Zirconium-Based Cladding Coating Technique for Oxidation, Corrosion and Embrittlement Reduction at High-Temperature: An Overview

Abstract

Fukushima Daichii accident attracted attention to one important factor for nuclear reactors safety – overcoming the high hydrogen emissions under accident conditions. The coating on zirconium-based cladding is one of significant approach to protecting the cladding materials from corrosion, accelerated oxidation at high temperature, embrittlement and (oxygen and hydrogen) uptake at aggressive water-chemical environments inside the core of Light Water Reactors (LWR). This paper presents a compact review of the most common technologies used to apply coating on zr-based cladding superstrates. The paper also discusses the coating materials, substrate preparations and recent advances in deposition techniques.