Jump to year -> [1958-09-01] [1961-09-18] [1968-05-01] [1976-03-01] [1980-01-01] [1987-03-01] [1987-12-01] [1989-05-01] [1995-09-11] [1999-03-01] [2000-03-29] [2001-03-06] [2015-01-01]
[SI]: 37000 Fuel 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: 49

    1958-09-01---------Jump to [Top]
  1. NPD-2 Design Description, OPG, 1958-09-01. Doc type: Report.
    Summary: This booklet presents a detailed design description of the NPD-2 station, a joint project of AECL, CGE and the Hydro-Electric Power Commission of Ontario.
    Keywords: [Concept] General [SI] 00000 General Project 30000 Reactor, Steam Generators and Auxiliaries 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Description [Audience] College Engineer High Technician Ugrad
    - Canada's First Nuclear Power Station CGE-NPD-DD-Sept1958.pdf (2766 kb)
    2. 1961-09-18---------Jump to [Top]
  2. NPD, a Description of, by J.L Olsen, OPG, 1961-09-18. Doc type: Presentation.
    Summary: Nuclear Power Demonstration. An illustrated talk presented at the Seventh AECL Symposium on Atomic Energy, Chalk River, September 18, 1961.
    Keywords: [Concept] General [SI] 00000 General Project 30000 Reactor, Steam Generators and Auxiliaries 37000 Fuel 40000 Turbine, Generator and Auxiliaries 60000 Instrumentation and Control [Discipline] Nuclear Engineering [Topic] Intro and Overview Physical Description Process Systems [Phase] Design Description [Audience] College Engineer High Technician Ugrad
    - Canada's First Nuclear Power Station CAPD10--Sept1961NPD-Description.pdf (5637 kb)
    3. 1968-05-01---------Jump to [Top]
  3. 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)
    4. 1976-03-01---------Jump to [Top]
  4. 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)
    5. 1980-01-01---------Jump to [Top]
  5. 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 20042001.pdf (35 kb)
    - Chapter 2 - Physical Description of the CANDU-600 20042002.pdf (672 kb)
    - Chapter 3 - Methodology for Reactor Physics Analysis In Core Design 20042003.pdf (1922 kb)
    - Chapter 4 - Initial Fuel Loading Determination 20042004.pdf (379 kb)
    - Chapter 5 - Physics Analysis and Tests Related to Commissioning 20042005.pdf (764 kb)
    - Bibliography 20042006.pdf (111 kb)
    6. 1987-03-01---------Jump to [Top]
  6. Nuclear Journal of Canada, 1987 Vol 1 No. 1, by G. Hotte, G. Parent, L. Cloutier, A. Aubin, and N. Macici, CNS, 1987-03-01. Doc type: Paper.
    Summary: This paper gives an overview of the Gentilly-2 experience in managing the CANDU nuclear fuel cycle in an efficient and secure manner. The following areas of fuel management are covered: quality assurance in fuel design and fabrication; fuel supply; in-core fuel management including core follow-up and fuel replacement strategies; detection and replacement of defective fuel; spent fuel storage.
    Keywords: [Concept] Reactor Physics [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Reactor Physics [Phase] Operation [Audience] College Engineer Grad Manager Technician Ugrad
    - Gestion du cycle de combustible a la Centrale Nucleaire Gentilly-2 NJC-1-1-10.pdf (762 kb)
    7. 1987-12-01---------Jump to [Top]
  7. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by J.A.L. Robertson, CNS, 1987-12-01. Doc type: Paper.
    Summary: The outstanding performance of CANDU fuel is attributed to a well-rounded development program that combined sound science with excellent engineering. Economic analysis and technology transfer were integrated into the program to ensure successful commercialization. The CANDU fuel program provides useful lessons that are being Ignored by policymakers in their desire to exploit our world-elass resources in science and technology to benefit the Canadian economy.
    Keywords: [Concept] Materials [SI] 01000 General Engineering (Methods, Policy, Procedures) 37000 Fuel [Discipline] General Engineering History Materials Engineering [Topic] Performance [Phase] Design [Audience] Engineer Grad Manager Ugrad
    - Fuel for Thought NJC-1-4-07.pdf (876 kb)
    8. 1989-05-01---------Jump to [Top]
  8. CANDU Advanced Plutonium Burner - The Canadian Response to the ALWR, by A.R. Dastur and A.C. Mao , AECL, 1989-05-01. Doc type: Paper.
    Summary: As published in the Canadian Nuclear Society Bulletin Vol. 10, No. 3, 1989 with the kind permission of the CNS: It is demonstrated that the prescnt CANDU design concept has potential for increased conversion and resource utilization compared with other reactor concepts. Discussed here is a CANDU based concept thau utilizes energy produced by subcritical multiplication in a fertile region designed for accelerated plutonium production is presented. Its feasibility is based on incorporating the channels with fertile material into the primary heal transport circuit. Calculations with multigroup transport codes predict very high fuel utilization due to the production and burnup of fissile plutonium in the fertile region.
    Keywords: [Concept] Reactor Physics [SI] 03300 Nuclear Engineering 31000 Reactor 37000 Fuel [Discipline] Nuclear Engineering [Topic] Conceptual Reactor Physics [Phase] Concept [Audience] Engineer Grad Manager Ugrad Vendor
    - 19890101.pdf (299 kb)
    9. 1995-09-11---------Jump to [Top]
  9. 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 20054702.pdf (443 kb)
    10. 1999-03-01---------Jump to [Top]
  10. CANDU Fuel Management Course, by Ben Rouben, AECL, 1999-03-01. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
    - Cover Page 20031100.pdf (91 kb)
    - Complete Course 20031101.pdf (286 kb)
    - Basic Characteristics of the CANDU Lattice 20031111.pdf (186 kb)
    - The CANDU Reactivity Devices 20031112.pdf (147 kb)
    - Detector Systems 20031113.pdf (141 kb)
    - Computational Scheme for CANDU Neutronics 20031114.pdf (182 kb)
    - General Discussion on CANDU Fuel Management 20031115.pdf (125 kb)
    - Equilibrium-Core Design 20031116.pdf (217 kb)
    - Ongoing Reactor Operation with Channel Refuellings 20031117.pdf (252 kb)
    - Effects of 135Xe 20031118.pdf (151 kb)
    - Summary 20031119.pdf (61 kb)
    - Basic Characteristics of the CANDU Lattice - Figures 20031121.pdf (324 kb)
    - The CANDU Reactivity Devices - Figures 20031122.pdf (404 kb)
    - Detector Systems - Figures 20031123.pdf (418 kb)
    - Computational Scheme for CANDU Neutronics - Figures 20031124.pdf (83 kb)
    - General Discussion on CANDU Fuel Management - Figures 20031125.pdf (78 kb)
    - Equilibrium-Core Design - Figures 20031126.pdf (309 kb)
    - Ongoing Reactor Operation with Channel Refuellings - Figures 20031127.pdf (323 kb)
    - Effects of 135Xe - Figures 20031128.pdf (99 kb)
    11. 2000-03-29---------Jump to [Top]
  11. RFSP Training Course, by Benoit Arsenault, AECL, 2000-03-29. Doc type: Course.
    Summary:
    Keywords: [Concept] - [SI] 37000 Fuel [Discipline] Nuclear Engineering [Topic] Modelling Reactor Physics [Phase] Design Analysis [Audience] Engineer Grad
    - Chapter 01 - Course Agenda 20054301.pdf (106 kb)
    - Chapter 02 - General Intro to Methods of Physics Analysis & Physics Computer Codes 20054302.pdf (381 kb)
    - Chapter 03 - The RFSP Direct-Access File 20054303.pdf (274 kb)
    - Chapter 04 - RFSP Model 20054304.pdf (400 kb)
    - Chapter 05 - Time-Average Model 20054305.pdf (322 kb)
    - Chapter 06 - Spatial Kinetics 20054306.pdf (272 kb)
    - Chapter 07 - Powderpufs-V 20054307.pdf (348 kb)
    - Chapter 08 - *Simulate and *Intrep 20054308.pdf (494 kb)
    - Chapter 09 - Flux and Power Mapping in RFSP 20054309.pdf (375 kb)
    - Chapter 10 - RRS Modelling in RFSP 20054310.pdf (275 kb)
    - Chapter 11 - *INSTANTAN 20054311.pdf (127 kb)
    - Chapter 12 - RFSP Code Development 20054312.pdf (336 kb)
    12. 2001-03-06---------Jump to [Top]
  12. Fuel for the Next Millennia, by Dan 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)
    13. 2015-01-01---------Jump to [Top]
  13. 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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