Jump to year -> [1971-03-01] [1972-05-25] [1987-06-01] [1987-09-01] [1995-06-25] [2009-05-30] [2015-01-01]
[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: 23

    1971-03-01---------Jump to [Top]
  1. 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)
    2. 1972-05-25---------Jump to [Top]
  2. 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 19720102.pdf (1025 kb)
    - Lecture 3 - Power Reactor Types 19720103.pdf (3378 kb)
    - Lecture 4 - Reactor Physics 19720104.pdf (1755 kb)
    - Lecture 5 - Canadian Reactor Fuel 19720105.pdf (3924 kb)
    - Lecture 8 - System Analysis 19720108.pdf (1770 kb)
    - Lecture 9 - Reactor and Station Control 19720109.pdf (2715 kb)
    - Lecture 10 - Plant Layout 19720110.pdf (3190 kb)
    - Lecture 11 - Accident Analysis 19720111.pdf (1418 kb)
    - Lecture 12 - Licensing 19720112.pdf (1755 kb)
    - Lecture 13 - Training 19720113.pdf (1432 kb)
    - Lecture 14 - Canadian Power Reactor Fuel. See AECL 5609 doc#19760101 for an updated version. 19720114.pdf (2844 kb)
    - Lecture 15 - Construction 19720115.pdf (3542 kb)
    - Lecture 16 - Costs 19720116.pdf (764 kb)
    - Lecture 17 - Development Potential 19720117.pdf (1390 kb)
    - Lectures 6 and 7 - Heat Transport and Auxiliary Systems 19720167.pdf (2431 kb)
    3. 1987-06-01---------Jump to [Top]
  3. 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)
    4. 1987-09-01---------Jump to [Top]
  4. 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)
    5. 1995-06-25---------Jump to [Top]
  5. 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)
    6. 2009-05-30---------Jump to [Top]
  6. 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)
  7. 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)
    8. 2015-01-01---------Jump to [Top]
  8. 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)
---end of page---