NUCE 703 Aging Management of Nuclear Materials
This course provides an understanding of material aging and degradation in nuclear power plant environments: General and localized corrosion of metallic and concrete structures; Stress corrosion cracking (SCC) of the primary and secondary components; Irradiation assisted stress corrosion cracking (IASCC) of reactor vessel internals; Radiation embrittlement of reactor vessel. The proposed degradation mechanisms and mechanical, material, and environmental factors controlling the aging and degradation will be presented. Considering the previous operation experience in other nuclear power plants, the aging management of APR 1400 nuclear plants over the design life is discussed.
Prerequisite
Graduate level course on Nuclear Materials, Structural Integrity, and Chemistry.
Offered
Fall Spring