Jump to year -> [1968-01-01] [1980-01-01] [1984-12-01] [1995-09-11] [1996-01-01] [1996-02-01] [1997-08-01] [1997-12-01] [1997-12-17] [2001-03-06] [2015-01-01]
[Topic]: Fuel Management 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: 39

    1968-01-01---------Jump to [Top]
  1. NPD Systems - Fuel Handling System, Course 053, by Staff, OPG, 1968-01-01. Doc type: Course.
    Summary: This manual is issued as an indoctrination course on the N.P.D. Fuel Handling System. The successful completion of the course and examinations will, however, be required as partial N04, NC4 or NM4 qualifications.
    Keywords: [Concept] Mechanical [SI] 35000 Fuel Transfer and Storage [Discipline] Mechanical Engineering [Topic] Fuel Management Physical Description Process Systems [Phase] Design Operation [Audience] College Engineer Technician Ugrad
    - Reactor Boiler and Auxiliaries Fuel Handling System NPD053-352.pdf (11616 kb)
    2. 1980-01-01---------Jump to [Top]
  2. Fundamentals of CANDU Reactor Nuclear Design (TDAI-244), by A.A. Pasanen, AECL, 1980-01-01. Doc type: Report.
    Summary: A Lecture Series given at Trieste 22 January - 28 March 1980, TDAI-244 1980 August
    Keywords: [Concept] - [SI] 31000 Reactor 37000 Fuel [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Manager Ugrad
    - Title and Table of Contents 20042000.pdf (176 kb)
    - Chapter 1 - Introduction, by A.A. Pasanen, 20042001.pdf (35 kb)
    - Chapter 2 - Physical Description of the CANDU-600, by A.A. Pasanen, 20042002.pdf (672 kb)
    - Chapter 3 - Methodology for Reactor Physics Analysis In Core Design, by A.A. Pasanen, 20042003.pdf (1922 kb)
    - Chapter 4 - Initial Fuel Loading Determination, by A.A. Pasanen, 20042004.pdf (379 kb)
    - Chapter 5 - Physics Analysis and Tests Related to Commissioning, by A.A. Pasanen, 20042005.pdf (764 kb)
    - Bibliography, by A.A. Pasanen, 20042006.pdf (111 kb)
    3. 1984-12-01---------Jump to [Top]
  3. Fluid Mechanics, Nuclear Training Course 223, December 1984, OPG, 1984-12-01. Doc type: Course.
    Summary: These sections provide definitions and sample calculations for basic concepts such as pressure, density, flowrate, etc. and are NOT the same as the corresponding sections in the January 1977 version of 223.
    Keywords: [Concept] Thermalhydraulics [SI] 31000 Reactor [Discipline] Mechanical Engineering [Topic] Fuel Management [Phase] Concept Design Design Analysis [Audience] College Engineer Ugrad
    - Course Objectives 20040400.pdf (29 kb)
    - Fluid Mechanics, 20040401.pdf (599 kb)
    - Answer Section, 20040402.pdf (407 kb)
    4. 1995-09-11---------Jump to [Top]
  4. 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)
    - Global 1995, International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France, by D.A. Meneley, A.R. Dastur, P.J. Fehrenbach and K.H. Talbot, 20054702.pdf (443 kb)
    5. 1996-01-01---------Jump to [Top]
  5. Reactor Physics & Fuelling Strategies 1.4, by R.D. Page, Chulalongkorn University, 1996-01-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Reference to Lecture 10 - Canadian Power Reactor Fuel 20042115.pdf (2381 kb)
    - Reference to Lecture 12 - Results of a Survey on Accident and Safety Analysis Codes, Benchmarks. Verification and Validation Methods, by A.G. Lee and G.B. Wilkin, 20042117.pdf (482 kb)
    - Lecture 1 - Reactor Design Philosophies, by John Brenciaglia, 20042101.pdf (665 kb)
    - Lecture 2 - Use of Reactor Design Codes, by John Brenciaglia, 20042102.pdf (137 kb)
    - Lecture 3 - Lattice Parameter Calculations, by John Brenciaglia, 20042103.pdf (531 kb)
    - Lecture 4 - Core Design Analysis, by John Brenciaglia, 20042104.pdf (332 kb)
    - Lecture 5 - Time Dependence Simulation, by John Brenciaglia, 20042105.pdf (600 kb)
    - Lecture 6 - Initial Fuel Load, by John Brenciaglia, 20042106.pdf (253 kb)
    - Lecture 7 - Startup Physics Tests, by John Brenciaglia, 20042107.pdf (531 kb)
    - Lecture 8 - Power Distribution Control, by John Brenciaglia, 20042108.pdf (720 kb)
    - Lecture 9 - Safety Analysis Requirements, by John Brenciaglia, 20042109.pdf (392 kb)
    - Chapter 10 - Fuel Design Analysis, by John Brenciaglia, 20042110.pdf (187 kb)
    - Lecture 11 - Fueling Strategies and Cycles, by John Brenciaglia, 20042111.pdf (745 kb)
    - Lecture 12 - Research Reactors Requirements, by John Brenciaglia, 20042112.pdf (138 kb)
    - Reference to Lecture 8 - In-Core Fuel Management, by D.A. Jenkins, 20042113.pdf (1105 kb)
    - Reference to Lecture 9 - Role of Physics Analysis in Safety and Licensing, by H.C. Chow, 20042114.pdf (1389 kb)
    - Reference to Lecture 11 - Fuel Management & Reactor Operation - Review of Operating Experience, by G.M. Frescura and A.L. Wight, 20042116.pdf (1501 kb)
    6. 1997-08-01---------Jump to [Top]
  6. Reactor Core Analysis & Fuel Management, Course 1.5, by D. Rozon, Chulalongkorn University, 1997-08-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Reactor Physics [SI] 31000 Reactor [Discipline] Nuclear Engineering Physics [Topic] Fuel Management Reactor Physics [Phase] Design Design Analysis [Audience] Engineer Ugrad
    - Chapter 5 - SLOWKIN: A Simplified Model for the Stimulation of Transients in a SLOWPOKE-2 Reactor 20043405.pdf (1297 kb)
    - Chapter 1 - Coupled Neutronics-Thermalhydaulics LOCA Analysis, by B. Rouben, 20043401.pdf (970 kb)
    - Chapter 2 - Core Physics Aspects of Safety Analysis, by B. Rouben, 20043402.pdf (1188 kb)
    - Chapter 4 - Fuel Management in CANDU, by B. Rouben, 20043404.pdf (1542 kb)
    - Workbook, Chapter 1 - Neutronics-Thermalhydraulics Overheads, by B. Rouben, 20043406.pdf (330 kb)
    - Workbook, Chapter 2 - Core Physics Overheads, by B. Rouben, 20043407.pdf (567 kb)
    - Chapter 3 - Fuel Management and Advanced Fuel Cycles, by D. Rozon, 20043403.pdf (1436 kb)
    7. 2001-03-06---------Jump to [Top]
  7. Fuel for the Next Millennia, by D.A. Meneley, AECL, 2001-03-06. Doc type: Presentation.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Fuel Management [Phase] Concept Design Operation [Audience] Engineer Manager
    - 20010201.pdf (906 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)
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