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Investigating Irradiation Creep of Zircaloy-4 Using In-Situ Proton Irradiation and Transmission Electron Microscopy

Product Number: Ed22-18344-SG

Author: Conor Gillen, Graeme Greaves, Rhys Thomas, Adeel Shaikh, Robert Harrison, Alistair Norris, Alistair Garner, Aidan Cole-Baker

Publication Date: 2022

$20.00

Zirconium alloys are used in civil nuclear reactors as fuel cladding, due to their relatively low neutron absorption cross section and being ability to maintain integrity during operation in a challenging environment – under elevated temperature, in corrosive water, under stress, and while being bombarded with different types of irradiation. In anisotropic materials, such as the hexagonal close packed Zr crystal structure, irradiation-induced defects diffuse at different rates in different crystallographic directions.

Products tagged with 'irradiation creep'

Investigating Irradiation Creep of Zircaloy-4 Using In-Situ Proton Irradiation and Transmission Electron Microscopy

Association for Materials Protection and Performance