Water chemistry and corrosion control of cladding and primary circuit components
2026-10-25 16:25:59
The document is available at IAEA website: https://www.iaea.org/publications/5819/water-chemistry-and-corrosion-control-of-cladding-and-primary-circuit-components
Corrosion is the principal life limiting degradation mechanism in nuclear steam supply systems, especially taking into account the trends to increase fuel burnup, thermal rate and cycle length. Primary circuit components of water cooled power reactors have an impact on Zr-based alloys behaviour due to crud (primary circuit corrosion products) formation, transport and deposition on heat transfer surfaces. Crud deposits influence water chemistry, radiation and thermal hydraulic conditions near cladding surface, and by this way-Zr-based alloy corrosion.
Proceedings of a Technical Committee meeting held in Hluboka nad Vltavou, Czech Republic, 28 September- 2 October 1998