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dc.contributor.advisorEl Kadiri, Haitham
dc.contributor.advisorShamsaei, Nima
dc.contributor.authorFuller, Robert William
dc.date2010
dc.date.accessioned2020-05-07T17:31:03Z
dc.date.available2020-05-07T17:31:03Z
dc.identifier.urihttps://hdl.handle.net/11668/16985
dc.description.abstractOne of prominent issues related to failures in nuclear power components is attributed to material degradation due the aggressive environment conditions, and mechanical stresses. For instance, reactor core support components, such as fuel claddings, are under prolonged exposure to an intense neutron field from the fission of fuel and operate at elevated temperature under fatigue loadings caused by start up, shut down, and unscheduled emergency shut down. Additionally, exposure to high-fluence neutron radiation can lead to microscopic defects that result in material hardening and embrittlement, which significantly affects the physical and mechanical properties of the materials, resulting in further reduction in fatigue life of reactor structural components. The effects of fatigue damage on material deterioration can be further exacerbated by the presence of thermal loading, hold-time, and high-temperature water coolant environments. In this study, uniaxial fatigue models were used to predict fatigue behavior based only on simple monotonic properties including ultimate tensile strength and Brinell hardness. Two existing models, the Bäumel Seeger uniform material law and the Roessle Fatemi hardness method, were employed and extended to include the effects of test temperature, neutron irradiation fluence, irradiation induced helium and irradiation induced swellings on fatigue life of austenitic stainless steels. Furthermore, a methodology to estimate fatigue crack length using a strip-yield based model is presented. This methodology is also extended to address the effect of creep deformation in a presence of hold- times, and expanded to include the effects of irradiation and water environment. Reasonable fatigue life predictions and crack growth estimations are obtained for irradiated austenitic stainless steels types 304, 304L, and 316, when compared to the experimental data available in the literature. Lastly, a failure analysis methodology of a mixer unit shaft made of AISI 304 stainless steel is also presented using a conventional 14-step failure analysis approach. The primary mode of failure is identified to be intergranular stress cracking at the heat affected zones. A means of circumventing this type of failure in the future is presented.
dc.publisherMississippi State University
dc.subject.otherirradiated stainless steel
dc.subject.otherfracture surface failure analysis
dc.subject.otherheat affected zones
dc.subject.otherintergrannular stress cracking
dc.subject.otherirradiation-induced helium
dc.subject.othervoid swelling
dc.subject.otherstainless steel
dc.subject.otherlife prediction
dc.subject.othercrack growth estimation
dc.subject.otherelevated temperature
dc.subject.othercreep-fatigue
dc.subject.otherneutron irradiation
dc.subject.otherStrip yield model
dc.titleFatigue Life and Crack Growth Predictions of Irradiated Stainless Steels
dc.typeDissertation
dc.publisher.departmentDepartment of Mechanical Engineering
dc.publisher.collegeBagley College of Engineering
dc.date.authorbirth1960
dc.subject.degreeDoctor of Philosophy
dc.subject.majorMechanical Engineering
dc.contributor.committeeNewman, James C.
dc.contributor.committeeHorstemeyer, Mark F.
dc.contributor.committeeLiu, Yucheng|
dc.date.defense2017-12-01


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