In-Situ TEM Self-Ion Irradiation and Thermal Aging of Optimized Zirlo

Abstract

The aggressive environments of nuclear reactors present a wide range of material difficulties due, in particular, to neutron radiation and elevated temperatures. Zirconium alloys are commonly used as nuclear fuel cladding due to their nuclear cross-section and high resistance to corrosion; however, neutron irradiation can result in hardening and swelling of… (More)

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