Jump to year -> [1962-09-01] [1968-05-01] [1976-03-01] [1987-06-01] [1987-12-01] [1993-06-01] [2002-01-01] [2003-01-01] [2017-12-27]
[Discipline]: Materials Engineering 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: 21

    1962-09-01---------Jump to [Top]
  1. 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)
    2. 1968-05-01---------Jump to [Top]
  2. The Performance of Zirconium Alloy Clad UO2 Fuel for Canadian Pressurized and Boiling Water Power Reactors, by R.D. Page and A.D. Lane, AECL, 1968-05-01. Doc type: Report.
    Summary: This paper presents the most recent information (as of 1968) on the performance of CANDU fuel, and goes on to summarize the results of an extensive irradiation program to develop fuels for boiling water cooled reactors.
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Materials Engineering [Topic] Function Performance [Phase] Design Development Operation [Audience] Engineer
    - 19680101.pdf (2338 kb)
    3. 1976-03-01---------Jump to [Top]
  3. 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)
    4. 1987-06-01---------Jump to [Top]
  4. Nuclear Journal of Canada, 1987 Vol 1 No. 2, by R.L. Tapping, P.A. Lavoie, and D.J. Disney, CNS-, 1987-06-01. Doc type: Paper.
    Summary: Severe pitting has occurred in moderator heat exchangers tubed with Incoloy-800 in Pickering Nuclear Generating Station. The pitting originated on the cooling water side (outside) of the tubes and perforation occurred in less than two years. It was known from corrosion testing at CRNL that Incoloy-800 was not susceptible to pitting in Lake Ontario water under isothermal conditions. Corrosion testing with heat transfer across the tube wall was carried out, and it was noted that severe pitting could occur under deposits formed on the tubes in silty Lake Ontario water. Subsequent testing, carried out in co-operation with Ontario Hydro Research Division, investigated the pitting resistance of other candidate tubing alloys: Incoloy-825, 904 L stainless steel, AL-6X, Inconel-625, 70:30 Cu:Ni, titanium, Sanicro-30 and Sanicro-28. Of these, only titanium and Saniero-28 have not suffered some degree of pitting attack in silt-containing Lake Ontario water. In the absence of silt. and hence deposits, no pitting took place on any of the alloys tested.
    Keywords: [Concept] Materials [SI] 32000 Moderator System [Discipline] Materials Engineering [Topic] Corrosion [Phase] - [Audience] Engineer Grad Ugrad
    - Corrosion of Heat Exchanger Materials under Heat Transfer Conditions NJC-1-2-05.pdf (418 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)
    5. 1987-12-01---------Jump to [Top]
  5. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by F.P. Vaccaro, G.J. Theus and B.P. Miglin, CNS-, 1987-12-01. Doc type: Paper.
    Summary: This review of the stress corrosion cracking (scc) of Alloy 600 tubing assesses the relative importance of steam generator operating temperature in contrast to other factors.
    Keywords: [Concept] Chemistry and Corrosion [SI] 36000 Steam Generator Steam and Water Systems [Discipline] Chemical Engineering Materials Engineering [Topic] Corrosion Performance [Phase] Operation [Audience] College Engineer Grad Technician Ugrad
    - The Effect of Steam Generator Tube Temperature on the Stress Corrosion Cracking of Alloy 600 NJC-1-4-04.pdf (663 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)
    6. 1993-06-01---------Jump to [Top]
  6. Materials, Nuclear Training Course 228, OPG, 1993-06-01. Doc type: Course.
    Summary: General material properties and the approach to material selection for CANDU reactors. Failure modes of materials, both mechanical and radiation induced. Pressure tube problems.
    Keywords: [Concept] Materials [SI] 31000 Reactor [Discipline] Materials Engineering [Topic] Conceptual [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Material Properties and Selection: Cover page, Table of contents, Introduction 20040900.pdf (140 kb)
    - Material Properties and Selection: Basic Material Properties and How They Can Be Altered, 20040901.pdf (553 kb)
    - Material Properties and Selection: Common Mechanical-Based Failure Modes, 20040902.pdf (870 kb)
    - Material Properties and Selection: Selection and Specification of Materials for Nuclear Applications, 20040903.pdf (514 kb)
    - Effect of Radiation on Materials: Radiation Damage to Materials, 20040904.pdf (547 kb)
    - Effect of Radiation on Materials: Problems with Pressure Tubes, 20040905.pdf (612 kb)
    7. 2002-01-01---------Jump to [Top]
  7. Materials Course, CNSC, 2002-01-01. Doc type: Course.
    Summary: This course covers the following areas pertaining to Mechanical Properties: Mechanical and Thermal Stress, Corrosion, Pressure Tubes and Fuel Bundles
    Keywords: [Concept] Materials [SI] - [Discipline] Materials Engineering [Topic] Corrosion Radiation [Phase] Concept Design Operation [Audience] College Engineer Ugrad
    - Cover Page 20030300.pdf (86 kb)
    - , 20030301.pdf (844 kb)
    - Materials & Chemistry, 20030302.pdf (687 kb)
    - Corrosion, 20030303.pdf (1280 kb)
    - Radiation Effects on Materials, 20030304.pdf (1093 kb)
    - Les Matériaux, 20070600.pdf (420 kb)
    8. 2017-12-27---------Jump to [Top]
  8. Canada's Power Reactor Fuel Bundle Design and Development, by R.D. Page and A.J. Langdon, AECL, 2017-12-27. Doc type: Other.
    Summary: This pictorial record of Canada's power reactor fuel bundles was prepared to historically record the evolution of the power reactor fuel over the years. No one report issued over the years has been able to describe in detail the various changes that these pictures portray. It should be noted that the record does not include WR-1 type fuel or special irradiation of assemblies. "A picture speaks a thousand words". Full resolution versions of the images contained in this document can be found in the Image Library of CANTEACH web site http://canteach.candu.org listed under the System Index (SI) 37000 - Fuel.
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Materials Engineering Mechanical Engineering [Topic] Chemistry Fluid Mechanics Heat Transfer Physical Description Thermalhydraulics [Phase] Concept Design Design Evolution [Audience] College Engineer Grad High Manager Technician Ugrad
    - Historical and Pictorial Record FuelStory.pdf (355 kb)
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