Supplemental Text for Power Conversion Lectures
NRC Regulations Title 10, Code of Federal Regulations – Appendix A to Part 50, General Design Criteria for Nuclear Power Plants. U. S. NRC.
NRC Regulations Title 10, Code of Federal Regulations – Appendix B to Part 50, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants. U. S. NRC.
NRC Regulations Title 10, Code of Federal Regulations – Part 50, Domestic Licensing of Production and Utilization Facilities. U. S. NRC.
Safety Culture Evaluation of the Davis-Besse Nuclear Power Station. Conducted by Performance, Safety, and Health Associates, Inc. April 14, 2003. (PDF)
Overview, goals of course
Review of reactor types
|Chapters 1, 2, and 4 [RAK]|
|2||Review of reactor physics||Chapter 4 [RAK]|
|3||Review of reactor kinetics and control||Chapters 5 and 6 [RAK]|
|4||Review of feedback effects and depletion||Chapter 6 [RAK]|
|6||Reactor heat removal||Chapter 7 [RAK]|
|7||Design issues: power cycles for nuclear plants|| |
Chapters 8, 9, and 10 [RAK]
Chapter 2 [MMEW]
|8||Power cycles for nuclear plants – Rankine and Brayton cycle||Chapters 7 and 8 [MMEW]|
|10||Safety systems and functions|| |
Chapter 13 [RAK]
|11||Safety analysis report and LOCA||Chapter 15 [RAK]|
|21||Significant nuclear accidents – Three Mile Island||Rogovin, Mitchell. Three Mile Island: A Report to the Commissioners and to the Public, Volume 1. Washington DC, Washington: NRC, 1980.|
|22||Significant nuclear accidents – Chernobyl||Chapter 15 [RAK]|
|24||Role of safety culture|| |
Sorensen, J. N. "Safety Culture: A Survey of the State-of-the-Art." Reliability Engineering and System Safety 76, (2002): 189-204.
Kadak, Andrew, C. "What's A Safety Culture? How Do I Get It? How Do I Keep It?" Nuclear Nonoperating Owner's Group, Boston, MA (September 28, 1989): 1-11. (PDF)
|25||Current regulatory issues||NRC Generic Letter 92-01, Revision 1, Supplement: Reactor Vessel Structural Integrity. May 19, 1995. U. S. NRC. (PDF - 2.6MB)|