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[Audience]: Grad 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: 252

    1962-11-01---------Jump to [Top]
  1. NPD Nucleonics Description, by Nucleonics, OPG, 1962-11-01. Doc type: Other.
    Summary:
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] Nuclear Engineering [Topic] - [Phase] Design Operation [Audience] College Engineer Grad Manager Technician Ugrad
    - NPD on the Line - a foldout description with layout diagrams and design date. NDP-NucleonicsNov1962.PDF (4922 kb)
    2. 1968-09-01---------Jump to [Top]
  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, 1968-09-01. 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. 1971-03-01---------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. 1971-05-01---------Jump to [Top]
  4. Do the Universities Prepare the Type of Engineers that our Nuclear Industry Needs, by G.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)
    5. 1986-01-01---------Jump to [Top]
  5. 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)
    6. 1987-03-01---------Jump to [Top]
  6. Nuclear Journal of Canada, 1987 Vol 1 No. 1, CNS, 1987-03-01. Doc type: Paper.
    Summary: The Nuclear Journal of Canada was launched in 1987. Four issues were published in that year but sadly publication then ceased.
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] - [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad Manager Technician Ugrad
    - Cover, Table of Contents and Editorial NJC-1-1-01.pdf (1539 kb)
    - The Formative Years of the Canadian Nuclear Society 1976-1984 NJC-1-1-02.pdf (1224 kb)
    - A Review of the Health Effects of Energy Development [See also Vol. 1 No. 4 for a followup discussion] NJC-1-1-03.pdf (729 kb)
    - Food Irradiation: Commercial and Scientific Review NJC-1-1-04.pdf (520 kb)
    - Technetium-iron Oxide Reactions Under Anaerobic Conditions: A Fourier Transform Infrared, FTIR Study NJC-1-1-05.pdf (357 kb)
    - Progress of the Swedish Radioactive Waste Management Program NJC-1-1-06.pdf (1534 kb)
    - A Non-Intrusive Neutron Method for Poison Concentration Monitoring in CANDU Reactors NJC-1-1-07.pdf (427 kb)
    - Containment Systems Capability NJC-1-1-08.pdf (1131 kb)
    - Chemistry Control at Bruce NGS 'B' from Construction to Commercial Operation NJC-1-1-09.pdf (382 kb)
    - Gestion du cycle de combustible a la Centrale Nucleaire Gentilly-2 NJC-1-1-10.pdf (762 kb)
    - Summaries of CNS Conferences, Seminars and Workshops. NJC-1-1-11.pdf (625 kb)
    7. 1987-06-01---------Jump to [Top]
  7. Nuclear Journal of Canada, 1987 Vol 1 No. 2, CNS, 1987-06-01. Doc type: Paper.
    Summary: The Nuclear Journal of Canada was launched in 1987. Four issues were published in that year but sadly publication then ceased.
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] - [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad Manager Technician Ugrad
    - Cover, Table of Contents and Editorial NJC-1-2-01.pdf (1782 kb)
    - Early Decisions in the Development of the CANDU Program NJC-1-2-02.pdf (719 kb)
    - Insights from Chernobyl on Severe Accident Assessment of CANDU Reactors NJC-1-2-03.pdf (829 kb)
    - Whole-Body Retention of99mTc-imidodiphosphate: A Measurement of Total Body Bone Turnover Rate NJC-1-2-04.pdf (250 kb)
    - Corrosion of Heat Exchanger Materials under Heat Transfer Conditions NJC-1-2-05.pdf (418 kb)
    - Concentration Processes under Tubesheet Sludge Piles in Nuclear Steam Generators NJC-1-2-06.pdf (937 kb)
    - Simulation Methodology for Pressure Tube Integrity Analysis and Comparison with Experiments NJC-1-2-07.pdf (575 kb)
    - The Drift Flux Model in the ASSERTSubchannel Code NJC-1-2-08.pdf (742 kb)
    - A Review of Low-Level Radioactive Waste Management Technology in the Canadian Nuclear Industry NJC-1-2-09.pdf (514 kb)
    - Characterization of Radioactive Wastes Incorporated in a Cement Matrix NJC-1-2-10.pdf (501 kb)
    - Spent Fuel Storage and Transportation Experience for the Idaho National Engineering Laboratory NJC-1-2-11.pdf (702 kb)
    - Summaries of CNS Conferences, Seminars and Workshops. NJC-1-2-12.pdf (474 kb)
    8. 1987-09-01---------Jump to [Top]
  8. Nuclear Journal of Canada, 1987 Vol 1 No. 3, CNS, 1987-09-01. Doc type: Paper.
    Summary: The Nuclear Journal of Canada was launched in 1987. Four issues were published in that year but sadly publication then ceased.
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] - [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad Manager Technician Ugrad
    - Cover, Table of Contents and Editorial NJC-1-3-01.pdf (1268 kb)
    - Chernobyl - A Canadian Technical Perspective NJC-1-3-02.pdf (1766 kb)
    - Seismic Qualification of CANDU-PHW Nuclear Power Plant Equipment NJC-1-3-03.pdf (660 kb)
    - Multifield Methods for Nuclear Thermalhydraulics Problems NJC-1-3-04.pdf (1030 kb)
    - CATHENA Simulation of Thermosiphoning in a Pressurized-Water Test Facility NJC-1-3-05.pdf (615 kb)
    - Use of Quantitative Indicators of Nuclear Safety in Ontario Hydro NJC-1-3-06.pdf (416 kb)
    - Safe, Permanent Disposal of Nuclear Fuel Waste NJC-1-3-07.pdf (942 kb)
    - The Projected Environmental Impacts of Transportation of Radioactive Material to the First United States Repository Site - An Overview NJC-1-3-08.pdf (491 kb)
    - Book Review: Fallout from Chernobyl by L. Ray Silver NJC-1-3-09.pdf (104 kb)
    - CNS Conferences, Seminars NJC-1-3-10.pdf (185 kb)
    9. 1987-12-01---------Jump to [Top]
  9. Nuclear Journal of Canada, 1987 Vol 1 No. 4, CNS, 1987-12-01. Doc type: Paper.
    Summary: The Nuclear Journal of Canada was launched in 1987. Four issues were published in that year but sadly publication then ceased.
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] - [Topic] Intro and Overview [Phase] - [Audience] College Engineer Grad Manager Technician Ugrad
    - Cover, Table of Contents and Editorial NJC-1-4-01.pdf (1312 kb)
    - The Outlook for Nuclear Power after Chernobyl NJC-1-4-02.pdf (499 kb)
    - Sea Dumping of Radioactive Wastes NJC-1-4-03.pdf (1065 kb)
    - The Effect of Steam Generator Tube Temperature on the Stress Corrosion Cracking of Alloy 600 NJC-1-4-04.pdf (663 kb)
    - Suitability Study of On-Line Leak Tests for CANDU Single-Unit Containment Buildings NJC-1-4-05.pdf (846 kb)
    - Trivac: A Modular Diffusion Code for Fuel Management and Design Applications NJC-1-4-06.pdf (472 kb)
    - Fuel for Thought NJC-1-4-07.pdf (876 kb)
    - Fusion Materials Issues NJC-1-4-08.pdf (916 kb)
    - The AC Device for Repositioning of Garter Springs in CANDU Reactors NJC-1-4-09.pdf (696 kb)
    - Waterlancing for CANDU Steam Generators NJC-1-4-10.pdf (370 kb)
    - Locating Gas Pipelines with Radioactive Sources NJC-1-4-11.pdf (145 kb)
    - Optimization of Darlington Tritium Removal Facility Performance: Effects of Key Process Variables NJC-1-4-12.pdf (230 kb)
    - Discussion: A Review of the Health Effects of Energy Development (Volume I, No. I, March 1987, pp. 14-24.) NJC-1-4-13.pdf (168 kb)
    - Book Reviews: (1) Planet Earth in Jeopardy: Environmental Consequences of Nuclear War by Lydia Datto; (2) Understanding Chernobyl by The Uranium Institute NJC-1-4-14.pdf (168 kb)
    - CNS Conferences, Seminars NJC-1-4-15.pdf (269 kb)
    10. 1989-05-01---------Jump to [Top]
  10. CANDU Advanced Plutonium Burner - The Canadian Response to the ALWR, by A.R. Dastur and A.C. Mao , AECL, 1989-05-01. 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)
    11. 1995-06-25---------Jump to [Top]
  11. 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)
    12. 1995-07-01---------Jump to [Top]
  12. Canada's Nuclear Achievement: Technical and Economic Perspectives, by T.E. Rummery and J.A. MacPherson, AECL, 1995-07-01. 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)
    13. 1996-02-01---------Jump to [Top]
  13. Introduction to Nuclear Reactor Kinetics 1.3, by Daniel Rozon, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: Predicting the evolution in time of the neutron population in a multiplying medium. Time variation of the reactor power (proportional to the total neutron population) is presented.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Table of Contents 20041800.pdf (31 kb)
    - Chapter 1 - Neutron/Nucleus Interactions and Fission 20041801.pdf (1008 kb)
    - Chapter 2 - The Diffusion Equation and the Steady State 20041802.pdf (1840 kb)
    - Chapter 3 - The Point Kinetics Equation 20041803.pdf (1190 kb)
    - Workbook to Chapter 1 - Neutron/Nucleus Interactions and Fission 20041804.pdf (447 kb)
    - Workbook to Chapter 2 - The Diffusion Equation and the Steady State 20041805.pdf (709 kb)
    - Workbook to Chapter 3 - The Point Kinetics Equations 20041806.pdf (385 kb)
    - Workbook to Chapter 4 - Elementary Solutions to the Kinetics Equations 20041807.pdf (398 kb)
    - Workbook to Chapter 5 - Approximate Solutions for Reactivity Ramps 20041808.pdf (276 kb)
  14. Thermal Study of Nuclear Reactors, Course 2.2, by A. Tapucu, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Design Design Analysis [Audience] Engineer Grad Ugrad
    - Title and Table of Contents 20043801.pdf (96 kb)
    - Chapter 1 - Fundamental Concepts 20043802.pdf (234 kb)
    - Chapter 2 - Single Phase Fluid Equations 20043803.pdf (200 kb)
    - Chapter 3 - Principles of Heat Transfer 20043804.pdf (1061 kb)
    - Chapter 4 - Forced Convection Heat Transfer 20043805.pdf (1624 kb)
    - Chapter 7 - Heat Removal from Nuclear Reactors 20043806.pdf (1557 kb)
    - Appendix 1 - Tensors 20043807.pdf (49 kb)
    - Appendix 2 - Stress in a Fluid 20043808.pdf (256 kb)
    - Appendix 3 - A Short Summary of Orthogonal Functions Used in Chapter 4 20043809.pdf (178 kb)
    - Workbook, Chapter 4 20043810.pdf (2301 kb)
    - Workbook, Chapter 7 20043811.pdf (2043 kb)
  15. Reactor Thermalhydraulics Analysis, Course 2.3, by W.J. Garland, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: Fundamentals of thermalhydraulic analysis (heat transfer and fluid mechanics)of the heat transport system.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Title and Table of Contents 20043901.pdf (144 kb)
  16. Nuclear Reactor Containment, Course 3.5, by J. Daams, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 20000 Buildings and Structures [Discipline] Civil Engineering [Topic] Conceptual Modelling [Phase] Concept Design [Audience] Engineer Grad Ugrad
    - Reference 1 - Requirements for Containment Systems for Nuclear Power Plants - Doc R7 20044501.pdf (2064 kb)
    - Reference 2 - Real Time Simulation of the Containment by A. Hodhod, L. Vindigni, H. Dana 20044502.pdf (1353 kb)
    - Reference 3 - ANSI 3.5 20044503.pdf (591 kb)
    - Reference 4 - Recent Advances in Concrete Containment Vessels in Japan by T.Koroda, T.Ebine, S.Sato, M. Kato 20044504.pdf (1353 kb)
    - Workbook, Chapter 0 - Title, Objectives 20044505.pdf (38 kb)
    - Workbook, Chapter 1 - Modules A to D 20044506.pdf (1317 kb)
    - Workbook, Chapter 2 - Modules A to C 20044507.pdf (1045 kb)
    - Workbook, Chapter 3 - Modules Ato E 20044508.pdf (1723 kb)
    - Workbook, Chapter 4 - Modules A to F 20044509.pdf (1628 kb)
  17. Nuclear Reactor Safety Design, Course 3.7, by W.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 20044702.pdf (441 kb)
    - Chapter 3 - Safety Criteria 20044703.pdf (396 kb)
    - Chapter 4 - Design Basis Accidents 20044704.pdf (131 kb)
    - Chapter 5 - Probabilistic Risk Assessment 20044705.pdf (154 kb)
    - Chapter 6 - Safety Analysis 20044706.pdf (190 kb)
    - Chapter 7 - Safety Systems 20044707.pdf (365 kb)
    - Chapter 8 - Good Design Principles & Practices 20044708.pdf (211 kb)
    - References 20044709.pdf (91 kb)
    - Appendix 1 - NRX Accident 20044710.pdf (308 kb)
    - Appendix 2 - Subcategory A.1 Events 20044711.pdf (135 kb)
    - Appendix 3 - Applicable Codes & Standards 20044712.pdf (99 kb)
    - Appendix 4 - Organization of Licensing Basis Document 20044713.pdf (64 kb)
    - Appendix 5 - Accident Analysis Matrix 20044714.pdf (97 kb)
    - Appendix 6 - Large LOCA 20044715.pdf (193 kb)
    - Appendix 7 - Failure Data 20044716.pdf (157 kb)
    - Appendix 8 - Accident Analysis Overview by R. Holmes 20044717.pdf (287 kb)
    - Workbook, Chapter 1 - Figures 20044718.pdf (638 kb)
    - Workbook, Chapter 2 - Figures 20044719.pdf (772 kb)
    - Workbook, Chapter 3 - Figures 20044720.pdf (656 kb)
    - Workbook, Chapter 4 - Figures 20044721.pdf (215 kb)
    - Workbook, Chapter 5 - Figures 20044722.pdf (266 kb)
    - Workbook, Chapter 6 - Figures 20044723.pdf (294 kb)
    - Workbook, Chapter 7 - Figures 20044724.pdf (600 kb)
    - Workbook, Chapter 8 - Figures 20044725.pdf (389 kb)
    18. 1997-01-01---------Jump to [Top]
  18. Nuclear Theory I (Statics), or Introduction to Nuclear Technology 1.1a, by Robin Chaplin, Chulalongkorn University, 1997-01-01. Doc type: Course.
    Summary: This lecture material is supplementary to Chulalongkorn University Training Program Course # 1.1, Nuclear Physics and Reactor Theory by Ian Cameron (Course 22106), Modules 1 to 7]
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations Conceptual Reactor Physics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Introduction 20041700.pdf (177 kb)
    - Section 1 - Nuclear Physics 20041701.pdf (461 kb)
    - Section 1 - Nuclear Physics (Figures) 20041702.pdf (346 kb)
    - Section 2 - Nuclear Interactions 20041703.pdf (727 kb)
    - Section 2 - Nuclear Interactions (Figures) 20041704.pdf (775 kb)
    - Section 3 - Neutron Diffusion 20041705.pdf (255 kb)
    - Section 4 - Reactor Theory 20041706.pdf (534 kb)
    - Section 4 - Reactor Theory (Figures) 20041707.pdf (456 kb)
    - Section 5 - Reactor Kinetics 20041708.pdf (1075 kb)
    - Question Bank 20041709.pdf (1095 kb)
    - Reference Data 20041710.pdf (537 kb)
    19. 1997-10-01---------Jump to [Top]
  19. Reactor Mechanical Design, Course 3.6, by R.S. Porter, Chulalongkorn University, 1997-10-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Mechanical Engineering [Topic] Conceptual Physical Description [Phase] Concept Design [Audience] Engineer Grad Ugrad
    - Section 0 - Title, Table of Contents 20044601.pdf (99 kb)
    - Section 1 - Overview, Reg. Req’ts, Codes & Standards 20044602.pdf (531 kb)
    - Section 2 - Design Philosophy, Rationale, Key Operating Parameters 20044603.pdf (481 kb)
    - Section 3 - Stress Analysis of Reactor Structures 20044604.pdf (253 kb)
    - Section 4 - Excitation Spectra Etc. 20044605.pdf (374 kb)
    - Section 5 - Design of Fuel Channels 20044606.pdf (622 kb)
    - Section 6 - Design of Reactivity Control Units 20044607.pdf (1181 kb)
    - Section 7 - Design of Fuel Handling System 20044608.pdf (1121 kb)
    - Appendix 1 - Design Loads and Load Cases for CANDU 6 20044609.pdf (174 kb)
    - Appendix 2 - Stresses for Design Cases 20044610.pdf (316 kb)
    - Appendix 3 - Finite Element Analysis 20044611.pdf (96 kb)
    - Appendix 4 - Seismic Behaviour of CANDU 6 20044612.pdf (168 kb)
    - Workbook, Chapter 1 - Figures 20044613.pdf (208 kb)
    - Workbook, Chapter 2 - Figures 20044614.pdf (778 kb)
    - Workbook, Chapter 3 - Figures 20044615.pdf (355 kb)
    - Workbook, Chapter 4 - Figures 20044616.pdf (455 kb)
    - Workbook, Chapter 5 - Figures 20044617.pdf (150 kb)
    - Workbook, Chapter 6 - Figures 20044618.pdf (964 kb)
    - Workbook, Chapter 7 - Figures 20044619.pdf (1006 kb)
    20. 1998-02-01---------Jump to [Top]
  20. Neutronic Analysis of Reactors, Course 1.7, by J. Koclas, Chulalongkorn University, 1998-02-01. Doc type: Course.
    Summary: Covers methods used to solve reactor physics problems in both steady state and transient.
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Basic Equations [Phase] Design [Audience] Engineer Grad Ugrad
    - Chapter 0 - Title and Table of Contents 20043601.pdf (175 kb)
    - Chapter 1 - Introduction 20043602.pdf (102 kb)
    - Chapter 2 - Parameter Definitions 20043603.pdf (144 kb)
    - Chapter 3 - Derivation of the Space-Time Kinetics Equations 20043604.pdf (174 kb)
    - Chapter 4 - Energy Condensation 20043605.pdf (137 kb)
    - Chapter 5 - Matrix Form of Equations 20043606.pdf (60 kb)
    - Chapter 6 - Spatial Mesh Considerations 20043607.pdf (592 kb)
    - Chapter 7 - Statics 20043608.pdf (255 kb)
    - Chapter 8 - Numerical Methods in Reactor Statics 20043609.pdf (420 kb)
    - Chapter 9 - KInetics Methods Classification 20043610.pdf (34 kb)
    - Chapter 10 - Point Kinetics 20043611.pdf (233 kb)
    - Chapter 11 - Elementary Numerical Integration Techniques 20043612.pdf (218 kb)
    - Chapter 12 - Adiabatic Method 20043613.pdf (140 kb)
    - Chapter 13 - Quasistatic Method 20043614.pdf (102 kb)
    - Chapter 14 - Modal Synthesis 20043615.pdf (164 kb)
    - Chapter 15 - Mesh Centered Finite Difference 20043616.pdf (409 kb)
    - Chapter 16 - Time Integration of the Space-Time Kinetics Equations 20043617.pdf (178 kb)
    - Chapter 17 - Comparisons of Spatial Approximations 20043618.pdf (300 kb)
  21. Reactor Thermalhydraulics Analysis, Course 2.3, by W.J. Garland, Chulalongkorn University, 1998-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Glossary and Foreword 20043902.pdf (152 kb)
    - Chapter 1 - Course Overview 20043903.pdf (140 kb)
    - Chapter 2 - Basic Equations for Thermalhydraulic Systems Analysis 20043904.pdf (561 kb)
    - Chapter 3 - Nodalization 20043905.pdf (303 kb)
    - Chapter 4 - Equation of State 20043906.pdf (338 kb)
    - Chapter 5 - The Rate Form of the Equation of State 20043907.pdf (512 kb)
    - Chapter 6 - Thermalhydraulic Network Simulation 20043908.pdf (343 kb)
    - Chapter 7 - Empirical Correlations 20043909.pdf (532 kb)
    - Chapter 8 - On Design Tools 20043910.pdf (481 kb)
    - Workbook, Chapter 1 20043911.pdf (151 kb)
    - Workbook Chapter, 2 20043912.pdf (767 kb)
    - Workbook Chapter 3 20043913.pdf (466 kb)
    - Workbook Chapter 4 20043914.pdf (604 kb)
    - Workbook Chapter 5 20043915.pdf (847 kb)
    - Workbook Chapter 6 20043916.pdf (614 kb)
    - Workbook Chapter 7 20043917.pdf (719 kb)
    - Workbook Chapter 8 20043918.pdf (903 kb)
    - Workbook Figures 20043919.pdf (509 kb)
  22. Reactor Thermalhydraulics Analysis, Supplementary, Course 2.3a, by W.J. Garland, Chulalongkorn University, 1998-02-01. Doc type: Course.
    Summary: Supplementary info for thermalhydraulic analysis (heat transfer and fluid mechanics)of the heat transport system.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Appendices 1 - 4 1 - Time Derivatives 2 - The Reynolds Transport Theorem 3 - Rearrangement of Independent Variables 4 - Fast Calculation of Light-Water Properties 20044001.pdf (647 kb)
    - Calculation of Water Properties 20044002.pdf (947 kb)
    - THSIM User Manual 20044003.pdf (733 kb)
    - A Pedagogical Look at Fully- and Semi-Implicit Solutions to T-H Eq'ns 20044004.pdf (320 kb)
    - Basic Equations for T-H Systems Analysis 20044005.pdf (590 kb)
    - Miscellaneous Figures and Equations 20044006.pdf (315 kb)
    23. 1999-03-01---------Jump to [Top]
  23. CANDU Fuel Management Course, by Ben Rouben, AECL, 1999-03-01. 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)
    24. 2000-03-29---------Jump to [Top]
  24. RFSP Training Course, by Benoit Arsenault, AECL, 2000-03-29. 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)
    25. 2000-06-01---------Jump to [Top]
  25. Radiation Monitoring Notebook, by James T. Voss, Individual Contributions, 2000-06-01. Doc type: Reference.
    Summary: LA-UR-00-2584 James T. (Tom) Voss, NRRPT, CHP June 2000 (Feb. 2001 Update)
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Design Operation [Audience] Engineer Grad Technician Ugrad
    - 20041901.pdf (191 kb)
    26. 2001-06-01---------Jump to [Top]
  26. Radiation Protection ("Green Book"), by Jan Burnham, NB Power, 2001-06-01. Doc type: Book.
    Summary:
    Keywords: [Concept] - [SI] 03400 Radiation Protection (including Waste Management) [Discipline] Health Physics [Topic] Radiation [Phase] Design Operation [Audience] Engineer Grad Technician Ugrad
    - Cover Page 20031300.pdf (98 kb)
    - Chapter 1 - Atomic Structure 20031301.pdf (898 kb)
    - Chapter 2 - Radiation Theory 20031302.pdf (1729 kb)
    - Chapter 3 - Radiation Dose 20031303.pdf (2016 kb)
    - Chapter 4 - Biological Effects Of Radiation 20031304.pdf (1341 kb)
    - Chapter 5 - Dose Limits And Risk 20031305.pdf (1929 kb)
    - Chapter 6 - Instruments 20031306.pdf (8721 kb)
    - Chapter 7 - Protection From External Exposures 20031307.pdf (3122 kb)
    - Chapter 8 - Internal Dose 20031308.pdf (1414 kb)
    - Chapter 9 - Contamination Control 20031309.pdf (9704 kb)
    - Chapter 10 - Dose Records 20031310.pdf (1925 kb)
    - Chapter 11 - Waste Management 20031311.pdf (4460 kb)
    - Chapter 12 - Work Planning 20031312.pdf (2171 kb)
    - Chapter 13 - Emergency Planning 20031313.pdf (2632 kb)
    - Answers to Problems 20031314.pdf (1093 kb)
    - Index 20031315.pdf (1210 kb)
    27. 2003-05-10---------Jump to [Top]
  27. Preserving CANDU Technical Knowledge – The CANTEACH Project, by Bill Garland, Yulia Kosarenko, Malcolm Lightfoot, Dan Meneley, CANTEACH, 2003-05-10. Doc type: Paper.
    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
    - 20031401.pdf (245 kb)
  28. Preservation and Dissemination of CANDU® Technical Knowledge (The CANTEACH Project), by Bill Garland, Yulia Kosarenko, Malcolm Lightfoot, Dan Meneley, CANTEACH, 2003-05-10. Doc type: Paper.
    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
    - 20031501.pdf (299 kb)
    29. 2003-06-01---------Jump to [Top]
  29. 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)
    30. 2003-10-01---------Jump to [Top]
  30. Nuclear Safety & Reliability Course, by Dan 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 20032201.pdf (293 kb)
    - Week 2 20032202.pdf (461 kb)
    - Week 3 20032203.pdf (378 kb)
    - Week 4 20032204.pdf (335 kb)
    - Week 5 20032205.pdf (666 kb)
    - Week 6 20032206.pdf (636 kb)
    - Week 7 20032207.pdf (930 kb)
    - Week 8 20032208.pdf (1943 kb)
    - Week 9 20032209.pdf (2120 kb)
    - Week 10 20032210.pdf (433 kb)
    - Week 11 20032211.pdf (476 kb)
    - Week 12 20032212.pdf (353 kb)
    31. 2009-05-30---------Jump to [Top]
  31. 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)
  32. 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)
    33. 2011-01-01---------Jump to [Top]
  33. Concept Maps, by Bill Garland, CANTEACH, 2011-01-01. Doc type: Other.
    Summary: Illustrated are the overall concepts and topics in the various disciplines involved in the design and operation of CANDU reactors. This provides some guidance for the detailed study of CANDU reactors.
    Keywords: [Concept] Overview [SI] - [Discipline] Nuclear Engineering [Topic] Conceptual Intro and Overview [Phase] Concept [Audience] College Engineer Grad High Manager Technician Ugrad
    - Overview of Concepts and Topics 20110101.pdf (264 kb)
    34. 2012-01-25---------Jump to [Top]
  34. 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)
    35. 2015-01-01---------Jump to [Top]
  35. 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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