Fatigue Behavior of Irradiated and Unirradiated Zircaloy and Zirconium
Auteur : RB. Adamson, MB. Reynolds, SB. Wisner
Date de publication : 1994
Éditeur : ASTM International
Nombre de pages : 22
Résumé du livre
As a normal part of reactor operation, Zircaloy components in the core of boiling water reactors (BWRs) are subjected to oscillating loads. It then becomes important to assess the fatigue behavior of core materials. These include Zircaloy-2 used as fuel cladding, zirconium used as liners in barrier fuel, and Zircaloy-4 used for fuel channels.