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Abstract/Syllabus:
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Apostolakis, George, Neil Todreas, Ronald Ballinger, and Andrew Kadak, 22.39 Integration of Reactor Design, Operations, and Safety, Fall 2006. (Massachusetts Institute of Technology: MIT OpenCourseWare), http://ocw.mit.edu (Accessed 07 Jul, 2010). License: Creative Commons BY-NC-SA
Integration of Reactor Design, Operations, and Safety
Fall 2006
The "GEN IV" (Generation IV) design is a next generation nuclear power plant that produces electricity and hydrogen without greenhouse gas emissions. (Image courtesy of U.S. DOE.)
Course Highlights
This course features an extensive set of lecture slides, readings, and assignments.
Course Description
This course integrates studies of engineering sciences, reactor physics and safety assessment into nuclear power plant design. Topics include materials issues in plant design and operations, aspects of thermal design, fuel depletion and fission-product poisoning, and temperature effects on reactivity, safety considerations in regulations and operations, such as the evolution of the regulatory process, the concept of defense in depth, General Design Criteria, accident analysis, probabilistic risk assessment, and risk-informed regulations.
Technical Requirements
Special software is required to use some of the files in this course: .zip
Syllabus
This page includes a course calendar.
Prerequisites
22.211, 22.312
Textbooks and Readings
There is no required textbook for the course. Readings will be assigned from various regulatory, industry, and scientific sources.
Assignments
Students are required to complete nine homework problems and a midterm paper on national nuclear energy strategy.
Grading
Grading criteria.
| ACTIVITIES |
PERCENTAGES |
| Homework (Weighted, see below) |
35% |
| National Nuclear Energy Strategy Paper |
20% |
| Midterm Oral Exam |
10% |
| Final Oral Exam |
35% |
Homework Weighting
The score of each homework problem will be adjusted in accordance with the following relative weighting:
Homework weighting.
| PROBLEMS # |
MAXIMUM SCORES |
| 1 |
20 |
| 2 |
60 |
| 3 |
15 |
| 4 |
25 |
| 5 |
40 |
| 6 |
25 |
| 7 |
10 |
| 8 |
50 |
| 9 |
20 |
Calendar
Course calendar.
| LEC # |
TOPICS |
INSTRUCTORS |
KEY DATES |
| 1 |
Nuclear Energy System Strategies |
Prof. Todreas |
|
| 2 |
Design Goals and Interrelationship of Core Design Parameters |
Prof. Todreas |
|
| 3 |
Thermal Hydraulic Design Requirements - LWR Steady State and Transient Design |
Prof. Todreas |
Problem 1 due (topic of Lec #2) |
| 4 |
Thermal Hydraulic in Safety Analysis |
Prof. Todreas |
|
| 5 |
Reactor Physics - Design Parameters for PWRs |
Prof. Apostolakis |
|
| 6 |
Design Requirements - Safety and Critical Safety Functions |
Prof. Apostolakis |
Problem 2 due (topic of Lec #3) |
| 7 |
Reactor Safety: The Emergence of Probabilistic Risk Assessment |
Prof. Apostolakis |
|
| 8 |
Reactor Physics - Design Parameters for GFRs |
Chris Handwerk, Course TA |
Problem 3 due (topic of Lec #5) |
| 9 |
PRA Methodology Overview |
Prof. Apostolakis |
Problem 4 due (topic of Lec #6 and #7) |
| 10 |
Probabilistic Calculations - I |
Prof. Apostolakis |
|
| 11 |
Probabilistic Calculations - II |
Prof. Apostolakis |
Paper: U.S. National Nuclear Strategy (topic of Lec #1) due two days after Lec #11 |
| 12 |
Risk-Informed Changes to the Licensing Basis-I |
Prof. Apostolakis |
|
| 13 |
Applying Safety Regulations to Plant Operations |
Prof. Kadak |
Problem 5 due (topic of Lec #10 and 11) |
| 14 |
Risk-Informed Changes to the Licensing Basis-II |
Prof. Apostolakis |
|
| 15 |
Large Break LOCA Analysis/Result |
Prof. Todreas |
|
| 16 |
The Maintenance Rule I |
Prof. Apostolakis |
|
| 17 |
The Maintenance Rule II |
|
Problem 6 due (topic of Lec #13)
|
| 18 |
Plant Economic Evaluation |
Prof. Todreas |
|
| 19 |
Plant Economic Evaluation (cont.) |
Prof. Todreas |
|
| 20 |
Materials Selection Process |
Prof. Ballinger |
Problem 7 due (topic of Lec #15) |
| 21 |
Radiation Damage Effects and Their Design Implications |
Prof. Ballinger |
|
| 22 |
Environmental Degradation and its Design Implications |
Prof. Ballinger |
|
| 23 |
PWR Materials Applications |
Prof. Ballinger |
Problem 8 due (topic of Lec #18) |
| 24 |
GFR Materials Applications |
Prof. Ballinger |
|
| 25 |
Risk Informed Design
Guidance for Gen IV Reactors |
Prof. Apostolakis |
Problem 9 due (topic of Lec #21 and #22) two days after Lec #25 |
| 26 |
Integration of Design Process - IRIS as the Example |
Guest Lecturer: Bojan Petrovich, Westinghouse |
|
| 27 |
Integration of Design Process - 1: IRIS Plant, 2: Sample Oral |
Prof. Todreas/Prof. Apostolakis |
|
| 28 |
Student Oral Exams, 45 min. (Scheduled to Meet Individual Student Availability) |
Exam Committee |
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Further Reading:
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Readings
The following table lists the readings assigned for particular lecture sessions.
|
Course readings.
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|
LEC #
|
TOPICS
|
INSTRUCTORS
|
READINGS
|
|
1
|
Nuclear Energy System Strategies
|
Prof. Todreas
|
United States (2006)
Todreas, N. T. Testimony before the Hearing on R&D Priorities in the Global Nuclear Energy Partnership - Subcommittee on Energy Committee on Science, United States House of Representatives. April 6, 2006. (PDF)
Lester, R. K. "New Nukes." Issues in Science and Technology 22, no. 4 (Summer 2006): 39-46.
Chapter 1 in The Future of Nuclear Power: An Interdisciplinary MIT Study. 2003.
GenIV International Forum. "A Technology Roadmap for Generation IV Nuclear Energy Systems." U.S. DOE, GIF-002-00, December 2002.
France (2005)
CEA Nuclear Energy Division. "Future Nuclear Energy Systems R&D Strategy in France." April 12, 2005
China (2005)
Xu, Mi. "Status and Prospects of Sustainable Nuclear Power Supply in China." Proceedings of GLOBAL 2005. Tsukuba, Japan: October 9-13, 2005, Paper 511.
Russia (2000)
"Strategy for the Development of Power Engineering in Russia for the First Half of the 21st Century: Principal Provisions." Ministry of Atomic Power Engineering of the Russian Federation. Moscow, 2000.
"Millennium Summit." Excerpt from Address Made by President of Russian Federation V. V. Putin at UN Summit. September 6, 2000.
Adamov, Y. O. "Nuclear Power May Get Its Second Wind in the 21st Century." Nuclear News (November 2000): 38-42.
Todreas, N. T. "Comment on Adamov Paper." Nuclear News (November 2000). (PDF)
Uranium/Oil (2005/06)
"Uranium: Glowing." The Economist (August 17, 2006): 53-54.
Nocera, Joseph. "On Oil Supply, Opinions Aren't Scarce." New York Times, September 10, 2005.
Canada (2006)
Meneley, D. A. "Transition to Large Scale Nuclear Energy Supply."
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2
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Design Goals and Interrelationship of Core Design Parameters
|
Prof. Todreas
|
Class Note 1: Relationships Among Key Reactor System Design Variables (PDF - 1.1 MB)
|
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3
|
Thermal Hydraulic Design Requirements - LWR Steady State and Transient Design
|
Prof. Todreas
|
Class Note 2: Thermal Hydraulics Design Limits. (PDF)
U.S. NRC. "Thermal and Hydraulic Design." Section 4.4 in Standard Review Plan NUREG-0800. (PDF)
Ferroni, P., M. Fratoni, and N. Todreas, et al. "Feasibility of Improving BWR Performance Using Hydride Fuel." Paper 6241 in Proceedings of ICAPP '06. Reno, NV: USA, June 4-8, 2006.
Optional Reading
Fratoni, M., and E. Greenspan. "Optimal Hydride Fueled BWR Assembly Designs." Advances in Nuclear Analysis and Simulation, PHYSOR 2006. Vancouver, BC: Canada, September 10-14, 2006.
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16
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The Maintenance Rule I
|
Prof. Apostolakis
|
U.S. NRC. "Requirements for monitoring the effectiveness of maintenance at nuclear power plants." 10 CFR 50.65.
———. "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." Regulatory Guide 1.182.
Brewer, H. D., and K. S. Canady. "Probabilistic safety assessment support for the maintenance rule at Duke Power Company." Reliability Engineering & System Safety 63 (1999):243-249.
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18
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Plant Economic Evaluation
|
Prof. Todreas
|
Todreas, N. T. "Perspectives on the Economics of Nuclear Power from the MIT Study." (PDF)
Wald, Matthew L. "Committed to Coal, and in a Hurry, Too." New York Times, November 7, 2006, p. C1.
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19
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Plant Economic Evaluation (cont.)
|
Prof. Todreas
|
World Nuclear Association. "Supply of Uranium." June 2006.
|
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20-24
|
Materials Selection Process
Radiation Damage Effects and Their Design Implications
Environmental Degradation and its Design Implications
PWR Materials Applications
GFR Materials Applications
|
Prof. Ballinger
|
Required Readings
The following sections in Korb, L. J., ed. Metals Handbook. 9th ed. Volume 13, Corrosion. Materials Park, OH: ASM International, 1987. ISBN: 9780871700193.
Craig, B., and S. L. Pohlman. "Introduction."
Pohlman, S. L., ed. "General Corrosion."
Dexter, S. C., ed. "Localized Corrosion."
Steigerwald, R. "Metallurgically Influenced Corrosion."
Silverman, D. C., and R. B. Puyear. "Effects of Environmental Variables on Aqueous Corrosion."
Ma, B. "Fundamental Radiation Effects on Materials." Chapter 4 in Nuclear Reactor Materials and Applications. New York, NY: Springer-Varlag, 1982. ISBN: 9780442225599.
Olander, Donald E. "Radiation Damage." Chapter 17 in Fundamental Aspects of Nuclear Reactor Fuel Elements. Washington, DC: U.S. DOE, 1976. (PDF 1 - 2.0 MB) (PDF 2 - 1.9 MB)
U.S. NRC. "Radiation Embrittlement of Reactor Vessel Materials." In Regulatory Guide 1.99 (Revision 2, May 1988). (PDF - 1.6 MB)#
———. "Reevaluation of the pressurized thermal shock rule (10 CFR 50.61) screening criterion." June 23, 2000.
Optional Readings
Kohyama, A., et al. "R&D of Advanced Material Systems for Reactor Core Component of Gas Cooled Fast Reactor." Proceedings of ICAPP '05. Seoul: Korea, May 15-19, 2005. Paper 5282.
The following sections in Korb, L. J., ed. Metals Handbook. 9th ed. Volume 13, Corrosion. Materials Park, OH: ASM International, 1987. ISBN: 9780871700193.
Marek, M. I., et al. "Thermodynamics of Aqueous Corrosion."
Shoesmith, D. W. "Kinetics of Aqueous Corrosion."
Nuclear Energy Agency, OECD. "Accelerator-driven Systems (ADS) and Fast Reactors (FR) in Advanced Nuclear Fuel Cycles." NEA No. 3109, 2002.
———. "Fuels and Materials for Transmutation." NEA No. 5419, 2005. (PDF)
Olander, Donald E. "Radiation Effects in Metals: Hardening, Embrittlement, and Fracture," and "Radiation Effects in Metals: Void Swelling and Irradiation Creep." Chapters 18 and 19 in Fundamental Aspects of Nuclear Reactor Fuel Elements. Washington, DC: U.S. DOE, 1976. (PDF 1 - 4.9 MB) (PDF 2 - 4.8 MB)
U.S. NRC. Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. NUREG-1800, Rev. 1. September, 2005. (PDF - 1.5 MB)
———. Generic Aging Lessons Learned (GALL) Report. (PDF 1 - 1.1 MB) (PDF 2 - 4.3 MB)
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26
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Integration of Design Process - IRIS as the Example
|
Guest Lecturer: Bojan Petrovich, Westinghouse
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Mizuno, Y., H. Ninokata, and D. J. Finnicum. "Risk-informed design of IRIS using a level-1 probabilistic risk assessment from its conceptual design phase." Reliability Engineering and System Safety 87 (2005): 201-209.
Carelli, M. D., B. Petrovic, and N. E. Todreas, et al. "The Design and Safety Features of the IRIS Reactor." Nuclear Engineering & Design 230 (2004): 151-167.
Carelli, M. D., and B. Petrovic. "A Flexible and Economic Small Reactor." Nuclear Plant Journal (September-October 2006): 28-35.
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