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[Phase]: Safety Analysis 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: 35

    1969-01-02---------Jump to [Top]
  1. 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)
    2. 1971-03-01---------Jump to [Top]
  2. 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)
    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. 1978-01-01---------Jump to [Top]
  5. 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)
    6. 1978-08-01---------Jump to [Top]
  6. 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)
    7. 1980-01-01---------Jump to [Top]
  7. 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)
    8. 1981-04-01---------Jump to [Top]
  8. 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)
    9. 1982-01-01---------Jump to [Top]
  9. 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)
    10. 1984-12-01---------Jump to [Top]
  10. 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)
    11. 1987-04-01---------Jump to [Top]
  11. 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)
    12. 1987-06-01---------Jump to [Top]
  12. Nuclear Journal of Canada, 1987 Vol 1 No. 2, by G.H. Archinoff, J.e. Luxat, P.O. Lowe, K.E. Locke and A.P. Muzumdar, CNS-, 1987-06-01. Doc type: Paper.
    Summary: The computer code SMARTT (Simulation Method for Azimuthal and Radial Temperature Transients) is used in safety analysis of Ontario Hydro's CANDU reactors to predict fuel and pressure tube thermal and mechanical behaviour under asymmetric coolant conditions, such as stratified flow. This paper presents comparisons of SMARTT predictions, with preliminary results of two experiments in which large temperature nonuniformities developed on pressure tubes undergoing heatup and transverse strain at 1.0 MPa internal pressure.
    Keywords: [Concept] Materials [SI] 33100 Main Heat Transport System [Discipline] Materials Engineering [Topic] Performance [Phase] Operation Safety Analysis [Audience] Engineer Grad Ugrad
    - Simulation Methodology for Pressure Tube Integrity Analysis and Comparison with Experiments NJC-1-2-07.pdf (575 kb)
    13. 1987-09-01---------Jump to [Top]
  13. Nuclear Journal of Canada, 1987 Vol 1 No. 3, by J.P. Mallory and P.J. Ingham, CNS-, 1987-09-01. Doc type: Paper.
    Summary: Under some postulated accident conditions, decay heat is removed from a reactor core by 2-phase natural circulation or 'thermosiphoning' of the primary coolant. To assess the ability of the computer code CATHENA to predict such events, simulations were performed of thermosiphoning tests conducted in the RD-14 facility at the Whiteshell Nuclear Research Establishment.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety Thermalhydraulics [Phase] Safety Analysis [Audience] College Engineer Grad Technician Ugrad
    - CATHENA Simulation of Thermosiphoning in a Pressurized-Water Test Facility NJC-1-3-05.pdf (615 kb)
    14. 1995-06-25---------Jump to [Top]
  14. 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)
    15. 1995-08-01---------Jump to [Top]
  15. 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)
    16. 1997-04-01---------Jump to [Top]
  16. 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)
    17. 1999-02-23---------Jump to [Top]
  17. Decay Heat Estimates for MNR, by Wm.J. Garland, McMaster University, 1999-02-23. Doc type: Other.
    Summary: Decay heat removal is essential in preventing fuel overheating and possible fission product release.  This
    Keywords: [Concept] - [SI] 31000 Reactor [Discipline] Nuclear Engineering [Topic] Basic Equations Modelling Reactor Physics [Phase] Concept Design Safety Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - decayhe1.xls (521 kb)
    18. 2009-05-30---------Jump to [Top]
  18. 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)
  19. 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)
    20. 2015-01-01---------Jump to [Top]
  20. 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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