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[DocType]: Paper 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: 102

    1956-01-01---------Jump to [Top]
  1. The Pressurized Water Reactor as a Source of Heat for Steam Power Plants, by J.M. Kay and F.J. Hutchinson, IMechE, 1956-01-01. Doc type: Paper.
    Summary: Published in the Proceedings of the Institution of Mechanical Engineers Volume 170 1956 pps 281 - 297
    Keywords: [Concept] - [SI] 09000 Special Studies [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Conceptual Heat Transfer Thermodynamics [Phase] Concept Design Operation [Audience] Engineer Ugrad Vendor
    - Published in the Proceedings of the Institution of Mechanical Engineers Volume 170 1956 pps 281 - 296 20054600.pdf (2333 kb)
    2. 1962-09-01---------Jump to [Top]
  2. Reactor Loops at Chalk River, by Ronald Needham, AECL, 1962-09-01. Doc type: Paper.
    Summary: Description of the Chalk River NRX and NRU in-reactor test loops for materials testing under simulated reactor power conditions.
    Keywords: [Concept] - [SI] 03300 Nuclear Engineering [Discipline] Materials Engineering Nuclear Engineering [Topic] Radiation Reactor Physics Thermalhydraulics [Phase] Concept [Audience] Engineer Technician Ugrad
    - CRL-Loops1962.pdf (1547 kb)
  3. NDP Startup Trouble Spots, OPG, 1962-09-01. Doc type: Paper.
    Summary: Short report on the main trouble spots in NPD startup.
    Keywords: [Concept] Generic Design Issues [SI] 90000 Operations and Commissioning [Discipline] General Engineering [Topic] Performance [Phase] Commissioning [Audience] Engineer Manager Technician
    - Pumps, instrument tubing main trouble spots NDP-Startup1962.pdf (92 kb)
    4. 1969-01-02---------Jump to [Top]
  4. The Effect of Bypass Characteristics on Parallel Channel Flow Instabilities, by M.B. Carver, AECL, 1969-01-02. Doc type: Paper.
    Summary: This article is definitive because nobody could figure out why all the instability codes gave stability thresholds well below the measured threshold power in the experiments done at Canadian Westinghouse. The paper determines analytically that this is because the small bypass stabilized the experimental system as it could not maintain a constant pressure drop, which all the codes assumed at step 1.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics Mechanical Engineering [Topic] Basic Equations Collections Conceptual Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Proceedings of the Institution of Mechanical Engineers, Volume 184, 1969 BYPASS PIME_CONF_1969_184_083_02.pdf (703 kb)
    5. 1970-03-09---------Jump to [Top]
  5. Nuclear Heated Steam Generators, by D. J. Stelliga and J.M. Dyke, Babcock & Wilcox Canada, 1970-03-09. Doc type: Paper.
    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
    - Presented to the Canadian Electrical Association, Toronto, Ontario, March 9-12, 1970 20053900.pdf (928 kb)
    6. 1978-01-01---------Jump to [Top]
  6. Efficient Integration over Discontinuities in Ordinary Differential Equation Simulation, by M.B. Carver, AECL, 1978-01-01. Doc type: Paper.
    Summary: Efficient integration algorithms for ordinary differential equations take integration steps that are as large as the error control criteria permit. Events or discontinuities in equation definition are often implicitly defined to occur when a variable reaches a critical value, for example a fuel rod surface reaching saturation temperature, and this requires the integrator to basically restart the calculation precisely at the point of change. Instead integrators will "hunt" for the discontinuity wasting a lot of computer time, and will eventually "step over" the discontinuity using integration points either side of the event. This paper shows that if the discontinuity is defined and monitored as an additional part of the equation set, such a restart can be optimized, thus ensuring that the event will be defined as an integration restart point.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Mathematics and Computers in Simulation, XX, 1978 efficient-integration-over-discontinuities-in-ordinary-differential-equation.pdf (467 kb)
    7. 1978-08-01---------Jump to [Top]
  7. The method of lines and the advective equation, by M.B. Carver and H.W. Hinds, AECL, 1978-08-01. Doc type: Paper.
    Summary: This article showed that the common approach of first order differencing, used in almost all thermalhydraulic computer programs, would not properly solve the simplest hyperbolic PDE on the market. Despite the errata, it is Carver's most cited publication and laid the foundations for many higher order analyses by others, and Carver's pseudo-characteristic method of lines (PCMOL) solution of the thermalhydraulic conservation equations.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Basic Equations Modelling Process Systems Thermalhydraulics [Phase] Concept Design Analysis Safety Analysis [Audience] Engineer Grad
    - Simulation, August,1978. Also published as AECL 6155 AdvectiveEqn.pdf (804 kb)
    8. 1980-01-01---------Jump to [Top]
  8. Pseudo-characteristic method of lines solution of first-order hyperbolic equation systems, by M.B. Carver, AECL, 1980-01-01. Doc type: Paper.
    Summary: This paper introduced a new concept, pseudo-characteristics, which allows the directionality dictated by the method of characteristics to be applied on a fixed grid basis. This is the method that N.P. Kolev Nuclear Institute of Bulgaria and M. B. Carver used to apply to the EVUT form of the thermalhydraulic conservation equations at the OECD/CSNI conference on two phase flow, Pasedena, 1981. In this MACS paper, discretization of the PDEs is discussed, using higher order upwind biased derivatives of each of the Lagrange polynomials and the Hermite polynomials. Results are shown for incompressible flow in a hydraulic jump and for compressible flow in the EVET thermalhydraulic conservation equations.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Mathematics and Computers in Simulation, 22, 1980 pseudo-characteristic-method-of-lines-solution-of-first-order-hyperbolic-equation.pdf (455 kb)
    9. 1981-01-01---------Jump to [Top]
  9. Memories of my Life as a Professional Engineer in the Royal Navy and the Canadian Boiler Industry, by J.M. Dyke, Individual Contributions, 1981-01-01. Doc type: Paper.
    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
    - Fran Gregory, Ed 20054000.pdf (2139 kb)
    10. 1982-01-01---------Jump to [Top]
  10. A Method of Limiting Intermediate Volume Fraction in Iterative Two-Fluid Computations, by M.B. Carver, AECL, 1982-01-01. Doc type: Paper.
    Summary: This is seminal and the core contribution in Carver's thesis. The ICE guys, Harlow & Amsden and the IPSA guys, Spalding & Patankar had not got it quite right for air/water conditions where the water totally dominates the pressure field calculation when it is based on mass flux balance, as this is dominated by the water component and neglects continuity of the air. Herein, a volumetric balance fixes that and the calculation also converges better with the constraint mentioned in the title.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Journal of Mechanical Engineering Science, Vol. 24, No. 2, 1982 limiting_volume_fraction_JMES_JOUR_1982.pdf (374 kb)
    11. 1984-12-01---------Jump to [Top]
  11. Two Dimensional Modelling of the Homogenizing Effects of Flow Obstructions in Two Fluid Flow, by M.B. Carver and M. E. Salcudean, AECL, 1984-12-01. Doc type: Paper.
    Summary: It is well known that obstructions in two fluid flow have the effect of homogenizing the two fluid mixture, resulting not only in a more uniform phase distribution, but also in a significant reduction of the ratio of fluid velocities. This paper describes a 2D, 2Fluid computer program written by the first author to do proof of principal studies of 2fluid redistribution around bends and past obstacles. The details necessary for modelling air/water flows in these geometries have been introduced here before extending the work to 3D. The paper shows that these phase redistribution effects can be modelled using the two fluid computer program, and compares results to those obtained in a recent experiment on flow past obstructions.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Mathematics and Computers in Simulation 26(6):pp 475–484, December 1984 two-dimensional-modelling-of-the-homogenizing-effects-of-flow-obstructions.pdf (1202 kb)
    12. 1986-01-01---------Jump to [Top]
  12. 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)
    13. 1987-03-01---------Jump to [Top]
  13. 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, by G.R. Howey, P.A. Ross-Ross and I.S. Hewitt, 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], by O.K. Myers and M.M. Werner, NJC-1-1-03.pdf (729 kb)
    - Food Irradiation: Commercial and Scientific Review, by B. K. Wilson, NJC-1-1-04.pdf (520 kb)
    - Technetium-iron Oxide Reactions Under Anaerobic Conditions: A Fourier Transform Infrared, FTIR Study, by R.I. Haines, D.G. Owen and T. T. Vandergraaf, NJC-1-1-05.pdf (357 kb)
    - Progress of the Swedish Radioactive Waste Management Program, by Hans G. Forsstrom, NJC-1-1-06.pdf (1534 kb)
    - A Non-Intrusive Neutron Method for Poison Concentration Monitoring in CANDU Reactors, by E.M.A. Hussein, D.R. OConnor and M.E. Mosher, NJC-1-1-07.pdf (427 kb)
    - Containment Systems Capability, by W.G. Morison, W. J. Penn, K. Hassmann, J.D. Stevenson, K. Elisson, NJC-1-1-08.pdf (1131 kb)
    - Chemistry Control at Bruce NGS 'B' from Construction to Commercial Operation, by J.G. Roberts, NJC-1-1-09.pdf (382 kb)
    - Gestion du cycle de combustible a la Centrale Nucleaire Gentilly-2, by G. Hotte, G. Parent, L. Cloutier, A. Aubin and N. Macici, NJC-1-1-10.pdf (762 kb)
    - Summaries of CNS Conferences, Seminars and Workshops., NJC-1-1-11.pdf (625 kb)
    14. 1987-06-01---------Jump to [Top]
  14. 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, by J.L. Gray, NJC-1-2-02.pdf (719 kb)
    - Insights from Chernobyl on Severe Accident Assessment of CANDU Reactors, by J.T. Rogers, NJC-1-2-03.pdf (829 kb)
    - Whole-Body Retention of99mTc-imidodiphosphate: A Measurement of Total Body Bone Turnover Rate, by C.L. Schultz, J.G. Roberts, C.E. Webber, C.A. Woolever and J.D. Adachi, NJC-1-2-04.pdf (250 kb)
    - Corrosion of Heat Exchanger Materials under Heat Transfer Conditions, by R.L. Tapping, P.A. Lavoie, and D.J. Disney, NJC-1-2-05.pdf (418 kb)
    - Concentration Processes under Tubesheet Sludge Piles in Nuclear Steam Generators, by F. Gonzalez and P. Spekkens, NJC-1-2-06.pdf (937 kb)
    - Simulation Methodology for Pressure Tube Integrity Analysis and Comparison with Experiments, by G.H. Archinoff, J.e. Luxat, P.O. Lowe, K.E. Locke and A.P. Muzumdar, NJC-1-2-07.pdf (575 kb)
    - The Drift Flux Model in the ASSERTSubchannel Code, by M.B. Carver, R.A. Judd, J.E. Kiteley, and A. Tahir, NJC-1-2-08.pdf (742 kb)
    - A Review of Low-Level Radioactive Waste Management Technology in the Canadian Nuclear Industry, by T.J. Carter and P.K.M. Rao, NJC-1-2-09.pdf (514 kb)
    - Characterization of Radioactive Wastes Incorporated in a Cement Matrix, by E.R. Merz, D. Dyckerhoff and R. Odoj, NJC-1-2-10.pdf (501 kb)
    - Spent Fuel Storage and Transportation Experience for the Idaho National Engineering Laboratory, by C.P. Gertz, D.H. Schoonen and B.H. Wakeman, NJC-1-2-11.pdf (702 kb)
    - Summaries of CNS Conferences, Seminars and Workshops., NJC-1-2-12.pdf (474 kb)
    15. 1987-09-01---------Jump to [Top]
  15. 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, by J.Q. Howieson and V.G. Snell, NJC-1-3-02.pdf (1766 kb)
    - Seismic Qualification of CANDU-PHW Nuclear Power Plant Equipment, by S.A. Usmani, NJC-1-3-03.pdf (660 kb)
    - Multifield Methods for Nuclear Thermalhydraulics Problems, by S. Banerjee, NJC-1-3-04.pdf (1030 kb)
    - CATHENA Simulation of Thermosiphoning in a Pressurized-Water Test Facility, by J.P. Mallory and P.J. Ingham, NJC-1-3-05.pdf (615 kb)
    - Use of Quantitative Indicators of Nuclear Safety in Ontario Hydro, by R.T. Popple and S.B. Harvey, NJC-1-3-06.pdf (416 kb)
    - Safe, Permanent Disposal of Nuclear Fuel Waste, by W.T. Hancox, 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, by J.W. Cashwell, K.S. Neuhauser, P.C. Reardon and G.W. McNair, NJC-1-3-08.pdf (491 kb)
    - Book Review: Fallout from Chernobyl by L. Ray Silver, by A.N. Sinclair, NJC-1-3-09.pdf (104 kb)
    - CNS Conferences, Seminars, NJC-1-3-10.pdf (185 kb)
    16. 1987-12-01---------Jump to [Top]
  16. 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, by L.L. Bennett, NJC-1-4-02.pdf (499 kb)
    - Sea Dumping of Radioactive Wastes, by J.M. Bewers, NJC-1-4-03.pdf (1065 kb)
    - The Effect of Steam Generator Tube Temperature on the Stress Corrosion Cracking of Alloy 600, by F.P. Vaccaro, G.J. Theus and B.P. Miglin, NJC-1-4-04.pdf (663 kb)
    - Suitability Study of On-Line Leak Tests for CANDU Single-Unit Containment Buildings, by J.F. Lafortune, C.A. McDevitt and S. Poolpol, NJC-1-4-05.pdf (846 kb)
    - Trivac: A Modular Diffusion Code for Fuel Management and Design Applications, by Alain Hebert, NJC-1-4-06.pdf (472 kb)
    - Fuel for Thought, by J.A.L. Robertson, NJC-1-4-07.pdf (876 kb)
    - Fusion Materials Issues, by P.c. Stangeby and A.A. Haasz, NJC-1-4-08.pdf (916 kb)
    - The AC Device for Repositioning of Garter Springs in CANDU Reactors, by Matija Cenanovic and Hugo Maureira, NJC-1-4-09.pdf (696 kb)
    - Waterlancing for CANDU Steam Generators, by W.G. Schneider, NJC-1-4-10.pdf (370 kb)
    - Locating Gas Pipelines with Radioactive Sources, by Lubomir Zikovsky and Mostafa Yagoubi, NJC-1-4-11.pdf (145 kb)
    - Optimization of Darlington Tritium Removal Facility Performance: Effects of Key Process Variables, by A. Busigin and S. K. Sood, 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.), by E. Siddall, 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, by Alan Wyatt, David Mosey, NJC-1-4-14.pdf (168 kb)
    - CNS Conferences, Seminars, NJC-1-4-15.pdf (269 kb)
    17. 1989-05-01---------Jump to [Top]
  17. 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)
    18. 1993-02-01---------Jump to [Top]
  18. A Short History of the CANDU Nuclear Power System, by Gordon L. Brooks, AECL, 1993-02-01. 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)
    19. 1995-06-25---------Jump to [Top]
  19. 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)
    20. 1995-07-01---------Jump to [Top]
  20. 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)
    21. 1995-09-11---------Jump to [Top]
  21. Synergistic Nuclear Fuel Cycles of the Future, by D.A. Meneley, A.R. Dastur, P.J. Fehrenbach and K.H. Talbot, AECL, 1995-09-11. 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)
    22. 1999-10-01---------Jump to [Top]
  22. China Journal of Nuclear Power Engineering, 1999 Vol 20 No. 6, by Xu Jijun and K.R. Hedges, AECL, 1999-10-01. 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, by Zhang Yanfa and B.A. Shalaby, 20054402.pdf (3387 kb)
    - Paper 03 - Reactor Core Structure of Qinshan Phase III CANDU Nuclear Power Plant, by Qiu Suizheng and Norman C. Johnston, 20054403.pdf (1893 kb)
    - Paper 04 - Moderator, Heat Transport, and Steam Systems of Qinshan Phase III Nuclear Power Plant, by Gong Hongqi and R.S. Hart, 20054404.pdf (353 kb)
    - Paper 05 - Fuel Handling System for Qinshan Phase III Nuclear Power Plant, by Lin Chuanqing and D.C. Hancock, 20054405.pdf (649 kb)
    - Paper 06 - Control System of Qinshan Phase III Nuclear Power Plant, by Zhang Jianmin and R.A. Olmstead, by Jianmin Zhang 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, by Ji Yan, Jin Wanggui, He Ping and Surya Varanasi, 20054407.pdf (2543 kb)
    - Paper 08 - Safety Systems and Safety Analysis of Qinshan Phase III Nuclear Power Plant, by Cai Jianping, Shen Sen and Nick Barkman, 20054408.pdf (197 kb)
    - Paper 09 - Design and Performance of Fuel for Qinshan Phase III Nuclear Power Plant, by Song Wenhui and A.M. Manzer, 20054409.pdf (168 kb)
    - Paper 10 - Computer-Aided Engineering for Qinshan CANDU Projects, by Huang Zhizhang and David Goland, 20054410.pdf (366 kb)
    - Paper 11 - Fuel Management of CANDU Reactors, by Shao-hong Zhang and and B. Rouben, 20054411.pdf (252 kb)
    - Paper 12 - Physics Codes and Methods for CANDU Reactors, by Zhu XingGuan, Cai Jianping and H.C. Chow, 20054412.pdf (240 kb)
    - Paper 13 - Thermalhydraulic Design Methods and Computer Codes for CANDU Reactors, by Xu Jijun, V.S. Krishnan, P.J. Ingham, B.N. Hanna and J.R. Buell, 20054413.pdf (577 kb)
    - Paper 14 - Operational Characteristics and Management of the Qinshan Phase III CANDU Nuclear Power Plant, by Zhu Jizhou, Shan Jianqiang and Dennis McQuade, 20054414.pdf (201 kb)
    - Paper 15 - Advanced CANDU Fuel Cycle Vision, by Xie Zhonsheng and P.G. Boczar, 20054415.pdf (80 kb)
    - Paper 16 - A Brief Introduction to CANDU9 – A New Generation of Pressurized Heavy Water Reactors, by Zhang Zhenhua and K.R. Hedges, 20054416.pdf (189 kb)
    23. 2000-12-01---------Jump to [Top]
  23. How and Why is CANDU designed the way it is, by Wm.J. Garland, CANTEACH, 2000-12-01. 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)
    24. 2001-02-01---------Jump to [Top]
  24. CANDU Origins and Evolution, by Gordon L. Brooks and John S. Foster, AECL, 2001-02-01. 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, by Gordon L. Brooks, 20010302.pdf (99 kb)
    - Figure of 8, by Gordon L. Brooks, 20010303.pdf (111 kb)
    - Emergency Core Cooling System, by Gordon L. Brooks, 20010304.pdf (107 kb)
    - The Origin and Evolution of the Second Shutdown System, by Gordon L. Brooks, 20010305.pdf (101 kb)
    25. 2001-07-20---------Jump to [Top]
  25. Starting Up a CANDU Reactor, by D.A. Meneley, AECL, 2001-07-20. 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)
    26. 2002-05-01---------Jump to [Top]
  26. Testing the Dynamics of Shutdown Systems, by Oszvald Glockler, OPG, 2002-05-01. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Electrical Engineering [Topic] Performance [Phase] Commissioning Operation [Audience] Engineer Technician
    - Instrumentation in Reactor Trip Measurements 20030501.pdf (153 kb)
  27. Reactor Noise Measurements in the Safety and Regulating Systems of CANDU Stations, by Oszvald Glockler, OPG, 2002-05-01. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Electrical Engineering [Topic] Performance [Phase] Commissioning Operation [Audience] Engineer Technician
    - 20030601.pdf (242 kb)
    28. 2003-02-01---------Jump to [Top]
  28. What is RTD, RdF Corporation, 2003-02-01. Doc type: Paper.
    Summary:
    Keywords: [Concept] - [SI] 60000 Instrumentation and Control [Discipline] Electrical Engineering [Topic] Function Physical Description [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - 20030701.pdf (198 kb)
  29. 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, 2003-02-01. 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)
    30. 2003-04-20---------Jump to [Top]
  30. Fretting in Nuclear Steam Generators - A New Approach, by J.M. Dyke, Individual Contributions, 2003-04-20. Doc type: Paper.
    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
    - 11th International Conference on Nuclear Engineering, Tokyo, Japan 20054500.pdf (2821 kb)
    31. 2003-05-01---------Jump to [Top]
  31. Construction of CANDU® in China. A China–Canada Success Story, by Ken Petrunik, AECL, 2003-05-01. 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
    - 20031901.pdf (513 kb)
    32. 2003-05-10---------Jump to [Top]
  32. Preserving CANDU Technical Knowledge – The CANTEACH Project, by Wm.J. Garland, Yulia Kosarenko, Malcolm Lightfoot, D.A. 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)
  33. Preservation and Dissemination of CANDU® Technical Knowledge (The CANTEACH Project), by Wm.J. Garland, Yulia Kosarenko, Malcolm Lightfoot, D.A. 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)
    34. 2004-04-20---------Jump to [Top]
  34. The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators, by J.M. Dyke, Individual Contributions, 2004-04-20. Doc type: Paper.
    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
    - 12th International Conference on Nuclear Engineering, Washington, DC 20054201.pdf (1714 kb)
    35. 2006-03-01---------Jump to [Top]
  35. Fretting Failures in Early Canadian Nuclear Steam Generators, by J.M. Dyke and Wm.J. Garland, CANTEACH, 2006-03-01. Doc type: Paper.
    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
    - 20060201.pdf (140 kb)
    36. 2006-04-01---------Jump to [Top]
  36. Evolution of CANDU Steam Generators – A Historical View, by J.M. Dyke and Wm.J. Garland, CANTEACH, 2006-04-01. Doc type: Paper.
    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
    - 20060101.pdf (702 kb)
    37. 2009-05-30---------Jump to [Top]
  37. 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)
  38. 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)
    39. 2010-03-01---------Jump to [Top]
  39. Why Ontario Generates So Much Electricity from Nuclear Energy, by Lorne G. McConnell, CNA, 2010-03-01. Doc type: Paper.
    Summary: This historical review provides an excellent summary of the context in which CANDU was conceived, designed, built, commissioned and operated. The origins of some of the major characteristic features of CANDU are also given. Note: Figure G3 herein is a corrected version of the original published version which contained a scale error.
    Keywords: [Concept] - [SI] 00000 General Project [Discipline] History [Topic] Intro and Overview [Phase] Commissioning Concept Construction Design Operation [Audience] College
    - 20100500.pdf (5844 kb)
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