UN0803 - Nuclear Reactor Safety Design
(2011 version)
(This course is based on McMaster's EP714)

Announcements

  • Offered 2011.08.20 - 2011.10.16
  • Location: Lecture Theatre, Durham College - Whitby Campus, 1610 Champlain Avenue, Whitby. See Campus Maps.
  • Distance Education - If you will be participating in the course using distance education please inform the instructor by email prior to the course commencing. Access distance ed courses using Elluminate at, https://maclive.mcmaster.ca/
  • Although the level of physics and math required for UN0803 is relatively modest, it is highly recommended that you review the Physics refresher / prerequisite material for this course and the general Math refresher / prerequisite to ensure you are ready for UN0803. See the Refresher / Prerequisite Material page for further information.
  • It is assumed you are familiar with CANDU design. If not it is highly recommended that you skim the text for UN0803 to understand what you need to know; and read a summary of the CANDU design. The CANDU 6 technical summary can be found on the Refresher / Prerequisite Material page under the CANDU NPP heading, and the ACR-1000 Technical Description can be found under "supplementary reading" further down this page (for the latter, please ask the UN0803 lecturer for the password).

Course Description:

Safety design and analysis of nuclear reactors based on deterministic and probabilistic assessments. Topics include: concepts of risk; probability tools and techniques; safety criteria; design basis accidents; risk assessment; safety analysis; safety system design; and general policy and principles.

Prerequisite: Registration in the UNENE Joint M. Eng. Program
Instructor: Victor Snell.

Course Administration

  • Schedule - 9:00 am start
    • August 20 & 21
    • September 10 & 11
    • September 24 & 25
    • October 15 & 16

Course Notes:

  • Information below is the 2010 version unless otherwise noted. Stay tuned for updates.
  • Course Outline
  • Project
  • Chapter 1 - Introduction (Snell)
    • Text (pdf 739kb) - new as of 2011.08.17
    • Lecture 1 Slides (pdf 582kb) - new as of 2011.08.17
  • Chapter 2 - Design Basis Accidents (Snell)
    • Text (pdf 8.1Mb) - new as of 2011.08.19
    • Lecture 2 Slides (pdf 1.46Mb) - new as of 2011.08.19
  • Chapter 3 - Case Studies (Snell)
  • Chapter 4 - Probability Tools and Techniques
  • Chapter 5 - Safety Systems
  • Chapter 6- Safety Goals
  • Chapter 7 - Accident Analysis
  • Chapter 8 - Technology of Accident Analysis
  • Chapter 9 - Whither Safety
  • Supplementary reading
    • IAEA-NS-R-1 (pdf 201kb) - Safety of Nuclear Power Plants: Design - Safety Requirements
    • ICONE 12-49287 (pdf 145kb) - The Probability and Management of Human Error, Romney B. Duffey and John W. Saull, Proceedings of ICONE12: 12th International Conference on Nuclear Engineering , April 25-29, 2004, Virginia, USA
    • ACR-1000 Technical description, AECL 10820-01371-TED-001, Revision 2 (pdf 8.5Mb, 627 pages) [password protected - contact instructor]

Course Assignments and Projects

  • Student Reports
    • to come

Learning Resources

 

 
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Items of Interest

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