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Structural Mechanics in Nuclear Power Technology >> Content Detail



Lecture Notes



Lecture Notes

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

Handouts summary (PDF)


LEC #TOPICSHANDOUTS
1IntroductionWorld 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."

Amazon logo Gill, S.S. The Stress Analysis of Pressure Vessels and Pressure Vessel Components. Burlington, MA: Elsevier, 1970, pp. 8-51. ISBN: 9780080067292.

Amazon logo 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.

7Fusion First Wall Description and Thermal Stresses
8Introduction to Plasticity/Damage Mechanics
9The Deformation Prediction - CreepFish, 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.)

Amazon logo 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.)

Amazon logo 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.

24Special Topic: PSA
25Special Topic: Pressurized Thermal Shock
26Term Paper Presentation
27Term Paper Presentation (cont.)

 








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