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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
Learning Resources
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