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[SI]: 03000 Engineering Science and Technology Documents

Documents below are listed chronologically. Use the links on the left or below to filter documents by keyword. Use the links above to jump to a specific year on this page.

Number of files: 199

    1950-01-01---------Jump to [Top]
  1. Simulation Software, by Wm.J. Garland, McMaster University, 1950-01-01. Doc type: Essay.
    Summary: Major endeavours such as a CANDU nuclear power plant involves extensive engineering calculations usually performed using large simulation tools.  However, to aid in conceptual BOE (back of envelope) evaluations and for education and training exercises, simplified and focused calculations are often done.  To aid students and working professional alike, a few such small tools (primarily spreadsheets) are linked below.  Go to Topics: Modelling to see the full list.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor Steam Generators and Auxiliaries [Discipline] General Engineering Mechanical Engineering Nuclear Engineering [Topic] Basic Equations Conceptual Heat Transfer Modelling Process Systems Reactor Physics Thermalhydraulics [Phase] Concept Design Analysis [Audience] College Engineer Grad Technician Ugrad
    - SimulationSoftware.pdf (267 kb)
    2. 1969-01-02---------Jump to [Top]
  2. 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)
    3. 1972-05-25---------Jump to [Top]
  3. AECL Lectures on Nuclear Power Symposium, by G.A. Pon, AECL, 1972-05-25. 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, by G. Cowper, 19720102.pdf (1025 kb)
    - Lecture 3 - Power Reactor Types, by Gordon L. Brooks, 19720103.pdf (3378 kb)
    - Lecture 4 - Reactor Physics, by E. Critoph, 19720104.pdf (1755 kb)
    - Lecture 5 - Canadian Reactor Fuel, by R.D. Page, 19720105.pdf (3924 kb)
    - Lecture 8 - System Analysis, by D.B. Primeau, 19720108.pdf (1770 kb)
    - Lecture 9 - Reactor and Station Control, by E.M. Yaremy, 19720109.pdf (2715 kb)
    - Lecture 10 - Plant Layout, by R.B.V. Simmons, 19720110.pdf (3190 kb)
    - Lecture 11 - Accident Analysis, by J.D. Sainsbury, 19720111.pdf (1418 kb)
    - Lecture 12 - Licensing, by L. Pease, 19720112.pdf (1755 kb)
    - Lecture 13 - Training, by G.R. Howey, 19720113.pdf (1432 kb)
    - Lecture 14 - Canadian Power Reactor Fuel. See AECL 5609 doc#19760101 for an updated version., by R.D. Page, 19720114.pdf (2844 kb)
    - Lecture 15 - Construction, by V.A. Harrison, 19720115.pdf (3542 kb)
    - Lecture 16 - Costs, by D.L.S. Bate, 19720116.pdf (764 kb)
    - Lecture 17 - Development Potential, by W.B. Lewis, 19720117.pdf (1390 kb)
    - Lectures 6 and 7 - Heat Transport and Auxiliary Systems, by R.H. Renshaw, 19720167.pdf (2431 kb)
    4. 1975-07-01---------Jump to [Top]
  4. FORSIM a FORTRAN Oriented Simulation Package for the Automated Solution of Partial and Ordinary partial Differential Equation SYSTEMS, by M.B. Carver, AECL, 1975-07-01. Doc type: Report.
    Summary: FORSIM was Mike's vehicle for all the work he did in PDEs/ODEs including stiff equation solvers, reactor kinetics and mass action chemical kinetics, sparse matrix approximation to the Jacobian, integration over discontinuities, and parameter identification. In about a dozen PPV papers. FORSIM started as just an ODE simulator to replace MIMIC for the AECL Sheridan Park engineers.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries 32000 Moderator System 33000 Primary Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics Mechanical Engineering [Topic] Basic Equations Collections Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - AECL 4608, November 1973 FORSIM_AECL4608.pdf (538 kb)
    5. 1976-03-01---------Jump to [Top]
  5. Canadian Power Reactor Fuel, by R.D. Page, AECL, 1976-03-01. 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. 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. 1981-04-01---------Jump to [Top]
  9. Thermal-Hydraulics in Recirculating Steam Generators: Thirst Code User's Manual, by M.B. Carver, AECL, 1981-04-01. Doc type: Report.
    Summary: THIRST is for modeling ThermalHydraulics In Recirculating Steam generators. This manual gives complete details of the mathematical derivation and numerical solution of the 3D, 2Phase thermalhydraulic equilibrium conservation equations inside a reactor boiler and also explains the many constitutive correlations required. Finally the manual fully defines the immense amount of input detail required to model the primary side heat transfer and the secondary side water boiling and recirculating in the complex tube-in-shell geometry of a prototypical CANDU steam generator.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Fluid Mechanics Heat Transfer Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - AECL 7254, April 1981 THIRSTusersR43667.pdf (2290 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. 1987-03-01---------Jump to [Top]
  12. Nuclear Journal of Canada, 1987 Vol 1 No. 1, by B. K. Wilson, CNS-, 1987-03-01. Doc type: Paper.
    Summary: Radiation processing offers the food industry a 'new' process to control food spoilage and pathogenic organisms. The process is based on four decades of extensive research on the underlying aspects of radiation chemistry and radiobiology, concurrent with over 25 years of technical development and commercialization of radiation processing equipment. To date, many countries have approved a wide range of food irradiation applications, but commercial usc of the process is just beginning to grow significantly. This paper reviews some aspeGts of the scientific and commercial background behind this process, focusing on the microbial and chemical safety, and the nutritional issues.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Science [Topic] Radiation [Phase] - [Audience] College Engineer Grad High Manager Technician Ugrad Vendor
    - Food Irradiation: Commercial and Scientific Review NJC-1-1-04.pdf (520 kb)
    13. 1987-04-01---------Jump to [Top]
  13. Development and Application of a Three-Dimensional Two-Fluid Numerical Algorithm for Simulation of Phase Redistribution by Bends and Obstructions, by M.B. Carver, AECL, 1987-04-01. Doc type: Other.
    Summary: Mike completed his Ph.D in parallel to his full time position at AECL as branch head of Applied Mathematics at CRNL. Upon completion he was appointed adjunct professor at McMaster and was co-supervisor of two degrees.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics#Mechanical Engineering [Topic] Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Ph.D Thesis, Department of Mechanical Engineering, University of Ottawa, April 1987 ThesisNL56352.pdf (4350 kb)
    14. 1987-09-01---------Jump to [Top]
  14. Nuclear Journal of Canada, 1987 Vol 1 No. 3, by S. Banerjee, CNS-, 1987-09-01. Doc type: Paper.
    Summary: The multifield model, in which separate sets of conservation equations are written for each phase, or clearly identifiable portion of a phase, is derived and explored.
    Keywords: [Concept] Thermalhydraulics [SI] 03000 Engineering Science and Technology [Discipline] Mechanical Engineering [Topic] Basic Equations Modelling Thermalhydraulics [Phase] Design Analysis [Audience] Engineer Grad
    - Multifield Methods for Nuclear Thermalhydraulics Problems NJC-1-3-04.pdf (1030 kb)
    15. 1987-12-01---------Jump to [Top]
  15. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by Alain Hebert, CNS-, 1987-12-01. Doc type: Paper.
    Summary: A new three-dimensional neutron diffusion code named TRIVAC was set up using advanced discretization algorithms and improved iteration strategies. The two variable order discretization algorithms used in TRIVAC will be presented.
    Keywords: [Concept] Reactor Physics [SI] 03000 Engineering Science and Technology 31000 Reactor [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis Operation [Audience] Engineer Grad Ugrad
    - Trivac: A Modular Diffusion Code for Fuel Management and Design Applications NJC-1-4-06.pdf (472 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)
    16. 1993-01-01---------Jump to [Top]
  16. Fundamentals of Power Reactors, CNSC, 1993-01-01. Doc type: Course.
    Summary: Fundamentals of power reactors covering basic nuclear processes, basic thermodynamics, thermalhydraulics, materials, nuclear systems and radiation protection.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Operation [Audience] College Engineer Ugrad
    - Science & Engineering Fundamentals - Part 1 19930201.pdf (5929 kb)
    - Science & Engineering Fundamentals - Part 2, 19930202.pdf (7656 kb)
    - Nuclear Reactor System - Part 1, 19930203.pdf (6312 kb)
    - Nuclear Reactor System - Part 2, 19930204.pdf (8311 kb)
    - Nuclear Reactor System - Part 3, 19930205.pdf (3791 kb)
    - Nuclear Reactor System - Part 4, 19930206.pdf (4327 kb)
    - Radiation Protection, 19930207.pdf (5465 kb)
    17. 1993-02-01---------Jump to [Top]
  17. 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)
    18. 1995-06-25---------Jump to [Top]
  18. 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)
    19. 1995-08-01---------Jump to [Top]
  19. Numerical Solution of the Thermalhydraulic Conservation Equations from Fundamental Concepts to Multidimensional Analysis, by M.B. Carver, , 1995-08-01. Doc type: Report.
    Summary: This material was presented as part of a short course in Two-Phase Flow and Heat Transfer at McMaster University and is documented in report form for further reference. The discussion briefly establishes some requisite concepts of differential equation theory, and applies these to describe methods for numerical solution of the thennalhydraulic conservation equations in their various forms. The intent is to cover the general methodology without obscuring the principles with details. As a short overview of computational thermalhydraulics, the material provides an introductory foundation, so that those working on the application of thennalhydraulic codes can begin to understand the many intricacies involved without having to locate and read the references given. Those intending to work in code development will need to read and understand all the references.
    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 Collections Conceptual Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Grad
    - AECL-11387, ARD-TD-550, Revision 1 (2017) to the original (1995) Carver AECL-11387[3628]-WithAddendum.pdf (6457 kb)
    20. 1996-11-01---------Jump to [Top]
  20. CANDU Overiew, Course 3.2, by G. Bereznai, Chulalongkorn University, 1996-11-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Operation [Audience] College Engineer Ugrad
    - Chapter 0 - Title, Table of Contents, Objectives 20044201.pdf (89 kb)
    - Chapter 1 - Overall Unit, by G. Bereznai, 20044202.pdf (973 kb)
    - Chapter 2 - Reactor and Moderator, by G. Bereznai, 20044203.pdf (659 kb)
    - Chapter 3 - Reactor Control, by G. Bereznai, 20044204.pdf (881 kb)
    - Chapter 4 - Heat Transport, by G. Bereznai, 20044205.pdf (755 kb)
    - Chapter 5 - Steam, Turbine and Feedwater, by G. Bereznai, 20044206.pdf (666 kb)
    - Chapter 6 - Special Safety Systems, by G. Bereznai, 20044207.pdf (1131 kb)
    - Workbook, Chapter 0 - Table of Contents, Course Introduction, by G. Bereznai, 20044208.pdf (194 kb)
    - Workbook, Chapter 1 - Modules A to E, by G. Bereznai, 20044209.pdf (3559 kb)
    - Workbook, Chapter 2 - Modules A to C, by G. Bereznai, 20044210.pdf (688 kb)
    - Workbook, Chapter 3 - Modules A to C, by G. Bereznai, 20044211.pdf (2317 kb)
    - Workbook, Chapter 4 - Modules A to D, by G. Bereznai, 20044212.pdf (1115 kb)
    - Workbook, Chapter 5 - Modules A & B, by G. Bereznai, 20044213.pdf (1110 kb)
    - Workbook, Chapter 6 - Modules A to D, by G. Bereznai, 20044214.pdf (464 kb)
    21. 1997-04-01---------Jump to [Top]
  21. Software Quality Assurance: Practical Procedures to Meet CSA Standards, by M.B. Carver, CNSC, 1997-04-01. Doc type: Report.
    Summary: In the Canadian nuclear industry at the time, only the ASSERT code team and the NUCIRC team used definitive SQA (Software Quality Assurance), which identifies exactly what version of the computer code is being used for a given application, and every component used to build that version. A drive to apply such standards to all computer programs started in the 1990s, and Mike co-authored the 1995 AECL Reactor Development SQA manual. Upon his retirement, representatives of the then AECB (now CNSC) asked him to write a SQA guide for the industry that would bring all computer codes teams in line with CSA standards ( N286.7 & Q936).This report is CNSC-info-0669, 1997. To date the ASSERT-PV development team has followed these standards, the CATHENA team has not. Source attribution: Archived in the public domain at http://www.nuclearsafety.gc.ca/eng/about/past/timeline-dev/resources/documents/infohistorical/info-0669.pdf .
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Atomic Energy Control Board, Report INFO-0699, April 1997, http://www.nuclearsafety.gc.ca info-0669.pdf (3262 kb)
    22. 1998-09-22---------Jump to [Top]
  22. 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, 1998-09-22. 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, by D.A. Meneley and Y.Q. Ruan, 19980102.pdf (2650 kb)
    - Moderator, HTS, Heavy Water, by D.A. Meneley and Y.Q. Ruan, 19980103.pdf (2454 kb)
    - Main Steam & T/G Systems, by D.A. Meneley and Y.Q. Ruan, 19980104.pdf (2626 kb)
    - Special Safety Systems, by D.A. Meneley and Y.Q. Ruan, 19980105.pdf (949 kb)
    - CANDU Reactor Control, by D.A. Meneley and Y.Q. Ruan, 19980106.pdf (1038 kb)
    23. 1999-10-01---------Jump to [Top]
  23. 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)
    24. 2000-12-01---------Jump to [Top]
  24. 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)
    25. 2001-01-01---------Jump to [Top]
  25. CANDU Poster, AECL, 2001-01-01. Doc type: Presentation.
    Summary: Handy overview poster showing the major components and concepts of CANDU.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Operation [Audience] High
    - 20010501.pdf (945 kb)
    26. 2001-01-02---------Jump to [Top]
  26. CANDU - How a Reactor Works, AECL, 2001-01-02. Doc type: Presentation.
    Summary: A handy overview poster showing how a CANDU reactor works.
    Keywords: [Concept] Overview [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Operation [Audience] High
    - 20010601.pdf (578 kb)
    27. 2001-02-01---------Jump to [Top]
  27. 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)
    28. 2002-01-01---------Jump to [Top]
  28. Heavy Water Reactors: Status and Projected Development, Technical Report Series No. 407, IAEA, Vienna, Austria, 2002., IAEA, 2002-01-01. 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
    - Table of Contents. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp. D407_cont.pdf (54 kb)
    - Part 1. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp., D407_scr1.pdf (4200 kb)
    - Part 2. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp., D407_scr2.pdf (3619 kb)
    - Part 3. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp., D407_scr3.pdf (1384 kb)
    - Cover Page. Published on IEAE web site at http://www-pub.iaea.org/MTCD/publications/publications.asp., D407_start.pdf (53 kb)
    29. 2002-09-25---------Jump to [Top]
  29. ACR Presentation given to the US Nuclear Regulatory Commission on September 25-26, 2002, AECL, 2002-09-25. Doc type: Presentation.
    Summary: Presentation given by AECL to the US Nuclear Regulatory Commission on September 25-26, 2002
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Concept Design Licensing Safety [Audience] College Engineer Ugrad
    - Introduction. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html) 20031201.pdf (1939 kb)
    - An Overview of the ACR Design. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031202.pdf (7935 kb)
    - ACR Technology Base. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031203.pdf (19271 kb)
    - ACR Reactor and Fuel Handling. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031204.pdf (12607 kb)
    - Core Design & Reactor Physics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031205.pdf (957 kb)
    - Reactor Coolant System, Moderator and Major Auxiliary Systems. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031206.pdf (17255 kb)
    - ACR Safety Support Systems Safety Assessment. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031207.pdf (583 kb)
    - ACR Technology Base: Reactor Physics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031208.pdf (1490 kb)
    - ACR Technology Base: Fuel. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031209.pdf (2924 kb)
    - ACR Technology Base: RCS Thermalhydraulics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031210.pdf (3081 kb)
    - ACR Technology Base: Fuel Channels. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031211.pdf (1817 kb)
    - ACR Technology Base: Fuel Channel Thermalhydraulics. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031212.pdf (1444 kb)
    - ACR Moderator Circulation. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031213.pdf (2038 kb)
    - ACR Technology Base: Containment. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031214.pdf (792 kb)
    - Qualification Process for Safety Analysis Computer Codes. (http://www.nrc.gov/reactors/new-licensing/license-reviews/acr-700.html), 20031215.pdf (493 kb)
    30. 2003-02-01---------Jump to [Top]
  30. 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)
    - , by Ken Petrunik, 20031901.pdf (513 kb)
    31. 2003-05-01---------Jump to [Top]
  31. Chemistry Control Requirements for Generic CANDU Power Stations, by Stu Groom, NB Power, 2003-05-01. Doc type: Presentation.
    Summary: A series of presentations by Stu Groom to the Karachi Nuclear Power Plant (KANUPP) in May 2003 as a part of an IAEA 5-day training program to review the chemistry control requirements of the Karachi Nuclear Power Plant.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Construction [Audience] College Engineer Ugrad
    - Basic Chemistry Concepts 20032101.pdf (833 kb)
    - Moderator System Chemistry Control, by Stu Groom, 20032102.pdf (264 kb)
    - Annulus Gas System Chemistry Control, by Stu Groom, 20032103.pdf (362 kb)
    - Primary Heat Transport System Chemistry Control, by Stu Groom, 20032104.pdf (667 kb)
    - Feeder Thinning, by Stu Groom, 20032105.pdf (600 kb)
    - Boiler Feedwater / Condensate Chemistry Control, by Stu Groom, 20032106.pdf (605 kb)
    - Steam Generator Chemistry Control, by Stu Groom, 20032107.pdf (430 kb)
    - ECC and Dousing Systems Chemistry Control, by Stu Groom, 20032108.pdf (116 kb)
    - Spent Fuel Bay Chemistry Control, by Stu Groom, 20032109.pdf (85 kb)
    - Plant Chemistry Controm - PLGS Manual, by Stu Groom, 20032110.pdf (4826 kb)
    - PHT System Chemitry Monitoring and Control Improvements, by Stu Groom, 20032111.pdf (753 kb)
    - Chemistry Laboratory Analytical Procedure – Gadolinium Arsenazo III, by Stu Groom, 20032112.pdf (175 kb)
    - Chemistry Specifications, by Stu Groom, 20032113.pdf (119 kb)
    32. 2003-06-01---------Jump to [Top]
  32. Qinshan Project, by Ken Petrunik, AECL, 2003-06-01. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] General Engineering [Topic] Intro and Overview [Phase] Construction [Audience] College Engineer Ugrad
    - CNS 2003 Conference Paper 20031801.pdf (3687 kb)
    33. 2003-06-24---------Jump to [Top]
  33. CANDU Fundamentals, CNSC, 2003-06-24. Doc type: Course.
    Summary: Fundamentals of reactor processes of the CANDU reactor.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Complete Course 20040700.pdf (6375 kb)
    - Objectives, 20040701.pdf (422 kb)
    - Atomic Structure, 20040702.pdf (257 kb)
    - Radioactivity - Spontaneous Nuclear Processes, 20040703.pdf (372 kb)
    - Nuclear Stability And Instability, 20040704.pdf (264 kb)
    - Activity and Half-Life, 20040705.pdf (271 kb)
    - Neutrons and Neutron Interactions, 20040706.pdf (296 kb)
    - Fission, 20040707.pdf (488 kb)
    - Fuel, Moderator, and Reactor Management, 20040708.pdf (231 kb)
    - Nuclear Safety, 20040709.pdf (182 kb)
    - Nuclear Power Reactors, 20040710.pdf (205 kb)
    - Candu Reactor Construction, 20040711.pdf (653 kb)
    - Moderator and Moderator System, 20040712.pdf (196 kb)
    - Moderator Auxiliary Systems, 20040713.pdf (253 kb)
    - Heat Transport System (HTS), 20040714.pdf (410 kb)
    - Heat Transport Auxiliary Systems, 20040715.pdf (372 kb)
    - Reactor Fuel, 20040716.pdf (503 kb)
    - Neutron Life Cycle, 20040717.pdf (221 kb)
    - Criticality and Neutron Multiplication, 20040718.pdf (297 kb)
    - Changes In Reactor Power With Time, 20040719.pdf (236 kb)
    - Xenon: A Fission Product Poison, 20040720.pdf (287 kb)
    - Reactivity Effects of Temperature Changes, 20040721.pdf (268 kb)
    - Neutron Flux Control, 20040722.pdf (311 kb)
    - Reactivity Mechanisms, 20040723.pdf (538 kb)
    - Emergency Coolant Injection & Containment, 20040724.pdf (795 kb)
    - The Conventional Side of the Station, 20040725.pdf (1049 kb)
    - Other Major Systems, 20040726.pdf (665 kb)
    - Radioactivity - Spontaneous Nuclear Processes, 20040727.pdf (539 kb)
    - Nuclear Stability And Instability, 20040728.pdf (1360 kb)
    - Activity and Half-Life, 20040729.pdf (120 kb)
    - Neutrons and Neutron Interactions, 20040730.pdf (163 kb)
    - Fission, 20040731.pdf (3750 kb)
    - Fuel, Moderator, and Reactor Management, 20040732.pdf (937 kb)
    - Nuclear Safety, 20040733.pdf (465 kb)
    - Nuclear Power Reactors, 20040734.pdf (693 kb)
    - CANDU Reactor Construction, 20040735.pdf (1259 kb)
    - Moderator System, 20040736.pdf (731 kb)
    - Heat Transport System, 20040737.pdf (1053 kb)
    - Fuel and Fuelling, 20040738.pdf (2226 kb)
    - Neutron Life Cycle, 20040739.pdf (151 kb)
    - Criticality and Neutron Multiplication, 20040740.pdf (709 kb)
    - Changes in Reactor Power with time, 20040741.pdf (2744 kb)
    - Neutron Flux Control, 20040742.pdf (157 kb)
    - Reactivity Mechanisms, 20040743.pdf (1894 kb)
    - Emergency Coolant Injection & Containment, 20040744.pdf (1024 kb)
    - The Conventional Side of the Station, 20040745.pdf (1535 kb)
    - Other Major Systems, 20040746.pdf (2581 kb)
  34. Principes Fondamentaux des Réacteurs CANDU - CANDU Fundamentals, CNSC, 2003-06-24. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Operation [Audience] College Engineer Ugrad
    - Texte Complet 20060300.pdf (7093 kb)
    - Table des Matières, 20060301.pdf (102 kb)
    - Chapitre 1 - Objectifs, 20060302.pdf (105 kb)
    - Chapitre 2 - Structure de l’Atome, 20060303.pdf (156 kb)
    - Chapitre 3 - Radioactivité - Phénomènes Nucléaires Spontanés, 20060304.pdf (296 kb)
    - Chapitre 4 - Stabilité et Instabilité Nucléaires, 20060305.pdf (198 kb)
    - Chapitre 5 - Activité et Période, 20060306.pdf (177 kb)
    - Chapitre 6 - Les Neutrons et Leurs Interactions, 20060307.pdf (206 kb)
    - Chapitre 7 - La Fission, 20060308.pdf (382 kb)
    - Chapitre 8 - Combustible, Modérateur et Gestion du Réacteur, 20060309.pdf (156 kb)
    - Chapitre 9 - Sûreté Nucléaire, 20060310.pdf (141 kb)
    - Chapitre 10 - Réacteurs de Puissance, 20060311.pdf (157 kb)
    - Chapitre 11 - Structure d’un Réacteur, 20060312.pdf (820 kb)
    - Chapitre 12 - Modérateur et Circuit du Modérateur, 20060313.pdf (125 kb)
    - Chapitre 13 - Circuits Auxiliaires du Modérateur, 20060314.pdf (250 kb)
    - Chapitre 14 - Circuit Caloporteur (CC), 20060315.pdf (356 kb)
    - Chapitre 15 - Systèmes Auxiliaires du Circuit Caloporteur, 20060316.pdf (321 kb)
    - Chapitre 16 - Le Combustible CANDU, 20060317.pdf (575 kb)
    - Chapitre 17 - Cycle de Vie des Neutrons, 20060318.pdf (126 kb)
    - Chapitre 18 - Criticité et Multiplication de Neutrons, 20060319.pdf (189 kb)
    - Chapitre 19 - Changements dans la Puissance du Réacteur au Fil du Temps, 20060320.pdf (149 kb)
    - Chapitre 20 - Un Produit de Fission Agissant Comme Poison : le Xénon, 20060321.pdf (211 kb)
    - Chapitre 21 - Effets des Changements de Température sur la Réactivité, 20060322.pdf (197 kb)
    - Chapitre 22 - Contrôle du Flux de Neutron, 20060323.pdf (267 kb)
    - Chapitre 23 - Mécanismes de Contrôle de la Réactivité, 20060324.pdf (461 kb)
    - Chapitre 24 - Injection d’Urgence de Caloporteur et Confinement, 20060325.pdf (969 kb)
    - Chapitre 25 - Les Parties Non Nucléaires de la Centrale, 20060326.pdf (1176 kb)
    - Chapitre 26 - Autres Grands Systèmes, 20060327.pdf (752 kb)
    35. 2005-07-01---------Jump to [Top]
  35. Nuclear Power Plant Systems and Operation, by G. Bereznai, University of Ontario Institute of Technology, 2005-07-01. Doc type: Reference.
    Summary: Nuclear Power Plant Systems and Operation course covering following: science fundamentals, equipment and systems principles relevant to CANDU reactors; CANDU reactor power plant systems and their operation.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries [Discipline] Nuclear Engineering [Topic] Conceptual Function Intro and Overview Process Systems Transient [Phase] Operation [Audience] College Engineer Ugrad
    - 20071000.pdf (2511 kb)
    36. 2010-01-01---------Jump to [Top]
  36. ACR-1000 Technical Description Summary, AECL, 2010-01-01. 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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