22.314
Structural Mechanics in Nuclear Power Technology
Fall 2006
This course deals with structural components in nuclear power plant systems, their functional purposes, operating conditions, and mechanical-structural design requirements. It combines mechanics techniques with models of material behavior to determine adequacy of component design. Considerations include mechanical loading, brittle fracture, in-elastic behavior, elevated temperatures, neutron irradiation, and seismic effects.
Readings
- Harvey, John F. Theory and Design of Pressure Vessels . New York, NY: Van Nostrand Reinhold Co., 1985.
- Suresh, S. Fatigue of Materials. 2nd ed. Cambridge, UK: Cambridge University Press, 2001.
- Roberts, J. T. Adrian. Structural Materials in Nuclear Power Systems . New York, NY: Plenum Press, 1981.
- Barsom, J. M., and S. T. Rolf. Fracture and Fatigue Control . 2nd ed. Upper Saddle River, NJ: Prentice Hall, 1987.
- Au-Yang, M. K. Flow Induced Vibrations of Power and Process Plant Components: A Practical Workbooks . New York, NY: ASME Press, 2001.
- Collins, chapters 1.1 to 1.5.
- Collins, chapters 2.1 to 2.3.
- Collins, chapter 4.
- Collins, chapters 5.1 to 5.3.
- Collins, chapters 6.8 to 6.11.
- 7 · Fusion First Wall Description and Thermal Stresses · Collins, chapter 8.3.
- Collins, chapters 8.5 and 8.6.
- Collins, chapters 13.1 to 13.8.
- 12 · Fuel Pin Design (cont.) · Collins, chapter 5.4.
- Collins, chapters 6.2 and 6.8.
- 22 · Brittle Fracture · Collins, chapters 3.7 to 3.11.
Sources
- Course catalogue ↗Historical OpenCourseWare
- MIT OCW syllabus ↗
- MIT OCW readings ↗
- Historical MIT OpenCourseWare offering. Named reading entries and schedule topics are automatically extracted from the linked source pages.