Open AccessZirconium-Based Cladding Coating Technique for Oxidation, Corrosion and Embrittlement Reduction at High-Temperature: An Overview
Author(s) -
Mamoun I. A. Sagiroun,
Xiaoyan Cao
Publication year - 2019
Publication title -
iop conference series. materials science and engineering
Language(s) - English
Resource type - Journals
eISSN - 1757-899X
pISSN - 1757-8981
DOI - 10.1088/1757-899x/649/1/012008
Subject(s) - cladding (metalworking) , coating , materials science , corrosion , zirconium , embrittlement , metallurgy , hydrogen embrittlement , hydrogen , high temperature corrosion , zirconium alloy , oxide , oxygen , composite material , chemistry , organic chemistry
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.