| 1 |
Nuclear Energy System Strategies
Interrelationship of Core Design Parameters |
Prof. Todreas |
Xu, Mi. "Status and Prospects of Sustainable Nuclear Power Supply in China." Proceedings of GLOBAL 2005. Tsukuba, Japan: October 9-13, 2005, paper #511.
GenIV International Forum. "A Technology Roadmap for Generation IV Nuclear Energy Systems."
"The Future of Nuclear Power." MIT, July 2003.
CEA-Nuclear Energy Division. "Future Nuclear Energy Systems R&D Strategy in France." April 12, 2005.
Nocera, Joseph. "On Topics of Oil Supply, Opinions Aren't Scarce." New York Times, September 10, 2005.
Associated Press. "U.S. Panel Backs Nuclear Dump On Indian Reservation in Utah." New York Times, September 9, 2005. |
| 2 |
Design Requirements - T/H |
Prof. Todreas |
U.S. NRC. "Thermal and Hydraulic Design." Section 4.4 in Standard Review Plan NUREG-0800. (PDF) |
| 3 |
Design Requirements - Reactor Physics |
Prof. Apostolakis |
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| 4 |
Design Requirements - Safety |
Prof. Apostolakis |
North Atlantic Energy Service Corp. "Seabrook Station Probabalistic Safety Study (SSPSS - 1999) - Tier 1."
"Decrease in Reactor Coolant Inventory." In Seabrook Station UFSAR (Updated Final Safety Analysis Report): Accident Analyses. |
| 5 |
The PWR and GFR Design Challenges |
Prof. Todreas |
Carelli, M. D., et al. "The Design and Safety Features of the IRIS Reactor." In 11th International Conference on Nuclear Engineering. Tokyo, Japan: The Japan Society of Mechanical Engineers, 2003.
Hejzlar, P., M. J. Pope, W. C. Williams, and M. J. Driscoll. "Gas Cooled Fast Reactor for Generation IV Service." Progress in Nuclear Energy 47, no. 1-4 (2005): 271-282. |
| 6 |
Reactor Physics - Design Parameters for PWRs |
Dr. Pilat |
U.S. NRC. "Nuclear Design." Section 4.3 in Standard Review Plan NUREG-0800. (PDF)
FPL Energy. "Seabrook Station: Cycle 10 Startup Report." Filed with NRC, Docket No. 50-443 (NYN-03106). |
| 7 |
Reactor Physics - Design Parameters for GFRs |
Dr. Hejzlar |
Garnier, J. C., et al. "Feasibility Study of an Advanced GFR: Design Trends and Safety Options, Status of France and US Studies." Global 2003 Conference Paper.
Rouault, J., and T. Y. C. Wei. "I-NERI France-U.S. GFR Project: Synthesis of Main Design Trends." ICAPP '05. Seoul, Korea: May 2005.
Wade, D. C., and Y. I. Chang. "The Integral Fast Reactor Concept: Physics of Operation and Safety." Nuclear Science and Engineering 100 (1988): 507-524.
Wei, T. Y. C., P. Hejzlar, et al. "A Semi-Passive Approach to GFR Depressurized Decay Heat Removal Accidents." ICAPP '05. Seoul, Korea: May 2005. (PDF) (Courtesy of Argonne National Laboratory for the U.S. Dept. of Energy and the authors. Used with permission.) |
| 8 |
Reactor Safety: The Emergence of Probabilistic Risk Assessment |
Prof. Apostolakis |
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| 9 |
Large Break LOCA Analysis/Results |
Prof. Todreas |
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| 10 |
Safety Impact on Design and Performance of Reactor Systems |
Prof. Golay |
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| 11 |
Risk-Informed Changes to the Licensing Basis |
Prof. Apostolakis |
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| 12 |
Logic Diagrams |
Prof. Apostolakis |
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| 13 |
Probabilistic Calculations |
Prof. Apostolakis |
Garrick, B. J. "Recent Case Studies and Advancements in Probabilistic Risk Assessment." Risk Analysis 4, no. 4 (1984): 267-279. |
| 14 |
Deterministic and Risk Informed Performance Based Regulation |
Prof. Golay |
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| 15 |
Use of PWR in Design - GFR Example |
Prof. Apostolakis |
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| 16 |
Applying Safety Regulations to Plant Operation |
Prof. Kadak |
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| 17 |
Thermal Hydraulic Considerations - Transients and Accidents |
Prof. Todreas |
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| 18 |
Thermal Hydraulic Considerations - Steady State |
Prof. Todreas |
Greenspan, E., N. Todreas, B. Petrovic, et al. "Optimization of UO2 Fueled PWR Core Design." Paper 5569, Proceedings of ICAPP. Seoul, Korea: May 15-19, 2005. |
| 19 |
Take-home Midterm Exam |
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| 20 |
Materials Selection Process |
Prof. Ballinger |
Ma, B. "Fundamental Radiation Effects on Materials." Chapter 4 in Nuclear Reactor Materials and Applications. New York, NY: Chapman & Hall, 1982. ISBN: 0442225598.
Olander, Donald E. Fundamental Aspects of Nuclear Reactor Fuel Elements. Washington, DC: US DOE, 1976, chapters 17-19. (PDF 1)# (PDF 2)# (PDF 3 - 2.1 MB)# (PDF 4 - 2.0 MB)# |
| 21 |
Risk Informed Design Guidance for Gen IV Reactors |
Prof. Apostolakis |
Delaney, M. J., G. E. Apostolakis, and M. J. Driscoll. "Risk-informed design guidance for future reactor systems." Nuclear Engineering and Design 235 (2005): 1537-1556. |
| 22 |
Radiation Damage Effects and their Design Implications |
Guest Lecturer |
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| 23 |
Environmental Degradation and its Design Implications |
Prof. Ballinger |
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| 24 |
PWR Materials Applications |
Prof. Ballinger |
Korb, L. J., ed. Metals Handbook. Volume 13: Corrosion. 9th ed. Materials Park, OH: ASM International, 1989, pp. 18-189. ISBN: 0871700190.
U.S. NRC. "Radiation Embrittlement of Reactor Vessel Materials." In Regulatory Guide 1.99 (Revision 2, May 1988). (PDF - 1.7 MB)#
Andresen, P. L., et al. "Proactive Materials Degradation Assessment." Draft NUREG for U.S. NRC, 2005. |
| 25 |
GFR Materials Applications |
Prof. Ballinger |
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| 26 |
Integration of Design Process |
Prof. Todreas |
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| 27 |
Student Oral Exams |
Exam Committee |
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