Local Corrosion Behavior of Zr-1Nb Cladding in Water-Water Energetic Reactor Primary Coolants under Ambient Conditions and at High Temperature

host posted on May 26, 2011 16:27

A. Somogyi, A. Horvath, and G. Nagy et al.
Localized corrosion of the Zr-1Nb (E110) alloy was studied in solutions of a chemical composition similar to the primary coolant in Russian-type water-water energetic reactor (VVER)-type reactors. Cyclic voltammetry and chronoamperometry measurements were used to detect pit initiation, propagation ... [Corrosion 67, 066001 (2011)] published Wed Jun 01, 2011.

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Local Corrosion Behavior of Zr-1Nb Cladding in Water-Water Energetic Reactor Primary Coolants under Ambient Conditions and at High Temperature

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