Zircaloy-2 Lined Zirconium Barrier Fuel Cladding

Zircaloy-2 Lined Zirconium Barrier Fuel Cladding

Auteur : CD. Williams, MO. Marlowe, RB. Adamson, SB. Wisner, RA. Rand, JS. Armijo

Date de publication : 1996

Éditeur : ASTM International

Nombre de pages : 19

Résumé du livre

The introduction of Zr-lined "barrier" fuel clad tubing by GE in the early 1980s to counter the pellet-clad interaction (PCI) failure mechanism in fuel for boiling water reactors provided a major improvement in fuel reliability and operational flexibility. While the frequency of fuel failures has been substantially reduced in the past decade, an increased tendency has been observed for failed fuel rods to exhibit post-failure degradation in the form of longer cracks that allow release of radioactive off-gas and contamination of the reactor coolant circuit with tramp fuel material. One factor involved in this degradation is hydriding of the cladding at a location remote from the initial perforation of the fuel rod. This local hydriding can lead to secondary crack initiation in the cladding when stressed by the fuel expansion accompanying a power increase.

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