernobyl-type accident cannot happen in CANDU reactors, AECL, 03/01/2001. 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)
  20. 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)
  21. Fuel for the Next Millennia, by Dan Meneley, AECL, 06/03/2001. 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)
  22. Starting Up a CANDU Reactor, by Dan Meneley, AECL, 20/07/2001. Doc type: Paper.
    Summary: CANDU power reactor designers and operators are fully aware of the need for caution in starting up power reactors. However, the open literature describing these established methods is quite sparse, especially with regard to the unique advantages in operability and safety that arise from the computer-driven Reactor Regulating System (RRS). The following text provides a general outline of one procedure appropriate for start-up of a CANDU 6 reactor.
    Keywords: [Concept] - [SI] 90000 Operations and Commissioning [Discipline] Nuclear Engineering [Topic] Reactor Physics [Phase] Operation [Audience] College Engineer Manager Technician Ugrad
    - Abbreviated Step-by Step Procedure 20010401.pdf (94 kb)
    23. 2002---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  23. Introduction to Reactor Physics, by Ben Rouben, AECL, 01/09/2002. Doc type: Course.
    Summary: This is a descriptive course on the physics of CANDU reactors. The objective is to familiarize you with the basic concepts and ideas, definitions and quantities which are important in the understanding of reactor physics. The discussion will be at a basic level, as this is an introduction to the subject. Very little emphasis is placed on complex equations or difficult mathematics. The desired outcome of this course is that you will be able in the future to understand and follow reactor-physics discussions in meetings, reports or presentations.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Ugrad
    - 20040501.pdf (369 kb)
    - Presentation 20040502.pdf (13610 kb)
  24. 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)
    25. 2003---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  25. 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)
    - CNS 2003 Conference Paper 20031801.pdf (3687 kb)
  26. Safer Nuclear Energy for the Future, by Dan Meneley, AECL, 30/06/2003. 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 20041001.pdf (115 kb)
    - Lecture 2 - Past Design Evolution 20041002.pdf (103 kb)
    - Lecture 3 - Future Design Directions 20041003.pdf (136 kb)
    - Lecture 4 - The Long Term 20041004.pdf (205 kb)
    27. 2010---------Jump to [Top] [Organization] [Concept] [SI] [Discipline] [Topic] [Phase] [Audience]
  27. 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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