Structural Mechanics in Nuclear Power Technology

Lecture Notes

Notes by J. E. Meyer were internal documents and may not be available outside MIT.

Handouts summary (PDF)

LEC #	TOPICS	HANDOUTS
1	Introduction	World Nuclear Power Reactor Status
2-5	General Structural Equations Metal Design Methods and Mechanics Fundamentals Mechanics Fundamentals (cont.) and Pressure Values of LWRs Elastic Stress Analysis Elastic Stress Analysis (cont.)	Meyer, J. E. “Beam Theory.” Gill, S.S. The Stress Analysis of Pressure Vessels and Pressure Vessel Components. Burlington, MA: Elsevier, 1970, pp. 8-51. ISBN: 9780080067292. Olander, Donald R. “Appendix - Elasticity Theory.” In Fundamental Aspects of Nuclear Reactor Fuel Elements. Springfield, VA: Technical Information Center, Office of Public Affairs, Energy Research, and Development Administration, 1976. ISBN: 9780870790317.
6	Pressure Vessel Analysis Design Limits	ASME. “Cases of ASME Boiler and Pressure Vessel Code, Section III, Division I, Case N-47-32: Class I Components in Elevated Temperature Service.” ASME, New York, NY: August 5, 1994. Analysis of Cylindrical Shells Analysis of Spherical Shells ASME. “Criteria of the ASME Boiler and Pressure Vessel Code for Design by Analysis in Sections III and VIII, Division 2.” ASME, New York, NY: 1969. ASME. Article 2 and Article 4 in “Subsection A: Requirements for Class A Vessels, Section III, Rules for Construction of Nuclear Vessels, ASME Boiler and Pressure Vessel Code.” ASME, New York, NY: 1968. Ma, B. M. “Fundamental Radiation Effects on Materials.” Chapter 4 in Nuclear Reactor Materials and Applications. New York, Van Nostrand Reinhold Co., 1983.
7	Fusion First Wall Description and Thermal Stresses
8	Introduction to Plasticity/Damage Mechanics
9	The Deformation Prediction - Creep	Fish, R. L. “Creep-Rupture Properties of 20% Cold-Worked Type 316 Stainless Steel After High Fluence Neutron Irradiation.” Nuclear Technology 35 (1977): 9-11.
10-13	Fuel, Modeling and Design Fuel Pin Design Fuel Pin Design (cont.) Fuel Pin Design (cont.) Fuel Pin Design (cont.)	Olander, Donald R. “Modeling of the Structural Behavior of Fuel Elements and Assemblies.” Chapter 21 in Fundamental Aspects of Nuclear Reactor Fuel Elements. Springfield, VA: Technical Information Center, Office of Public Affairs, Energy Research, and Development Administration, 1976. ISBN: 9780870790317. Wallin, H. “Fuel Rod Modelling in Reactivity-Initiated Accidents at High Burnups: Transuranus Verses Frey.” PSI Science Report 4 (2001). “Extensive Programs Demonstrate ZIRLO Cladding Performance Benefits.” A Westinghouse brochure. (Available in hard copy only.) “Focus X5 and HTP X5 - A New Generation of Higher Enrichment PWR Fuel Assemblies.” A brochure from Siemens Nuclear Power.
14-16	Containment Designs Containment Design Containment Design (cont.) Containment Design / NDE	Buyukozturk, Oral. “Nonlinear Analysis of Reinforced Concrete Structures.” Computers and Structures 7 (1977): 149-156. Buyukozturk, Oral. “Imaging of Concrete Structures.” NDT&E International 31 (1998): 233-243. Pagnoni, T., J. Slater, R. Ameur-Moussa, and O. Buyukozturk. “A Nonlinear Three-Dimensional Analysis of Reinforced Concrete Based on a Bounding Surface Model.” Computers and Structures 43 (1992): 1-12.
17-21	Flow Induce Variations and Seismic Analysis Dynamic Analysis Dynamic Analysis (cont.) Quiz #1 Dynamic Analysis (cont.) Dynamic Analysis (cont.)	“Regulations and Standards for Design of Nuclear Facilities.” (Available in hard copy only.) Au-Yang, M. K. Flow-Induced Vibrations of Power and Process Plant Components: A Practical Workbook. New York, NY: ASME Press, 2001, pp. 404-412. ISBN: 9780791801666. Herron, R. “Summary of Important Flow-Induced Vibration Relations.” 2002. (Available in hard copy only.)
22-23	Radiation Effects on Materials and Components Brittle Fracture Brittle Fracture (cont.)	Raske, D. T., and C. F. Cheng. “Fatigue Crack Propagation in Types 304 and 308 Stainless Steel at Elevated Temperatures.” Nuclear Technology 34 (1977). Klueh, R. L. “Tensile Behavior of Neutron-Irradiated Martenistic Steels: A Review.” Nuclear Technology 102 (1993): 376-385.
24	Special Topic: PSA
25	Special Topic: Pressurized Thermal Shock
26	Term Paper Presentation
27	Term Paper Presentation (cont.)